1
English is not an official language of the Swiss Confederation. This translation is provided for information purposes only and has no legal force. Radiological Protection Ordinance (RPO) of 22 June 1994 (Status as of 1 January 2014) The Swiss Federal Council, on the basis of Article 47 paragraph 1 of the Radiological Protection Act (RPA)
of 22 March 19911, ordains: Chapter 1
General Provisions and Principles of Radiological Protection
Art. 1
Scope 1 This Ordinance applies to substances, articles and waste whose activity, concentration, contamination, dose rate or mass exceeds the values given in Annex 2.
2
The Ordinance also applies to: a. ionising radiation generators; b. equipment and installations capable of emitting stray ionising radiation in cases where the ambient dose rate at 10 cm from the surface, determined in accordance with Annex 5, is greater than 1 microsievert (µSv) per hour; c.2 …
3
For the implementation of radiological protection regulations, the values given in Annex 3 are applicable.
Art. 2
Exemptions
1
This Ordinance does not apply to the handling of raw materials of natural origin and nuclide composition that are not mentioned in Annex 2 and give rise to a dose of less than 1 mSv per year.3 AS 1994 1947
1
SR 814.50
2
Repealed by No I of the Ordinance of 17 Nov. 1999, with effect from 1 Jan. 2000 (AS 2000 107).
3
Amended by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
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2
This Ordinance does not apply to substances with a specific activity below the exemption limit specified in Annex 3 Column 9 and a local dose rate at 10 cm from the surface, after subtraction of background radiation, of more than 0.1 Sv per
hour, if it has been demonstrated to the supervisory authority that at no time will anyone accumulate an effective dose of more than 10 Sv per year.
3
Articles 125-127, 133 and 134 do not apply to activities requiring a licence under the Nuclear Energy Act of 21 March 20034.5
Art. 3
Mixtures
1
Mixtures of radioactive substances with inactive materials that are intended solely to circumvent this Ordinance are not permissible.
2
Subject to the provisions of Article 82, the supervisory authority may allow substances defined in Article 2 paragraph 2 to be mixed with inactive materials for recycling purposes, provided that the evidence required by that provision can be furnished.
Art. 4
Definitions
For the purposes of this Ordinance, the definitions given in Annex 1 are applicable.
Art. 5
Justification
1
An activity is justified within the meaning of Article 8 of the Radiological Protection Act (RPA) if the associated benefits clearly outweigh the radiation-related drawbacks and no alternative not involving radiation exposure is available which would be more favourable overall for humans and the environment.
2
Activities involving ionising radiation that give rise to an effective dose of less than 10
Sv per year for the persons concerned are deemed to be justified in any event.
Art. 6
Optimization
1
In the case of justified activities, radiological protection is deemed to be optimised if:
a. the various appropriate options have been assessed and compared in terms of radiological protection; b. it is possible to trace the steps in the decision-making process leading to the solution adopted;
c.6 the possibility of abnormal occurrences and the disposal of radiation sources have been taken into account.
4
SR 732.1
5
Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
6
Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
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2
The supervisory authority (Art. 136) may specify guidance values for optimisation on a case-by-case basis.
3
The principle of optimisation is deemed to be satisfied where activities do not lead in any cases to an effective dose of more than 100 Sv per year for occupationally exposed persons and more than 10 Sv per year for non-occupationally exposed persons.
Art. 7
7
The source-related dose guidance value must not be higher than the dose limit specified in Article 37.
2
The licensing authority (Art. 127) shall decide for which enterprises a sourcerelated dose guidance value is required and shall specify the value.
3
The source-related dose guidance value shall be specified in accordance with the principle of optimisation, with discharges of radioactive substances and direct radiation from other enterprises also being taken into account.
Art. 8
Research
1
The supervisory authorities may commission research projects concerning the effects of radiation and radiological protection, or participate in such projects.
2
The Paul Scherrer Institute (PSI) and other federal institutions shall place themselves as far as possible at the disposal of the supervisory authorities to carry out research projects concerning the effects of radiation and radiological protection.
3
The supervisory authorities shall consult each other before awarding a research contract.
Art. 9
8
The Federal Commission for Radiological Protection is a body providing advice on matters of radiological protection to the Federal Council, the Federal Department of Home Affairs (FDHA), the Federal Department of the Environment, Transport, Energy and Communications (DETEC), the Federal Department of Defence, Civil Protection and Sport (DDPS), interested public offices and the Swiss Accident Insurance Fund (Suva).
2
It has the following duties: a. It shall regularly inform the public about the radiological protection situation in Switzerland.
7
Amended by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
8
Amended by No I 2.7 of the Ordinance of 9 Nov. 2011 (Review of the ExtraParliamentary Commissions), in force since 1 Jan. 2012 (AS 2011 5227).
9
The name of this administrativ unit was amended by Art. 16 para. 3 of the Publications Ordinace of 17 Nov. 2004 (SR 170.512.1), in force since 1 Jan. 2015. This amendment has been made throughout the text.
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b. It provides advice on the following matters in particular: 1. the interpretation and appraisal of international recommendations in the field of radiological protection with regard to their application in Switzerland; 2. the elaboration and development of harmonised principles for the application of radiological protection regulations;
3. environmental radioactivity, the results of monitoring, their interpretation and the resultant radiation doses for the public.
3
It is composed of experts from academia and industry.
4
The Federal Council shall appoint its president, vice-president and other members based on proposals submitted by the FDHA.
5
The CPR may submit proposals for replacement and new members to the FDHA.
6
Administratively, it shall be attached to the Federal Office of Public Health (FOPH).
7
It shall work with the Federal Commission for NBC Protection (ComNBC), the Swiss Federal Nuclear Safety Commission (NSC) and the Emergency Organisation for Radioactivity (EOR). In doing so, it shall give particular consideration to joint tasks in the field of radiological protection.
8
The CPR and its committees may engage external experts for the examination of special issues. The CPR may issue assignments to its members or to external experts.
Chapter 2
Qualifications, Experts, Training and Continuing Education Section 1 Principle
Art. 10
1 Persons handling ionising radiation must undergo radiological protection training and continuing education in line with their activities and responsibility.
2
The training must ensure that such persons: a. are familiar with the basic rules of radiological protection; b. learn appropriate working methods; c. can apply the radiological protection regulations relevant to the activity concerned;
d. are aware of the risks of radiation exposure which may arise from malpractice;
e. are aware of the health risks involved in working with ionising radiation.
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Section 2
Qualifications for Medical Applications
Art. 11
10
The following shall be regarded as evidence that a person is duly qualified: a. for diagnostic applications of ionising radiation generators (radiation generators) and sealed radioactive sources, a Swiss medical degree or a foreign medical degree recognised as equivalent;
b. for diagnostic applications of radiation generators for chiropractic purposes, FOPH-recognised training, including an examination, in radiology and radiological protection.
2
For high-dose diagnostic procedures as specified in paragraph 1 letter a, evidence must also be furnished of a relevant Swiss specialist title, a foreign specialist title recognised as equivalent, or equivalent specialist training in the relevant diagnostic method.
3
The following shall be regarded as evidence that a person is duly qualified for diagnostic applications of radiation generators for dental purposes: a. a Swiss dental degree or a foreign dental degree recognised as equivalent; or b. a successfully completed examination as a cantonally certified dentist.
4
For persons serving as experts, the above provisions are without prejudice to Article 18.
Art. 12
11
The following shall be regarded as evidence that a person is duly qualified for therapeutic applications of radiation generators and sealed radioactive sources: a. a Swiss medical degree or a foreign medical degree recognised as equivalent;
b. a relevant Swiss specialist title, a foreign specialist title recognised as equivalent, or equivalent specialist training in the relevant therapeutic method;
c. appropriate practical hospital training; and d. FOPH-recognised training in radiological protection.
2
If the content of the training specified in paragraph 1 Letters c and d is already covered by the specialist training specified in paragraph 1 letter b, the FOPH may exempt physicians from additional training requirements.
10 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
11 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Art. 13
12
The following shall be regarded as evidence that a person is duly qualified for the application of unsealed radioactive sources: a. a Swiss medical degree or a foreign medical degree recognised as equivalent;
b. a relevant Swiss specialist title, a foreign specialist title recognised as equivalent, or equivalent specialist training in the relevant diagnostic and therapeutic method;
c. appropriate practical hospital training; and d. FOPH-recognised training in radiological protection for the medical application of radionuclides.
2
If the content of the training specified in paragraph 1 Letters c and d is already covered by the specialist training specified in paragraph 1 letter b, the FOPH may exempt physicians from additional training requirements.
Art. 14
Veterinary surgeons
1
A Swiss veterinary degree or a foreign veterinary degree recognised as equivalent shall be regarded as evidence that a person is duly qualified for veterinary applications of ionising radiation.13 2 For persons serving as experts, the above is without prejudice to Article 18.
Art. 15
14
1
For the following occupational groups, FOPH-recognised training, including a final examination, in radiological protection shall be regarded as evidence that a person is duly qualified: a. medical radiation technologists (MTRA); b. medical practice assistants, dental assistants and dental hygienists; c. veterinary practice assistants; d. other medical personnel who are involved in medical radiography or have radiological protection responsibilities vis-à-vis other people.
2
If training as specified in paragraph 1 is already provided as part of training under the Vocational Training Act of 13 December 200215, the appropriate certificate or a foreign certificate recognised as equivalent shall be regarded as evidence that a person is duly qualified.
12 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
13 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
14 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
15 SR
412.10
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Section 3
Qualifications for other Applications
Art. 16
Requirements for qualifications 1
For persons in research, teaching, medical analysis, industry, nuclear facilities, transport and trade who have radiological protection responsibilities vis-à-vis other people, radiological protection training, including an examination, recognised by the supervisory authority shall be regarded as evidence that they are duly qualified.
2
If the risk involved in an activity is low, the supervisory authority may in individual cases waive the examination requirement.
Art. 17
Qualifications for service in emergency organizations 1
Persons belonging to an emergency organisation, such as the police, fire brigade, civil protection, emergency management teams or medical services, who have radiological protection responsibilities in the event of a radiological emergency must be trained in line with their function and activities.
2
Training shall be coordinated by the Federal Office for Civil Protection.16 Section 4
Experts
Art. 18
1 Experts as specified in Article 16 RPA must demonstrably have undergone training in radiological protection, including an examination, which is appropriate to their activities and responsibilities and recognised by the supervisory authority, and have a knowledge of radiological protection legislation.
2
Physicians, veterinary surgeons and chiropractors who have been trained as specified in Articles 11-14 and who serve as experts must have undergone FOPHrecognised training, including a final examination, in radiological protection and medical applications of ionising radiation.17 3
If the content of the training specified in paragraph 1 or 2 is already covered by the training or specialist training specified in Articles 11-16, the supervisory authority may exempt the person concerned from additional training requirements.18 4 If the risk involved in an activity is low, the supervisory authority may in individual cases waive the examination requirement.
5
Dentists and cantonally certified dentists who have been trained as specified in Article 11 paragraph 3 shall be regarded as experts in their field of activity.19 16 Amended by Art. 10 No 2 of the Ordinance of 18 June 2008 on the Federal Commission for NBC Protection, in force since 15 July 2008 (AS 2008 3153).
17 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
18 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Section 5
Training and Continuing Education Courses; Financial Assistance
Art. 19
Training and continuing education courses 1
The supervisory authorities and the PSI shall organise radiological protection courses as required.
2
Within the scope of their responsibilities, the FDHA and DETEC may request other agencies or institutions to organise radiological protection courses.20
a21 Training and continuing education registry 1
The licensing authority may maintain a registry of persons who have completed training and continuing education courses to attain expertise in the area for which a licence is granted.
2
The purpose of the registry is to simplify the administrative procedures required for the granting of licences.
3
The following data shall be stored in the registry: a. name, first name, maiden name; b. date of
birth;
c. occupational
training;
d. type, provider and date of radiological protection courses; e. date of recognition of equivalence in the case of training undergone abroad.
4
All entries relating to a person shall be deleted from the registry after 80 years, calculated from the date of birth.
5
The data specified in paragraph 3 on persons who have successfully completed training and continuing education courses shall be transmitted by the recognised training institutions to the competent licensing authority.
Art. 20
Financial assistance for third-party training and continuing education courses 1
Within the limits of their approved budgets, the FOPH or the Swiss Federal Nuclear Safety Inspectorate (ENSI) may provide financial assistance for training or continuing education courses in radiological protection organised by third parties (colleges, professional organisations).22
19 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
20 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
21 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
22 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
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2
Financial assistance shall only be provided if the training has been recognised by the supervisory authority.
3
Financial assistance shall be calculated so that, taken together with other revenues, it does not exceed the course organiser's documented costs.
Section 6
Delegation to the FDHA and DETEC; Recognition of Training undergone abroad
Art. 21
1 Within the scope of their responsibilities, the FDHA and DETEC shall define: a. the requirements for recognition of training or a course specified in Articles 11, 12, 13, 15, 16 and 18;
b. the conditions for service in emergency organisations as specified in Article 17.
2
They may define the content of examinations and the examination procedure.
3
They shall define the activities that qualified persons are entitled to perform.
Art. 22
23
Chapter 3
Medical Applications Section 1
Principles
Art. 23
Patient information and consent Where radiation is to be used for diagnostic or therapeutic applications, patient information and consent shall be governed by the relevant federal regulations concerning the protection of life, limb and personality and by the provisions of cantonal health law.
Art. 24
Protection of the patient The licence holder must ensure that, for every medical radiation generator, the elements required to protect the patient are in place and are used.
23 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Art. 25
Record-keeping
The licence holder must record therapeutic, high-dose or interventional diagnostic procedures in such a way that the radiation dose received by the patient can also be determined at a later date.
Art. 26
Fluoroscopy
1
Fluoroscopy may only be performed by a physician; for radiation field verification in radiotherapy, fluoroscopy may also be performed by a MTRA under the direction of a physician.
2
For this purpose, only systems with an image intensifier and automatic dose rate control may be used.
3
It is not permissible to perform fluoroscopic examinations for fitness tests and in particular for pre-enrolment insurance assessments.
Section 2
Special Examinations
Art. 27
Radiological screening 1
Radiological screening may only be carried out if it is justified on medical and epidemiological grounds.
2
It is not permissible to use fluoroscopy or photofluorography for screening purposes.
Art. 28
24
The conduct of research projects involving radiation sources requires authorisation from the responsible ethics committee in accordance with Article 45 paragraph 1 letter a of the Human Research Act of 30 September 201125, and from the Swiss Agency for Therapeutic Products in accordance with Article 54 paragraphs 1 and 2 of the Therapeutic Products Act of 15 December 200026.
2
In the calculation or estimation of the dose, all radiation sources to which the persons concerned are exposed must be taken into account. The uncertainty factor is to be taken into account in the final result.
3
In research projects where no direct benefit is expected for the participants, the effective dose must not exceed the limit of 5 mSv per person per year.
4
In exceptional cases, for research projects where no direct benefit is expected for the participants, the limit may be up to 20 mSv per person per year, with consideration being given to age, fertility, life expectancy or health status, provided that this is absolutely essential for methodological reasons.
24 Amended by Annex 6 No 3 of the Ordinance of 20 Sept. 2013 on Clinical Trials, in force since 1 Jan. 2014 (AS 2013 3407).
25 SR
810.30
26 SR
812.21
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Persons who have already participated in a research project involving radiation sources where no direct benefit is expected and were exposed to an effective dose of more than 5 mSv per year must not be included in any further research projects in the following 12 months.
Section 3
Special Provisions for Radiopharmaceuticals27
Art. 29
28
Art. 30
29
Placing on the market and use of radiopharmaceuticals 1
Radiopharmaceuticals may only be placed on the market or used in humans if they meet the requirements of the HMG30. Approval is required from the FOPH for: a. the registration of radiopharmaceuticals under Article 9 paragraph 1 HMG; b. the simplified registration of radiopharmaceuticals under Article 14 HMG; c. the licensing of radiopharmaceuticals for a limited period under Article 9 paragraph 4 HMG.
2
The FOPH shall grant approval if the quality controls for the radiopharmaceutical are carried out in accordance with the current state of science and technology.
3
Radiopharmaceuticals must be labelled as such and include at least the following information:
a. the product name; b. the hazard warning symbol in accordance with Annex 6; c. the radionuclides, their chemical form and activity, as well as other radionuclides present and their activity on a particular date;
d. other chemical forms of the radionuclides present; e. non-radioactive substances contained as additives; f.
earliest and latest dates for use (expiry date).
Art. 31
Quality control
1
Anyone who produces radiopharmaceuticals or uses them in humans must regularly carry out quality controls.
27 Repealed by Annex 6 No 3 of the Ordinance of 20 Sept. 2013 on Clinical Trials, with effect from 1 Jan. 2014 (AS 2013 3407).
28 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
29 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
30 SR
812.21
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2
The FOPH may take samples of radiopharmaceuticals at any time in order to determine whether the requirements specified in Article 30 are still met.31 For this purpose, it may engage specialist laboratories.
a32 Preparation and synthesis of radiopharmaceuticals 1
The preparation and synthesis of finished radiopharmaceutical products must comply with the cGRPP33 Guidelines issued in March 2007 by the EANM34.
2
The preparation and synthesis of radiopharmaceuticals with increased hazard potential must be carried out under the direction of a person responsible for technical matters who fulfils the professional requirements specified in Article 5 paragraph 4 letter d of the Ordinance of 17 October 200135 on Establishment Licences or has completed equivalent training. Radiotherapeutic products from radiolabelling kits registered in Switzerland may be prepared under the direction of a person who, while not fulfilling these requirements himself/herself, has been instructed and is supervised by a person responsible for technical matters.
Art. 32
36
The Expert Commission for Radiopharmaceuticals (ECRP) shall advise Swissmedic and the FOPH on radiopharmaceutical matters. It shall prepare expert reports on:
a. applications for the authorisation of radiopharmaceuticals; b. safety-related questions connected with radiopharmaceuticals.
2
The ECRP is comprised of specialists from the fields of nuclear medicine, pharmaceutics, chemistry and radiological protection.
3
The Federal Council shall appoint its president, vice-president and other members based on proposals submitted by the FDHA.
4
The FOPH und Swissmedic may submit proposals for replacement and new members to the FDHA.
31 Amended by No II 7 of the Ordinance of 17 Oct. 2001, in force since 1 Jan. 2002 (AS 2001 3294).
32 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
33 Guidelines on Current Good Radiopharmacy Practice (cGRPP) in the Preparation of Radiopharmaceuticals, version 2, March 2007.
34 European Association of Nuclear Medicine The EANM Guidelines referred to in this Ordinance can be obtained from the Federal Office of Public Health, Radiological Protection Division, CH-3003 Bern, or downloaded from the EANM website (www.eanm.org).
35 SR
812.212.1
36 Amended by No I 2.7 of the Ordinance of 9 Nov. 2011 (Review of the ExtraParliamentary Commissions), in force since 1 Jan. 2012 (AS 2011 5227).
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Chapter 4
Protection of Exposed Persons Section 1
Dose Limitation
Art. 33
Occupationally exposed persons 1
The licence holder shall designate all occupationally exposed persons within the enterprise and inform them of their special status as occupationally exposed persons.
2
In particular, the licence holder shall inform them of: a. the radiation doses to be expected in the course of their work; b. the dose limits applicable for them.
3
The licence holder must not employ persons under 16 years of age as occupationally exposed persons.
Art. 34
Dose limits
1
The dose limits specified in Articles 35-37 apply to the dose from controllable radiation exposure accumulated in a calendar year.
2
They are not applicable for: a. exposures of patients for diagnostic or therapeutic purposes; b. exposures in exceptional situations as specified in Article 20 RPA; c. exposures to natural radiation from a source that is not amenable to control; d. the exposure of persons helping to support and care for patients in a nonoccupational capacity.
3
For the calculation of dose limits, exposures due to natural radiation or to any medical measures shall not be taken into account, subject to the consideration of radon exposure as specified in Article 110 paragraph 3.
Art. 35
Dose limit for occupationally exposed persons 1
For occupationally exposed persons, the effective dose must not exceed the limit of 20 mSv per year, subject to the provisions of Article 36.
2
For occupationally exposed persons carrying out important tasks, the dose limit by way of exception and with an authorisation granted by the supervisory authority shall be up to 50 mSv per year, provided that the cumulative dose for the last five years including the current year is less than 100 mSv.
3
For occupationally exposed persons, the equivalent dose must not exceed the following limits:
a. for the lens of the eye, 150 mSv per year; b. for the skin, hands and feet, 500 mSv per year.
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Art. 36
Protection of young people and women 1
For occupationally exposed persons aged 16-18 years, the effective dose must not exceed the limit of 5 mSv per year.
2
For occupationally exposed women, from the time when the pregnancy becomes known until the end of the pregnancy, the equivalent dose to the surface of the abdomen must not exceed 2 mSv and the effective dose from internal exposure must not exceed 1 mSv.
3
Breast-feeding women must not perform any work with radioactive substances involving a risk of intake or radioactive contamination.
Art. 37
Dose limit for non-occupationally exposed persons For non-occupationally exposed persons, the effective dose must not exceed the limit of 1 mSv per year.
a37 Diagnostic reference levels 1
The FOPH shall issue recommendations on radiation doses for diagnostic procedures in the form of diagnostic reference levels. In doing so, it shall take into account data from national surveys and international recommendations.
2
In the case of high-dose procedures, the person who is qualified as specified in Article 11 must record the relevant dose or activity levels in the patient's file and regularly compare these with the associated reference level. A justification is to be given if reference levels are exceeded.
3
In the case of high-dose diagnostic radiological procedures, at the request of the FOPH, data on the following is to be recorded for a month and made available to the FOPH: a. time and type of examination; b. radiation dose or activity levels; c. equipment specifications;
d. age and sex of patients.
Art. 38
Measures to be taken if dose limits are exceeded 1
Anyone who suspects or observes that a dose limit has been exceeded must notify the supervisory authority immediately.
2
The licence holder must initiate an investigation as specified in Article 99.
3
The supervisory authority shall adopt the necessary measures.
4
If the dose limit for occupationally exposed persons is exceeded, the person concerned may accumulate an effective dose of no more than 1 mSv during the rest of
37 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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the year, subject to the granting of an authorisation by the supervisory authority in accordance with Article 35 paragraph 2.
Art. 39
Medical surveillance in the event of dose limits being exceeded 1
Any person who, in the course of a year, has received an effective dose of more than 250 mSv, an equivalent dose to the skin or bone surface of more than 2500 mSv, or an equivalent dose to any other organ of more than 1000 mSv is to be placed under medical surveillance.
2
The physician shall inform the person concerned and the supervisory authority of the results of the investigation and propose measures to be adopted. If the person concerned is an employee, the physician shall notify Suva38.
3
The physician shall disclose to the supervisory authority: a. data concerning any early effects detected; b. data concerning illnesses or special predispositions making it necessary to declare the person unfit for radiation work; c. biological dosimetry data.
4
The supervisory authority shall retain this data for as long as the person concerned remains occupationally exposed.
5
The supervisory authority shall take the necessary measures in the case of persons who are not in employment. It may order a temporary or permanent exclusion from work.
Art. 40
Exceptional radiation exposures 1
The dose limits specified in Articles 35-37 may be exceeded in efforts to manage abnormal occurrences in accordance with Article 97, if this is necessary to protect the public and in particular to save human lives.
2
For persons with special obligations under Article 120, the values specified in Article 121 paragraph 1 are applicable.
Art. 41
Flight personnel
1
On commencing flight duties, jet aircraft personnel are to be informed by the operator of the exposure occurring in the course of their work.
2
Pregnant women may request exemption from flight duties.
38 Designation in accordance with No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107). This amendment has been applied throughout the text.
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Section 2
Determination of Radiation Doses (Dosimetry)
Art. 42
Dosimetry in occupationally exposed persons 1
In occupationally exposed persons, exposure to radiation is to be determined individually in accordance with Annex 5 (personal dosimetry).
2
External exposure is to be determined every month.
3
The supervisory authority shall define on a case-by-case basis how and at what intervals internal exposure is to be determined. In doing so, it shall take into account the working conditions and the type of radionuclides used.
4
The supervisory authority may request the use of a second, independent dosimetry system fulfilling an additional function.
5
The supervisory authority may grant exemptions from paragraphs 1 and 2 in cases where an additional or another appropriate dose monitoring system is available.
Art. 43
Duties of the licence holder 1
The licence holder must have the exposure of all the occupationally exposed persons working in the enterprise determined by an approved personal dosimetry laboratory. The licence holder may also carry out screening measurements in-house to detect internal exposure.
2
The licence holder must inform these persons of the results of dosimetry.
3
The licence holder must bear the costs of dosimetry.
4
The licence holder must provide Suva with the operational, personal and dosimetry data required for preventive occupational medicine.
Art. 44
Dosimetry in non-occupationally exposed persons39 1
Exposure of non-occupationally exposed persons shall be determined via monitoring of the off-site limits specified in Article 102 or by modelling. In isolated cases, exposure may also be determined individually.
2
For non-occupationally exposed persons within an enterprise, the supervisory authority shall define the method for determining exposure on a case-by-case basis.
3
Exposure is to be determined in accordance with Annexes 3, 4, 5 and 7.40 39 Amended by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
40 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Section 3
Personal Dosimetry Laboratories
Art. 45
Approval and requirements 1
Anyone wishing to operate a personal dosimetry laboratory must obtain official approval.
2
Approval shall be granted if the following requirements are met: a. The manager responsible for the personal dosimetry laboratory must have been trained as an expert in radiological protection, have a degree in a scientific or technical discipline from a university or university of applied sciences, and have a practical knowledge of the measurement technique concerned.
b. The personal dosimetry laboratory must be located in Switzerland and have an appropriate organisation with a sufficient number of adequately trained staff.
c. The measurement system must be in line with the current state of technology and be linked to national or international standards (traceability41).
3
If a personal dosimetry laboratory is accredited for this activity, it shall be assumed that the requirements specified in paragraph 2 are met.
Art. 46
Approval procedure and term 1
The competent authority shall determine, by means of an inspection and a technical review, whether the requirements for approval are met. It may engage third parties for this purpose.
2
Traceability in accordance with Article 45 paragraph 2 letter c shall be defined on a case-by-case basis by the Swiss Federal Institute of Metrology (METAS) and verified by a body recognised by METAS.42 3 Approval shall be valid for five years.
Art. 47
Competent authorities 1
The following authorities are responsible for approval: a. the FOPH, in cases where a personal dosimetry laboratory wishes to operate wholly or largely within the area supervised by the FOPH or Suva; b.43 the ENSI, in cases where a personal dosimetry laboratory wishes to operate wholly or largely within the area supervised by this authority.
41 Designation in accordance with No I of the Ordinance of 17 Nov. 1999, in force since.
1 Jan. 2000 (AS 2000 107). This amendment has been applied throughout the text.
42 Amended by No I 5 of the Ordinance of 7 Dez. 2012 (New Legal Basis for Metrology), in force since 1 Jan. 2013 (AS 2012 7065).
43 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
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2
In cases where a personal dosimetry laboratory wishes to operate in various areas, the competent authorities shall jointly decide which of them is to be responsible for approval.
3
The competent authorities must not operate any personal dosimetry laboratories themselves.
Art. 48
Information to be notified by the licence holder The licence holder must notify to the appointed personal dosimetry laboratory the personal details (name, first name, maiden name, date of birth, social insurance [AHV] number, sex) of the occupationally exposed persons working in the enterprise and the data relating to the enterprise (name and address).
Art. 49
Information to be notified by the personal dosimetry laboratory 1
Within a month after the end of the monitoring period, the personal dosimetry laboratory must notify the data specified in Article 48 and the radiation doses determined to the licence holder and to the Central Dose Registry in a form prescribed by the FOPH (Art. 53). Data from the area supervised by the ENSI is also to be notified directly to this authority.44 2 If the effective dose determined over the monitoring period is greater than 2 mSv or the equivalent dose to an organ is greater than 10 mSv, this must be reported by the personal dosimetry laboratory to the licence holder and to the competent supervisory authority (FOPH or Suva) no later than ten calendar days after receipt of the dosimeter.
3
In cases where it is suspected that a dose limit has been exceeded, the personal dosimetry laboratory must report the result to the licence holder within 24 hours. If the dose exceeds the limit specified in Article 35 or 36, the personal dosimetry laboratory must inform the competent supervisory authority immediately. It shall also inform Suva if the case concerns an employee.
Art. 50
Duties of the personal dosimetry laboratory 1
The personal dosimetry laboratory must retain the dose measurements and personal details, as well as all the raw data required for subsequent calculation of the notifiable doses, for a period of two years after submission to the Central Dose Registry.
2
In accordance with the instructions of the competent authority, it must participate at its own expense in intercomparison measurements.
Art. 51
Duty of confidentiality and data protection 1
The personal dosimetry laboratory must not disclose the personal details or results of dosimetry to anyone other than the subject concerned, the client, the supervisory authority, the licensing authority and the Central Dose Registry.
44 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
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2
With regard to the duty of confidentiality and data protection, the persons engaged to carry out dosimetry are subject to the regulations applicable for federal civil servants.
Art. 52
Technical provisions
1
After consulting METAS, the FDHA and DETEC shall jointly issue technical provisions for personal dosimetry.
2
The technical provisions shall specify in particular: a. minimum requirements for measurement systems; b. minimum requirements for measurement accuracy in routine operations and for intercomparison measurements; c. standard models for calculation of radiation doses; d. the format for notifications.
Section 4
Recording of Radiation Doses
Art. 53
Central Dose Registry 1
The FOPH shall maintain a registry of the doses accumulated by occupationally exposed persons in Switzerland (Central Dose Registry).
2
The purpose of the Central Dose Registry is: a. to make it possible for the supervisory authorities to review at any time the doses accumulated by all occupationally exposed persons in Switzerland; b. to permit statistical analyses; c. to ensure that the data is retained.
Art. 54
Data processed
1
The following data may be stored in the Central Dose Registry: a. name, first name and maiden name; b. date of
birth;
c. social insurance (AHV) number; d. sex; e. name and address of the enterprise; f. dose measurements;
g. occupational
group.
2
For persons working in Switzerland only temporarily, the doses accumulated in Switzerland shall be recorded. For other occupationally exposed persons, the doses accumulated abroad shall also be recorded.
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3
The supervisory authorities and the occupational medicine unit of Suva shall have direct access to data in the area for which they are responsible.
Art. 55
Retention and publication of data 1
The FOPH must retain all data recorded in the Central Dose Registry for 100 years.
2
The supervisory authorities shall produce annual reports on the results of personal dosimetry.
3
The reports shall be published by the FOPH.
Art. 56
Use of data for research projects 1
The FOPH may use, or disclose to third parties, data stored in the Central Dose Registry for research projects concerning the effects of radiation and radiological protection.
2
The FOPH shall only make data available in an anonymised form, unless the disclosure of personal details is indispensable to the research project.
3
The data shall be made available if: a. the recipient cannot carry out a particular research project without it; b. the recipient guarantees compliance with data protection.
4
The recipient may only use the data in connection with the research project. He/she may only transmit it to third parties in connection with the research project.
5
The recipient must anonymise or destroy the data if it is no longer required for the research project. If a follow-on project is planned, the data must be deposited with the FOPH.
Art. 57
Personal dose record form 1
The FOPH shall issue a personal dose record form.
2
The approved personal dosimetry laboratories must distribute this dose record form free of charge to occupationally exposed persons.
3
The licence holder must record the doses accumulated. The personal dose record form, with the doses entered, must be handed over to occupationally exposed persons when they leave the employment of the licence holder or before they undertake an assignment at another enterprise.
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Chapter 5
Handling of Radiation Generators and Radioactive Sources Section 1 Controlled Areas
Art. 58
1 The licence holder must establish controlled areas to limit and monitor radiation exposure.
2
Controlled areas are to be clearly delimited and marked with signs as specified in Annex 6.
3
The licence holder must control access to and presence in controlled areas.
4
Within the scope of their responsibilities, the FDHA and DETEC shall issue the necessary regulations governing behaviour in controlled areas.45 Section 2
Shielding and Location of Radiation Generators and Radioactive Sources
Art. 59
46
1
The room or area in which stationary radiation generators or radioactive sources are operated or stored shall be designed and shielded in such a way that, taking into account the frequency of use: a. in places situated within the premises but outside controlled areas, where non-occupationally exposed persons may be present, the local dose does not exceed 0.02 mSv per week; in places where people are not continuously present, this value may be exceeded by up to a factor of five; b. in places outside the premises, the off-site limits specified in Article 102 are not exceeded.
2
With the agreement of the supervisory authority, in rarely occupied places outside controlled areas within continuously monitored premises, where exceeding the dose limit specified in Article 37 is prevented by appropriate measures, the ambient dose rate may be up to 0.0025 mSv per hour.
Art. 60
Location of non-medical radiation generators and radioactive sources 1
Radiation generators for non-medical applications and irradiators used for nondestructive material testing (macrostructural analysis) must be installed in an irradiation room or equipped with a full protection system.
45 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
46 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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2
The irradiation room must meet the following requirements: a. The control unit must be located outside the irradiation room.
b. Access to the irradiation room must be prevented by suitable devices while the installation is in operation. Egress must be assured at all times.
c. The operating state of the installation must be clearly indicated by an acoustic or visual signal in the irradiation room, at the entrance to the irradiation room and at the control unit.
3
The supervisory authority may grant exemptions from paragraph 1 in cases where a radiation generator or irradiator cannot be operated in an irradiation room. The ambient dose at the perimeter of the controlled area must not exceed 0.1 mSv per week outdoors and 0.02 mSv per week indoors.
4
If a radiation generator or irradiator is used outside an irradiation room, it must be ensured that the operator can call on another person for assistance at all times.
5
Analytical and other X-ray systems and units containing sealed radioactive sources for radiometric measurements such as level meters, level controllers and thickness gauges must be installed in a controlled area or equipped with a full protection system.
Art. 61
Location of medical radiation generators and radioactive sources 1
The FDHA shall define the requirements for the location of medical radiation generators. In particular, it shall specify structural measures and the basis for calculations.
2
The time spent by people in the vicinity of patients to whom radioactive sources have been administered for therapeutic purposes is to be kept to a minimum. The physician responsible for the patient shall ensure that the area around the patient is appropriately monitored.
3
The FDHA shall define: a. the requirements for rooms where radioactive sources are administered; b. the radiological protection measures for the care and accommodation of patients receiving such therapy.
Art. 62
Technical requirements The FDHA and DETEC shall specify the technical requirements for radiation generators and radioactive sources and define the protective measures required for the handling thereof.
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Section 3
Radiation Measuring Devices
Art. 63
Radiation measuring devices 1
The licence holder must ensure that the enterprise is equipped with the necessary number of suitable radiation measuring devices.
2
In rooms or areas where radioactive sources are handled, suitable radiation measuring devices must be available at all times to monitor dose rates or contamination.
3
If non-medical radiation generators or irradiators for macrostructural analysis of materials are operated without fixed shielding or outside irradiation rooms, operating staff must have at their disposal, in addition to a personal dosimeter, a radiation measuring device incorporating a warning system.
4
If the position and dimensions of shielding elements can be altered or if barriers are to be erected to demarcate a controlled area, at least one suitable radiation measuring device with a direct read-out must be available at the radiation generator to measure ambient dose rates.
Art. 64
47
Measuring instruments for ionising radiation are governed by the Measuring Instruments Ordinance of 15 February 200648 and the implementing provisions issued by the Federal Department of Justice and Police in consultation with the FDHA and the FOEN. 2
The licence holder must carry out functional testing of measuring instruments for ionising radiation at appropriate intervals, using suitable test sources.
3
The supervisory authority may require the licence holder to participate in intercomparison measurements.
Section 4
Design and Labelling of Sealed Radioactive Sources
Art. 65
Design
1
With regard to design, sealed radioactive sources must be in line with the current state of science and technology.49 2 For sealed radioactive sources, the radionuclides selected must be chemically as stable as possible.
3
If sealed radioactive sources are used exclusively as gamma emitters, shielding must be provided which prevents the escape of primary particle radiation.
47 Amended by No I of the Ordinance of 7 Dec. 2012, in force since 1 Jan. 2013 (AS 2012 7157).
48 SR
941.210
49 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Art. 66
Labelling
1
Sealed radioactive sources and their containers are to be labelled in such a way as to permit identification of the source at any time. The supervisory authority may grant exemptions in cases where labelling cannot be affixed.
2
The radionuclide, activity, date of manufacture and measurement, and classification according to ISO50 291951 must be immediately apparent or ascertainable from the labelling.52
Art. 67
Testing
1
Every sealed radioactive source must be tested for leak tightness and absence of contamination by a body accredited for this task or recognised by the supervisory authority.
2
Every sealed radioactive source whose activity is greater than 100 times the licensing limit specified in Annex 3 Column 10 must undergo type testing in accordance with accepted technical standards and be classified accordingly.53 3
In justified cases, the supervisory authority may grant exemptions from paragraphs 1 and 2 or require additional quality tests.
Art. 68
Use and operation
1
For irradiators and protective containers with sealed radioactive sources which are handled outside irradiation rooms, with shielding in place, the maximum ambient dose rate at 1 m from the surface shall be 0.1 mSv per hour.
2
When not in use, sealed radioactive sources for non-destructive material testing must be kept in a protective container (irradiator). The useful beam from the radioactive source in the extended position must be collimated to the required field size.
Section 5
Working Areas for the Handling of Unsealed Radioactive Sources
Art. 69
Working areas
1
Work with unsealed radioactive sources whose activity exceeds the licensing limit specified in Annex 3 Column 10 must be carried out in working areas.
50 International
Organization for Standardization The ISO technical standards referred to in this Ordinance can be consulted free of charge at the Federal Office of Public Health, CH-3003 Bern, or purchased from the Swiss information centre for technical rules (switec), Bürglistrasse 29, CH-8400 Winterthur or
from the website of the Swiss Association for Standardization (www.snv.ch).
51 ISO 2919:1999, 2nd edition, Radiation protection - Sealed radioactive sources - General requirements and classification.
52 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
53 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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2
Working areas are to be established in separate rooms reserved for these purposes.
3
The working areas shall be classified into the following types, according to the activities handled per operation or per day: a. Type C: An activity from 1 to 100 times the licensing limit specified in Annex 3 Column 10;
b. Type B: An activity from 1 to 10 000 times the licensing limit specified in Annex 3 Column 10;
c. Type A: An activity from one times the licensing limit to an upper limit that shall be defined in the licensing procedure.
4
For activities not involving a risk of inhalation, the supervisory authority may define the type of working area on a case-by-case basis, taking into account the risk of intake.
5
The FDHA and DETEC shall issue the necessary regulations concerning protective measures for the handling of unsealed radioactive sources.54
Art. 70
Exceptions
1
The supervisory authority may allow exceptions to Article 69 paragraph 2 on operational grounds, provided that radiological protection is assured.
2
Where handling involves a low risk of intake, the supervisory authority may in exceptional cases increase the values specified in Article 69 paragraph 3 by up to a factor of 10, provided that radiological protection is assured.
3
The supervisory authority may increase the values specified in Article 69 paragraph 3 by up to a factor of 100 if a working area is only used for storage of radioactive sources.
4
The supervisory authority may grant exemptions from Article 69 paragraph 1 in facilities with a zoning plan.55
Art. 71
Guidance values for contamination 1
The guidance values specified in Annex 3 Column 12 are applicable for the contamination of skin, underwear, clothing, materials and surfaces outside controlled areas.
2
If in accessible parts of controlled areas the contamination of materials and surfaces is greater than ten times the guidance value specified in Annex 3 Column 12, decontamination measures must be implemented or other appropriate protective measures adopted.
54 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
55 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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3
If, in a controlled area, part of the contamination will remain attached to the surface under foreseeable conditions of handling, the guidance values specified in Annex 3 Column 12 shall only apply to the removable contamination.
Art. 72
Treatment and release of working areas after discontinuation of work 1
Working areas where the handling of unsealed radioactive sources has been discontinued and if necessary also the surrounding areas, including all installations and the remaining material, must be decontaminated by the licence holder at least to such an extent that the guidance values specified in Annex 3 Column 12 and the offsite limits specified in Article 102 are not exceeded.
2
The licence holder must submit a report to the supervisory authority on the measures carried out in accordance with paragraph 1.
3
The licence holder may only use the working areas concerned for other purposes after they have been released by the supervisory authority.
Section 6
Operation and Maintenance of Radiation Generators and Radioactive Sources56
Art. 73
Principle
1
The licence holder must ensure that radiation generators are comprehensively inspected and serviced at appropriate intervals.
2
The supervisory authority shall specify the intervals for non-medical radiation generators on a case-by-case basis.
3
The licence holder must regularly inspect the condition of sealed radioactive sources and keep records of the inspections.
Art. 74
Medical radiation generators and medical equipment containing sealed radioactive sources 1
The licence holder must ensure that an acceptance test is carried out before a medical radiation generator or medical equipment containing sealed radioactive sources is used for the first time.
2
After commissioning of the medical radiation generator or medical equipment containing sealed radioactive sources, the licence holder must implement a regular quality assurance programme.
3
Medical X-ray systems and medical equipment containing sealed radioactive sources must undergo a condition inspection during servicing at least once every six 56 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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years, and radiotherapy systems operating at a voltage of more than 100 kV and irradiators at least once a year.57 4 In the case of radiotherapy systems or irradiators, the elements relevant to safety and those determining the dose must be inspected at least once a year and whenever a component is changed which could affect the dose rate. The inspection of the dosedetermining elements must be carried out under the supervision of a medical physicist with certification in medical radiophysics from the Swiss Society of Radiobiology and Medical Physics or other equivalent training.58 5 For the operation of medical accelerators and medical irradiators and for dosimetry in the planning of radiotherapy, the licence holder must have one or more medical physicists as specified in paragraph 4 at his disposal.
6
The FDHA shall define the minimum scope of the acceptance test and the quality assurance programme, taking international quality assurance standards into account.
7
For nuclear medicine applications and for fluoroscopy-guided interventional radiology and computer tomography, the licence holder must periodically enlist the services of a medical physicist as specified in paragraph 4.59
Section 7
Storage, Transport, Import, Export and Transit of Radioactive Sources
Art. 75
Storage
1
Radioactive sources whose activity is above the licensing limit specified in Annex 3 Column 10 must be stored in such a way that they are only accessible to persons who are authorised to use them.
2
Within the scope of their responsibilities, the FDHA and DETEC shall specify the type of storage and the requirements for storage facilities.60
Art. 76
Off-site transport
1
Anyone who transports or arranges the transport of radioactive sources off-site must comply with the relevant federal regulations concerning the transport of hazardous goods.
2
Such persons must provide evidence of and implement an appropriate quality assurance programme.
57 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
58 Wording of the sentence according to No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
59 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
60 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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3
The consignor and the transporter of radioactive sources must designate a person responsible for quality assurance and define quality assurance measures in writing.
4
If the consignor or the transporter has in place a quality assurance system for the transport of radioactive sources, certified by an accredited body, it shall be assumed that they implement an appropriate quality assurance programme.
5
The consignor and the transporter must make sure that the transport containers or packaging materials comply with the relevant regulations and are properly maintained.
6
The consignor must make sure that the contracted transporter has a licence for the transport of radioactive sources.
Art. 77
61
Within the scope of their responsibilities, the FDHA and DETEC shall specify the requirements to be met by transport packaging materials for radioactive sources that are to be transported on-site.
Art. 78
62
Radioactive sources may only be imported, exported or undergo transit via the customs offices designated by the Directorate General of Customs.
2
The customs declaration for imports and exports must include the following details:63
a. the precise designation of the goods; b. the radionuclides;
c. the total activity per radionuclide (in becquerels); d. the licence number of the recipient or sender in Switzerland.
3
An individual licence is required for storage in a customs bonded warehouse or in a duty-free warehouse. This must be presented to the customs office.
Chapter 6
Radioactive Waste Section 1
Discharge to the Environment
Art. 79
Principle
1
Radioactive waste may only be discharged to the environment with a licence and under the supervision of the licence holder.
61 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
62 Amended by Annex 4 No 44 of the Customs Ordinance of 1 Nov. 2006, in force since 1 May 2007 (AS 2007 1469).
63 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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2
Only low-level radioactive waste may be discharged to the environment.
Art. 80
Discharge of gaseous, aerosol and liquid waste 1
Gaseous, aerosol or liquid radioactive waste may only be discharged via exhaust air to the atmosphere or via liquid effluent to surface waters.
2
The licensing authority shall specify maximum permissible discharge rates and, where appropriate, discharge concentrations for each enterprise on a case-by-case basis.
3
It shall specify the discharge rates and discharge concentrations in such a way that the source-related dose guidance value specified in Article 7 and the off-site limits specified in Article 102 are not exceeded.
Art. 81
Control measures
1
In the licence, the licensing authority shall specify the monitoring of emissions. It may provide for mandatory reporting.
2
Off-site monitoring shall be based on Article 103.
3
The licence holder may engage external bodies to carry out monitoring measurements, provided that they are recognised by the supervisory authority.
4
The licensing or supervisory authority may request that a meteorological assessment and local background radiation measurements be carried out before operations are commenced.
Art. 82
64
Solid radioactive waste with specific activities no greater than 100 times the exemption limit specified in Annex 3 Column 9 may by way of exception, with the agreement of the licensing authority, be discharged to the environment, provided it can be ensured by mixing with inactive materials that the values specified in Annex 2 are not exceeded.
2
With the agreement of the licensing authority, materials containing radium or uranium from urban areas with specific activities no greater than 1000 times the exemption limit specified in Annex 3 Column 9 may also be discharged to the environment if: a. they arose before the commencement of the RPA; b. disposal via the usual channels would be impossible or would involve disproportionate costs;
c. removal represents a significantly better option for humans and the environment overall than maintenance of the status quo; and
64 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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d. it can be ensured that, after mixing with inactive materials, the values specified in Annex 2 will not be exceeded.
Art. 83
Incineration of waste at enterprises 1
Combustible radioactive waste may be incinerated at the enterprise where it arises or, with the agreement of the licensing authority, at other enterprises if: a. the enterprise has a waste incinerator complying with the requirements of the Clean Air Ordinance of 16 December 198565 and the Technical Ordinance on Waste of 10 December 199066; and b. an appropriate monitoring programme is in place.67 2
The waste may only contain the radionuclides H-3, C-14 or S-35. In justified cases, waste containing other radionuclides may be incinerated with the agreement of the licensing authority.68 3 The activity approved for incineration per week must not exceed 1000 times the licensing limit specified in Annex 3 Column 10.
4
Radioactive residues from incineration and flue gas scrubbing must be treated as radioactive waste.
Section 2
Management of Waste within the Enterprise
Art. 84
Record-keeping
The holder of radioactive waste must monitor waste holdings and keep records of the activities and composition relevant for subsequent management.
Art. 85
Waste with short half-lives 1
Waste exclusively containing radionuclides with a half-life of 60 days or less must be stored at the sites where it arises until its activity has decreased to such a level that it no longer comes under the scope of Article 1 or is below the licensed discharge rate specified in Article 80.
2
In the absence of an alternative that is more favourable overall for humans and the environment, waste which, as a result of radioactive decay, will fall outside the scope of Article 1 no later than 30 years after arising is to be separated from radioactive waste. In the event of separation, it shall be: a. packaged and retained in such a way as to prevent the uncontrolled release of radioactive substances and avoid creating a fire hazard; 65 SR
814.318.142.1 66 SR
814.600
67 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
68 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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b. labelled and provided with documentation indicating the type of waste and the activity content.69 3
The activity must be verified in an appropriate manner immediately prior to disposal of the waste.70 4
The licence holder must ensure that labels, hazard warning symbols or other markings drawing attention to radioactivity are removed after the activity has decayed and before the material is disposed of as inactive waste.71
Art. 86
Gases, dust, aerosols and liquids Where appropriate and possible at reasonable expense: a. radioactive waste in the form of gases, dust or aerosols is to be retained by means of suitable devices such as filters or scrubbing towers; b. liquid radioactive waste is to be converted to solid form.
Section 3
Surrender
Art. 87
72
Radioactive waste not arising as a result of the use of nuclear energy must be surrendered, following any treatment that may be required, to the federal collection centre.
2
The federal collection centre is the PSI.
3
The following is exempted from mandatory surrender to the PSI: a. radioactive waste that may be discharged to the environment; b. radioactive waste with short half-lives as specified in Article 85.
4
The FDHA shall define the technical details for the treatment of radioactive waste subject to mandatory surrender prior to its receipt by the federal collection centre.
a 73 Duties of the PSI
The PSI shall take receipt of radioactive waste subject to mandatory surrender and be responsible for stacking, treatment and interim storage.
69 Inserted by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
70 Originally Para. 2.
71 Originally Para. 3.
72 Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
73
Inserted by No I of the Ordinance of 3 June 1996 (AS 1996 2129). Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
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b74 Coordination Commission A Coordination Commission comprising representatives from the FOPH, the ENSI and the PSI shall make recommendations on further action to the supervisory and licensing authorities if new or additional licences or permits are required.
Section 4
…
Art. 88-9275 Section 5
…
Art. 93
76
Abnormal Occurrences Section 1
Prevention of Abnormal Occurrences
Art. 94
Prevention
1
The licence holder must adopt appropriate measures to prevent abnormal occurrences.
2
The enterprise must be designed in such a way that the source-related dose guidance value specified in Article 7 can also be complied with in the event of abnormal occurrences with a frequency of more than 10-1 per year.
3
For abnormal occurrences with an expected frequency of between 10-1 and 10-2 per year, the enterprise must be designed in such a way that the additional dose resulting from a single abnormal occurrence is no greater than the yearly source-related dose guidance value specified for the enterprise.
4
For abnormal occurrences with an expected frequency of between 10-2 and 10-4 per year, the enterprise must be designed in such a way that the dose resulting from a single abnormal occurrence for non-occupationally exposed persons is no greater than 1 mSv.77 74
Inserted by No I of the Ordinance of 3 June 1996 (AS 1996 2129). Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
75
Repealed by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, with effect from 1 Feb. 2005 (AS 2005 601).
76
Repealed by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, with effect from 1 Feb. 2005 (AS 2005 601).
77 Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
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5
For abnormal occurrences with an expected frequency of between 10-4 and 10-6 per year, the enterprise must be designed in such a way that the dose resulting from a single abnormal occurrence for non-occupationally exposed persons is no greater than 100 mSv. The licensing authority may specify a lower dose in particular cases.78 6 The enterprise must be designed in such a way that only a small number of abnormal occurrences of the type referred to in paragraphs 4 and 5 can occur.79 7
For abnormal occurrences of the type referred to in paragraphs 4 and 5, and for abnormal occurrences which have an expected frequency of less than 10-6 per year but which could have major impacts, the supervisory authority shall order the necessary preventive measures.80 8 The supervisory authority shall specify on a case-by-case basis the methodology and conditions for analysis of abnormal occurrences and for the assignment of abnormal occurrences to the frequency classes specified in paragraphs 3-5. The effective dose or the organ doses arising from abnormal occurrence-related exposure of persons are to be determined in accordance with the current state of science and technology, using the assessment quantities and dose coefficients specified in Annexes 3, 4 and 7.81
Art. 95
Safety report
1
The supervisory authority may require the licence holder to submit a safety report.
2
The safety report shall include descriptions of: a. the safety systems and equipment; b. the measures adopted to ensure safety; c. the operational organisation playing a decisive role in safety and radiological protection;
d. abnormal occurrences, their effects on the site and the vicinity, and their approximate frequency;
e. in the case of enterprises covered by Article 101 paragraph 1, emergency planning for protection of the public.
3
The supervisory authority may request additional documentation.
78 Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
79 Inserted by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
80 Inserted by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (SR 732.11).
81 Originally Para. 6. Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2005 601).
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Art. 96
Preventive measures
1
The licence holder must make the necessary in-house preparations so that abnormal occurrences can be managed.
2
The licence holder shall issue instructions concerning the emergency measures to be adopted.
3
The licence holder must ensure that appropriate resources are available at all times for the management of abnormal occurrences; in rooms where radioactive substances are handled, this also applies to firefighting.
4
The licence holder must ensure that staff receive regular instruction in rules of conduct, are trained in emergency measures and are familiarised with the location and use of the relevant resources.
5
The licence holder must take appropriate measures to ensure that, in the first year after the event, the staff deployed to deal with abnormal occurrences do not receive an effective dose of more than 50 mSv, or more than 250 mSv in the case of efforts to protect the public and in particular to save human lives.82 5bis For enterprises where abnormal occurrences as specified in Article 94 paragraph 5 may occur, the supervisory authority may order:
a. the recording of plant parameters that are required to monitor the course of an accident, to produce diagnoses and forecasts, and to determine the measures necessary to protect the public; b. the continuous transmission of these plant parameters to the supervisory authorities via a network capable of withstanding an abnormal occurrence.83
6
The supervisory authority may require that exercises be conducted to test reporting channels, the functionality of resources and the training of staff. It may organise exercises itself.
7
The licence holder must inform the competent cantonal authorities and emergency services of the radiation sources present on the site.
Section 2
Management of Abnormal Occurrences
Art. 97
Emergency measures
1
The licence holder must make every effort to manage abnormal occurrences.
2
In particular, the licence holder must, without delay: a. control the extent of the abnormal occurrence, in particular by taking measures at source;
82 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
83 Inserted by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
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b. ensure that all persons not involved in management of the abnormal occurrence do not enter the danger zone or leave it immediately;
c. take measures to protect the staff deployed, such as dose monitoring and appropriate instruction;
d. ensure that all those involved are registered, monitored for contamination and intake, and if necessary decontaminated.
3
The licence holder must, as soon as possible: a. remove any contamination that has arisen; b. take the measures required to analyse the abnormal occurrence.
Art. 98
Mandatory reporting
1
The licence holder must report every abnormal occurrence to the supervisory authority.
2
The licence holder must also report radiological incidents to the National Emergency Operations Centre (NEOC) without delay.
3
In the event of a radiation accident, the licence holder must notify the supervisory authority without delay. If the victim is an employee, the licence holder must additionally report the radiation accident to Suva without delay.
Art. 99
Investigation
1
After an abnormal occurrence, the licence holder must, without delay, request an expert to carry out an investigation.
2
The results of the investigation are to be recorded in a report. The report must contain:
a. a description of the abnormal occurrence, the cause, the effects determined and other possible effects, and the measures taken; b. an account of measures that are planned or have already been taken to prevent further similar abnormal occurrences.
3
The licence holder shall submit the report to the supervisory authority no later than six weeks after the abnormal occurrence.
Art. 100
84
84 Amended by Annex 2 No II 3 of the NBCN Response Ordinance of 20 Oct. 2010, in force since 1 Jan. 2011 (AS 2010 5395).
85 SR
520.17
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Section 3
Emergency Protection Measures in the vicinity of Enterprises
Art. 101
1 For enterprises where the dose limit specified in Article 37 may be exceeded as a result of an abnormal occurrence, the licensing authority shall specify on a case-bycase basis to what extent they are required to participate in the preparation and implementation of emergency protection measures in the vicinity of the site, or to adopt such measures themselves.
2
The licensing authority shall involve the competent cantonal authorities and emergency services in the preparation of emergency protection measures and inform them of the measures adopted.
3
For warnings and alerts and for the preparation and implementation of measures to protect against increased radioactivity in the vicinity of nuclear facilities, the Emergency Protection Ordinance of 20 October 201086 and the Alarm Ordinance of 18 August87 are applicable.88 Chapter 8
Monitoring of the Environment and Foodstuffs Section 1
Monitoring of the Environment
Art. 102
Off-site limits
1
The yearly average concentration of airborne radioactive substances off-site shall not exceed a three-hundredth of the guidance value specified in Annex 3 Column 11.
2
The weekly average concentration of radioactive substances in publicly accessible waters shall not exceed a fiftieth of the exemption limit for specific activity specified in Annex 3 Column 9.
3
Direct radiation off-site must not lead to ambient doses exceeding 1 mSv per year in premises where people live, spend time or work, or 5 mSv per year in other areas.
Art. 103
Off-site monitoring by the enterprise 1
The licensing authority may require the licence holder to monitor levels of radioactive substances in the environment and direct radiation from the site and to report the results to the supervisory authority.
2
The licence holder may engage external bodies to carry out measurements for monitoring purposes, provided that they are recognised by the supervisory authority.
86 SR
732.33
87 SR
520.12
88 Amended by Art. 20 No 4 of the Emergency Response Ordinance of 20 Oct. 2010, in force since 1 Jan. 2011 (AS 2010 5191).
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Art. 104
Monitoring of environmental radioactivity 1
The FOPH shall monitor ionising radiation and radioactivity in the environment.
2
The ENSI shall additionally monitor ionising radiation and radioactivity in the vicinity of nuclear facilities and the PSI.89 3 In monitoring radioactivity in foodstuffs, the FOPH shall cooperate with the Federal Food Safety and Veterinary (FSVO) and the cantons.90
Art. 105
Sampling and measurement programme 1
The FOPH shall prepare a sampling and measurement programme in cooperation with the ENSI, Suva, the NEOC and the cantons.91 2 For the implementation of the sampling and measurement programme, federal laboratories, in particular the PSI, the Swiss Federal Institute of Aquatic Science and Technology and the Spiez Laboratory, are required to cooperate and to make available at all times the necessary human and material resources. Third parties may be involved for this purpose.
Art. 106
Data collection and report 1
The ENSI, Suva, the NEOC, the cantons and the participating laboratories shall make available to the FOPH the monitoring data generated and interpreted.92 2 The FOPH shall use this input to prepare an annual report on the monitoring data and the resultant radiation doses to the public. It shall publish this report.
Art. 107
93
Monitoring of Foodstuffs
Art. 108
Limit and tolerance values for radionuclides in foodstuffs For radionuclides in foodstuffs, the limit and tolerance values specified in the Contaminants and Constituents Ordinance of 27 February 198694 are applicable.
89 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
90 Amended by No I 5 of the Ordinance of 4 Sept. 2013 (Reorganisation in the field of Food Safety and Veterinary Medicine), in force since 1 Jan. 2014 (AS 2013 3041).
91 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
92 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
93 Repealed by No I of the Ordinance of 15 Nov. 2000 (AS 2000 2894).
94
[AS 1986 647, 1987 1288, 1988 1235 1342, 1989 1197, 1990 1094, 1991 1878, 1994 2051 Art. 2. AS 1995 2893 Art. 6 Letter a]. See now the Ordinance of 26 June 1995 on Contaminants and Constituents in Foodstuffs (SR 817.021.23).
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Art. 109
95
1
If the monitoring bodies detect that a limit or tolerance value has been exceeded, they shall inform the FSVO.
2
The FSVO shall inform the FOPH and the monitoring bodies of any reports it receives under paragraph 1.
Section 3
Elevated Radon Concentrations
Art. 110
Limits and guidance value 1
For radon concentrations in premises where people live (residential) or spend time (non-residential), a yearly average limit of 1000 becquerels per cubic metre (Bq/m3) is applicable.
2
For radon concentrations in workplaces, a limit of 3000 Bq/m3 averaged over a monthly working period is applicable.
3
If an occupationally exposed person is additionally exposed to radon concentrations of more than 1000 Bq/m3 in the course of his/her work, the additionally accumulated dose due to radon must also be taken into account when calculating the permissible yearly dose in accordance with Article 35.
4
For new and converted buildings (Art. 114) and for remediation projects (Art. 113 and 116), a guidance value of 400 Bq/m3 is applicable, provided that this can be achieved by simple structural measures.
Art. 111
Measurements
1
Radon concentrations must be determined by approved measurement laboratories.
1bis
The measurement period in residential and non-residential premises must be at least a month.96 2
Measurements may be requested by the owner or by any other person concerned.
3
If measurements are not performed in accordance with paragraph 2, they shall be ordered by the cantonal authorities at the request of the person concerned. The cantonal authorities shall ensure that the results of the measurements are communicated to the person concerned.
4
Persons are deemed to be "concerned" if they have reason to suppose that the limits specified in Article 110 are exceeded as a result of the occupation of premises or workplaces. This applies in particular to persons in areas with elevated radon concentrations as specified in Article 115.
5
Building users must make rooms accessible for the performance of measurements.
95 Amended by No I 5 of the Ordinance of 4 Sept. 2013 (Reorganisation in the field of Food Safety and Veterinary Medicine), in force since 1 Jan. 2014 (AS 2013 3041).
96 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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6
The costs of measurements ordered by the cantonal authorities shall be borne by the owner.
Art. 112
97
The FOPH shall approve a radon measurement laboratory if it: a. has the specialist staff and measurement system required for due fulfilment of its responsibilities; b. can assure proper fulfilment of its responsibilities, and in particular if staff in the course of their work are not subject to any influences leading to conflicts of interest.
2
The Federal Department of Justice and Police shall specify the technical requirements for measurement systems and the methods for maintenance of measurement stability.
3
The measurement laboratories are required to enter their data in the radon database (Art. 118a).
4
The FOPH shall supervise the measurement laboratories.
Art. 113
Mitigation measures
1
If the limit specified in Article 110 is exceeded, the owner must, at the request of a person concerned, undertake the necessary remedial work within a period of three years.
2
If the deadline passes unmet or the owner refuses to comply, the cantonal authorities shall order the necessary remedial work. They shall set a time limit of up to three years for the completion of the work, depending on the urgency of the particular case.
3
The costs of the remedial work shall be borne by the owner.
4
The above provisions are without prejudice to remediation measures adopted by Suva in accordance with the Federal Accident Insurance Act of 20 March 198198.
Art. 114
Building regulations
1
The cantonal authorities shall take the necessary measures to ensure that the limit of 1000 Bq/m3 is not exceeded in new and converted buildings. They shall ensure that efforts are made, through appropriate structural measures, to prevent radon concentrations from exceeding the guidance value of 400 Bq/m3.
2
After the completion of construction work, the cantonal authorities shall carry out spot checks to assess compliance with the limit.
97 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
98
SR 832.20
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Art. 115
High radon areas
1
The cantons shall ensure that sufficient numbers of measurements are carried out on their territory.
2
They shall compile a register of areas with elevated radon concentrations and continuously revise the register on the basis of measurement data.
3
The cantons shall ensure that, in areas with elevated radon concentrations, measurements are carried out in sufficient numbers of residential and non-residential premises and workplaces in public buildings.
4
The maps of areas with elevated radon concentrations may be consulted by members of the public.
Art. 116
Remediation programmes 1
In areas with elevated radon concentrations, the cantons shall specify the remediation measures to be adopted for premises where the limit specified in Article 110 paragraph 1 is exceeded.
2
They shall determine the period within which the remediation measures are to be implemented according to the urgency of the particular case and the economic acceptability.
3
The remediation measures must have been implemented no later than 20 years after the commencement of this Ordinance.
4
The costs of the remediation measures shall be borne by the owner.
Art. 117
Information
1
The cantons shall regularly submit the updated maps of high radon areas to the FOPH.99 2
They shall regularly inform the FOPH of the status of remediation activities.
Art. 118
Radon Technical and Information Centre 1
The FOPH shall operate a Radon Technical and Information Centre.
2
It shall carry out the following tasks: a. in cooperation with the cantons, regularly making recommendations on measurements and conducting measurement programmes; b. advising cantons, property owners and other interested parties on radon problems;
c. regularly informing the public on the radon issue in Switzerland; d. advising persons concerned and interested bodies on appropriate mitigation measures;
99 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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e. regularly evaluating the effects of measures; f.
possibly carrying out studies on the origins and effects of radon; g. regularly providing the cantons with an overview of the high radon areas reported to it in accordance with Article 117.
3
The FOPH shall make the measurement data available to the cantons via an online access system.100 4
The FOPH may organise training courses.
a101 Radon database 1 The FOPH shall maintain a central radon database. In this database, it shall store the data that is required to allow continuous assessment of the implementation of measurements and remediation projects and to draw statistical and scientific conclusions.
2
The following data shall be stored in the central radon database: a. building location (coordinates, plot number); b. information on the building; c. information on the premises; d. measurement data;
e. remediation
data;
f.
building owner or user (name, address, postcode, town).
3
The staff of the Radon Technical and Information Centre are entitled to process the data in the database in accordance with the processing regulations.
4
The approved measurement laboratories, dosimeter vendors and the competent authorities are obliged to enter the data they have gathered in the central radon database. For this purpose, the data collected may be made available to the abovementioned bodies via an online access system.
5
The persons charged with measurement and remediation may consult the building data and are authorised to enter information on measurement and remediation. For this purpose, the data collected may be made available to them via an online access system.
6
The data held in the database shall be deleted after 100 years.
100 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
101 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Chapter 9
Protection of the Public in the event of increased Radioactivity Section 1 Emergency Response Organization
Art. 119
102 For events that may endanger the public as a result of increased radioactivity, the die
NBCN Response Ordinance of 20 October 2010103 applies in addition to the provisions of this Ordinance.
Section 2
Persons and Undertakings with Special Obligations
Art. 120
Categories of persons 1
In the event of danger arising as a result of increased radioactivity, the following are obliged to assume responsibilities under Article 20 paragraph 2 letter b of the RPA: a. persons and undertakings such as measurement and radiological protection teams, for direct intervention; b. persons and undertakings in the public and private transport sector, for passenger and freight transport and evacuations;
c. persons and undertakings, for indirect intervention, such as at-source measures designed to prevent further contamination of the vicinity; d. customs authorities, for border controls; e. healthcare professionals and medical staff, for the care of radiation victims or other persons affected.
2
Persons under 18 years of age and pregnant women shall be exempted from deployment under paragraph 1.
Art. 121
Protection of health
1
The persons with special obligations may only be deployed for tasks where it is not to be expected that, in the first year after the event, they will accumulate an effective dose of more than 50 mSv, or more than 250 mSv for life-saving actions.
2
If a person with special obligations has received an effective dose of more than 250 mSv, he/she is to be placed under medical surveillance. The physician responsible shall communicate the results of the investigation to the person concerned and to the FOPH, together with a proposal concerning measures to be adopted. If the person concerned is an employee, the physician shall notify Suva.
102 Amended by Annex 2 No II 3 of the NBCN Response Ordinance of 20 Oct. 2010, in force since 1 Jan. 2011 (AS 2010 5395).
103 SR
520.17
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3
The disclosure of data by the physician shall be governed by Article 39 paragraph 3.
4
The radiation exposure of persons with special obligations is to be determined at appropriate intervals by means of suitable measurements.
5
If members of the armed forces, civil protection or the emergency services are deployed under the provisions of the RPA, the protection of health shall be governed by paragraph 1.
Art. 122
Equipment
The Federal Staff (FST NBCN) responsible under Article 5 of the NBCN Response Ordinance of 20 October 2010104 for NBCN events as well as the federal and cantonal agencies under Article 4 of the NBCN Response Ordinance of 20 October 2010 shall ensure that persons with special obligations have the necessary equipment to perform their tasks and protect their health.105 2 The necessary equipment shall include in particular: a. an adequate number of measurement devices for the determination of radiation exposure;
b. means of protection against intake or contamination.
Art. 123
Instruction and training 1
The FST NBCN as well as the federal and cantonal agencies under Article 4 of the NBCN Response Ordinance of 20 October 2010106 shall ensure that, before they perform their tasks, persons with special obligations are appropriately instructed and are informed of the risks involved.107 2 Instruction must cover at least: a. behaviour in a radiation field (self-protection); b. the risks of radiation exposure; c. working and measurement methods for deployments.
3
Persons with special obligations may be required to participate in exercises.
Art. 124
Insurance cover and compensation 1
In the event of increased radioactivity, persons with special obligations are insured against accidents and illness. If the cover provided by compulsory accident insurance and existing private insurance is not sufficient, the Confederation shall guaran104 SR
520.17
105 Amended by Annex 2 No II 3 of the NBCN Response Ordinance of 20 Oct. 2010, in force since 1 Jan. 2011 (AS 2010 5395).
106 SR
520.17
107 Amended by Annex 2 No II 3 of the NBCN Response Ordinance of 20 Oct. 2010, in force since 1 Jan. 2011 (AS 2010 5395).
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tee benefits in accordance with the provisions of the Federal Act of 19 June 1992108 on Military Insurance. If necessary, the military insurance organisation may be involved for purposes of implementation.109 2 If, as a result of their activities, persons and undertakings with special obligations incur costs that are not covered, they shall receive compensation from the Confederation. The FDHA shall regulate the processing of financial claims.
Chapter 10 Licences and Supervision Section 1 Mandatory Licensing and Licensing Procedure
Art. 125
Mandatory licensing
1
Mandatory licensing is based on Article 28 of the RPA.
2
Anyone who deploys persons as occupationally exposed persons in a third-party enterprise shall also be subject to mandatory licensing.110 3 The following shall be exempt from mandatory licensing: a.111 work involving radioactive substances where the activity handled per operation or per day does not exceed the licensing limit specified in Annex 3 Column 10;
b. the handling of radiation sources approved in accordance with Article 128, with the exception of distribution; c.112 the distribution, use, storage, transport, disposal, import, export and transit of finished timepieces containing radioactive substances, provided that they comply with the ISO standards113 3157114 and 4168115, and of no more than 1000 timepiece components with radioluminescent paint; 108 SR 833.1
109 Sentence Amended by No 7 of the Ordinance of 27 April 2005, in force since 1 July 2005 (AS 2005 2885).
110 Amended by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
111 Amended by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
112 Inserted by No I of the Ordinance of 3 June 1996 (AS 1996 2129). Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
113 International
Organization for Standardization The ISO technical standards referred to in this Ordinance can be consulted free of charge at the Federal Office of Public Health, CH-3003 Bern, or purchased from the Swiss information centre for technical rules (switec), Bürglistrasse 29, CH-8400 Winterthur or
from the website of the Swiss Association for Standardization (www.snv.ch).
114 ISO 3157:1991, 2nd edition, Radioluminescence for time measurement instrumentsSpecifications.
115 ISO 4168:2002, 2nd edition, Timekeeping instruments - Conditions for carrying out checks on radioluminescent deposits.
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d.116 the transport of radioactive substances as excepted packages (UN numbers 2908, 2909, 2910 and 2911 in accordance with Annex A, Section 3.2.1, Table A, ADR117/SDR118, RID/RSD119, LTrR120, Ordinance of 10 January 1973121 on the Carriage of Dangerous Goods by Sea, ADNR122); e.123 the transport of radioactive substances by air (UN numbers 2912, 2915, 2916, 3321 and 3332 in accordance with Annex 18 to the Convention on International Civil Aviation of 7 December 1944124 and the associated Technical Instructions125).
Art. 126
Granting and term of licences 1
Licence applications are to be submitted to the competent licensing authority, together with the necessary documentation.
2
The licensing authority shall limit the term of the licence to a maximum of ten years.
3
A licence for the import or export of radioactive sources whose activity exceeds the licensing limit by a factor of more than 10 000 000 shall only be granted for a single import or export movement.
4
The licensing authority shall communicate its decision to the cantons concerned, to the supervisory authority and, in the case of companies subject to the Employment Act of 13 March 1964126, also to the competent federal employment inspectorate.
Art. 127
Licensing authorities 1
The ENSI is the licensing authority for:127 a. activities at nuclear facilities; b.128 … 116 Inserted by No I of the Ordinance of 17 Nov. 1999 (AS 2000 107). Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
117 SR
0.741.621
118 SR
741.621
119 SR
742.401.6
120 SR
748.411
121 [AS
1973 123. AS 2007 4477 No I 88] 122 SR
747.224.141.1 123 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
124 SR
0.748.0. This Annex is not published either in the Official Compilation (AS) or in the Classified Compilation of Federal Legislation (SR). It can be consulted at or obtained from the Federal Office of Civil Aviation, CH-3003 Bern.
125 The Technical Instructions are not published either in the Official Compilation (AS) or in the Classified Compilation of Federal Legislation (SR). They can be consulted in English and French at the Federal Office of Civil Aviation, CH-3003 Bern, and at the national airports' information centres; they are not translated into German or Italian.
126 SR 822.11 127 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
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c.129 … d.130 experiments involving radioactive substances in the context of geological studies as specified in Article 35 of the Nuclear Energy Act of 21 March 2003131; e.132 the import or export of radioactive substances for or from nuclear facilities; f.133 the transport of radioactive substances to and from nuclear facilities.
2
In all other cases, the FOPH is the licensing authority.
Section 2
Approval
Art. 128
Conditions
1
Radiation generators and radioactive sources may be approved by the FOPH if: a. they are constructed in such a way as to prevent inadmissible exposure or radioactive contamination of persons; b.134 it is assured that, where appropriate, they will be surrendered to the federal collection centre as radioactive waste at the end of their useful life; c. the ambient dose rate at a distance of 10 cm from the surface does not exceed 1
Sv per hour.
2
The FDHA may issue regulations concerning the approval of particular radiation generators and radioactive sources.
Art. 129
Type testing
The FOPH shall subject radiation generators and radioactive sources submitted for approval to type testing. It may engage other bodies for this purpose.
Art. 130
Effects of approval
1
Anyone who handles approved radiation generators and radioactive sources does not require a licence to do so, except in the case of distribution.
2
As part of the approval process, the FOPH shall specify: 128 Repealed by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, with effect from 1 Feb. 2005 (AS 2005 601).
129 Repealed by No II 2 of the Ordinance of 15 Nov. 1995 (AS 1995 4959).
130 Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
131 SR
732.1
132 Inserted by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
133 Inserted by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
134 Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
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a. under what conditions radioactive sources may be handled like inactive substances;
b.135 how, where appropriate, radioactive sources at the end of their useful life must be surrendered to the federal collection centre as radioactive waste; c. which radiation generators and radioactive sources must bear a warning label.
3
It shall limit approval to a maximum of ten years.
Art. 131
Duties of the approval holder 1
The approval holder is subject to the record-keeping and reporting duties specified in Article 134.
2
The approval holder must label the approved radiation generators and radioactive sources with an approval mark specified by the FOPH.
3
The FOPH may wholly or partly exempt certain categories of approved radiation generators and radioactive sources from labelling.
Section 3
Duties of the Licence Holder
Art. 132
Organizational duties 1
The licence holder must issue internal directives concerning working methods and protective measures and monitor compliance.
2
The licence holder shall specify in writing the powers of the various line managers and radiological protection experts, and of persons handling radiation sources.
Experts shall be granted the power to intervene wherever necessary on safety grounds.
3
The licence holder must ensure that all persons working in the enterprise are appropriately informed about the health risks that may arise from handling ionising radiation at the workplace.
4
If the licence holder deploys persons from service companies or other enterprises as occupationally exposed persons, these enterprises must be apprised of the relevant radiological protection regulations.
Art. 133
Notification duties
1
The licence holder must notify the supervisory authority of any changes before they are effected, in particular: a. changes to the output of a radiation generator, structural and design characteristics, and beam direction;
135 Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
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b.136 … c. a change of radiological protection expert.
2
Every year, the licence holder must report to the supervisory authority the precise location of each radiation source whose activity is greater than 100 000 times the licensing limit specified in Annex 3 Column 10 or for which the unshielded dose rate at a distance of 1 m exceeds 1 mSv/h.137 3 The loss of a radioactive source whose activity exceeds the licensing limit specified in Annex 3 Column 10 is to be reported to the supervisory authority without delay.
Art. 134
Record-keeping and reporting duties 1
Anyone who handles radioactive sources whose activity exceeds the licensing limit specified in Annex 3 Column 10 must maintain an inventory thereof.
2
Anyone who handles unsealed radioactive sources whose activity exceeds the licensing limit specified in Annex 3 Column 10 must keep records thereof.
3
Anyone who distributes radiation sources must report the following information to the supervisory authority on request:138 a. the designation of the radionuclides and their chemical and physical form; b. the designation of the equipment or articles that contain radioactive substances, with details of the radionuclides and their activity;
c. the designation of the radiation generators and the associated parameters; d. the addresses of domestic suppliers; e. the addresses of domestic clients and the activity of the individual radionuclides purchased.
4
For all other forms of handling, record-keeping and reporting requirements may be specified in the licence on a case-by-case basis.139
Art. 135
Distributor's duty of care Within Switzerland, the distributor may only transfer radiation generators or radioactive sources whose activity exceeds the licensing limit specified in Annex 3 Column 10 to enterprises or persons with an appropriate licence.
136 Repealed by No I of the Ordinance of 24 Oct. 2007, with effect from 1 Jan. 2008 (AS 2007 5651).
137 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
138 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
139 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Section 4
Supervision
Art. 136
Supervisory authorities 1
The FOPH, Suva and the ENSI are responsible for supervision of the protection of people and the environment.140 2 The FOPH shall supervise those enterprises where there is a need, above all, for protection of the public, in particular medical enterprises and research and teaching departments at higher education institutions.
3
Suva shall supervise those enterprises where there is a need, above all, for protection of employees, in particular industrial and commercial enterprises.
4
The ENSI shall supervise:141 a. nuclear
facilities;
b.142 geological studies as specified in Article 35 of the Nuclear Energy Act of 21 March 2003143;
c.144 … d.145 … e.146 the receipt or shipment of radioactive substances at or from nuclear facilities.
5
The supervisory authorities shall consult each other to resolve any uncertainties regarding responsibility.
6
The supervisory authorities shall assume that licence holders are in compliance with the organisational duties specified in Article 132 if they have in place a quality assurance system certified by an accredited body.
Art. 137
147
The supervisory authority shall carry out spot checks to monitor radiological protection at enterprises with medical radiation generators or medical equipment containing sealed radioactive sources.
140 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
141 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
142 Amended by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
143 SR
732.1
144 Repealed by No I of the Ordinance of 17 Nov. 1999 (AS 2000 107).
145 Repealed by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, with effect from 1 Feb. 2005 (AS 2005 601).
146 Inserted by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
147 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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2
Third parties carrying out servicing of diagnostic equipment in medical, dental and veterinary practices and the practices of chiropractors and cantonally certified dentists in accordance with Article 74 paragraph 3 may be requested by the FOPH to perform checks.
Art. 138
Monitoring of import, export and transit 1
The Directorate General of Customs, in consultation with the FOPH and the ENSI, shall issue instructions for monitoring of the import, export and transit of radioactive sources.148 2 The Swiss Federal Customs Administration shall grant the FOPH access to the database in which customs declarations with the details specified in Article 78 paragraph 2 are stored.149 In the case of storage in a customs bonded warehouse or in a duty-free warehouse, it shall cancel the individual licence and forward it to the FOPH.150 3 In the course of import and transit controls, the customs offices shall check whether a transport licence has been issued by the FOPH.151 4
The FOPH shall decide on approval of the agreement concerning the return of radioactive waste referred to in Article 25 paragraph 3 letter d of the RPA.152 Chapter 11 Criminal and Final Provisions
Art. 139
Criminal provisions
1
Any person who wilfully or negligently: a. without the consent of the supervisory authority mixes radioactive substances with inactive materials solely for the purpose of circumventing this Ordinance (Art. 3 Para. 1);
b.153 performs an activity that may involve an ionising radiation hazard without having the necessary training as specified in Articles 10-18; c. places radiopharmaceuticals on the market or uses them in humans without the approval of the FOPH (Art. 30 Para. 1); 148 Amended by Annex No 22 of the Ordinance of 12 Nov. 2008 on the Swiss Federal Nuclear Safety Inspectorate, in force since 1 Jan. 2009 (AS 2008 5747).
149 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
150 Amended by Annex 4 No 44 of the Customs Ordinance of 1 Nov. 2006, in force since 1 May 2007 (AS 2007 1469).
151 Amended by Annex 4 No 44 of the Customs Ordinance of 1 Nov. 2006, in force since 1 May 2007 (AS 2007 1469).
152 Inserted by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004, in force since 1 Feb. 2005 (AS 2005 601).
153 Amended by No I of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
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d. fails to notify the supervisory authority immediately when it is suspected or established that a dose limit has been exceeded (Art. 38); e. operates a personal dosimetry laboratory without official approval (Art. 45); f.
operates a personal dosimetry laboratory and contravenes the duties imposed thereon by Articles 49-51; g.154 fails to include in a customs declaration the details specified in Article 78 paragraph 2;
h. causes an abnormal occurrence in performing an activity.
shall be liable to the penalties under Article 44 paragraph 1 letter f of the RPA.
2
Any person who wilfully or negligently:155 a. fails to assume responsibilities imposed on him/her in accordance with Article 20 paragraph 2 letter b of the RPA (Art. 120);
b. fails, without excuse, to take part in exercises where participation is required in accordance with Article 123 paragraph 3 shall be liable to a fine of up to 20 000 Swiss francs.
Art. 140
Repeal and amendment of current legislation 1
The following shall be repealed: 1. the Ordinance of 30 June 1976156 on Radiological Protection; 2. the Dosimetry Ordinance of 11 November 1981157; 3. the Ordinance of 30 August 1978158 on Basic and Advanced Training in Radiological Protection.
2
…159
Art. 141
Transitional provisions 1
Physicians, dentists and veterinary surgeons who have not undergone the training specified in Article 18 paragraph 2 shall be considered to be experts: a. until no later than 30 September 2004 if, when this Ordinance commences, they have a licence for applications specified in Articles 11 to 14; 154 Amended by Annex 4 No 44 of the Customs Ordinance of 1 Nov. 2006, in force since 1 May 2007 (AS 2007 1469).
155 Amended by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
156 [AS 1976 1573, 1979 256, 1981 537, 1983 1964, 1984 876, 1987 652 Art. 21 No 4, 1988 1561, 1991 1459 Art. 22 No 2] 157 [AS 1981 1872] 158 [AS 1978 1404] 159 The amendment can be consulted under AS 1994 1947.
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b. until no later than 30 September 1997 if they obtain a licence for applications specified in Articles 11 to 14 after the commencement of this Ordinance.
2
Physicians and veterinary surgeons who, when this Ordinance commences, carry out applications specified in Article 11 paragraph 2 and Articles 12-14 and do not have the qualifications required by these provisions must furnish evidence of the necessary qualifications by 30 September 2004.
3
Registrations of radiopharmaceuticals granted under existing legislation shall remain valid until 30 September 1999.
4
The dose limits specified in Article 35 paragraphs 1 and 2 shall only be valid from 1 January 1995.
5
The shielding and location of approved radiation generators or radioactive sources must comply with Articles 59 and 60 from 1 October 2004 at the latest.
6
Fluoroscopy may be performed using approved radiation generators without an image intensifier and automatic dose rate control until 30 September 1996 at the latest.
7
Screening may be carried out with approved radiation generators using photofluorography without an image intensifier until 30 September 1999 at the latest. For chest screening using image intensifier and storage screen systems, Article 27 paragraph 1 is applicable.160 8
Subject to the provisions of paragraphs 6 and 7, unlimited licences, approvals in accordance with Article 45 or approvals in accordance with Article 128 granted under existing legislation shall remain valid until 30 September 2004.
9
Proceedings that are pending when this Ordinance commences shall be subject to the new legislation.
10
If there is no danger to humans or the environment and in the absence of legitimate opposing interests of parties concerned, the supervisory authority may until 30 September 1997 use existing legislation to assess in individual cases:
a. the minimum requirements for the measurement system of a personal dosimetry laboratory, the measurement accuracy and the threshold for rapid notifications (Art. 52);
b. the location of medical radiation generators and radioactive sources (Art. 61);
c. the type of storage for radioactive sources and the requirements for storage facilities (Art. 75); d. the on-site transport of radioactive sources (Art. 77).
160 Amended by No I of the Ordinance of 3 June 1996, in force since 1 Aug. 1996 (AS 1996 2129).
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53
814.501
a161 Transitional provisions concerning the Amendment of 24 October 2007
1
The preparation or synthesis of finished radiopharmaceutical products must comply with Article 31a from 1 January 2012 at the latest.
2
The medical physicist referred to in Article 74 paragraph 7 must be consulted from 1 January 2012 at the latest.
Art. 142
Commencement
This Ordinance comes into force on 1 October 1994.
161 Inserted by No I of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
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Annex 1162
(Art. 4)
Definitions
Abnormal occurrence An event during which a facility deviates from normal operation and: a. the safety of the facility or an article is compromised (technical failure); b. which may lead to an off-site limit or the dose limit for non-occupationally exposed persons (radiological incident) being exceeded; or c. during which someone is exposed to a dose of more than 50 mSv (radiation accident).
Acceptance test Inspection of a product that has been offered for delivery or delivered in order to
establish whether the technical specifications and safety requirements for its intended use are met.
Activity Number of disintegrations per unit time. The unit of activity is the becquerel (Bq);
1 Bq = 1 s-l.
Activity concentration Activity per unit volume. The activity concentration is expressed in becquerels per
cubic metre (Bq/m3).
Activity, specific Activity per unit mass. Specific activity is expressed in becquerels per kilogram
(Bq/kg).
Area, controlled Controlled areas are: a. working areas for the handling of unsealed radioactive sources, as specified in Art. 69;
b. areas in which air concentrations may exceed 1/20 of the guidance values specified in Annex 3 Column 11; c. areas in which surface contamination may exceed the guidance values specified in Annex 3 Column 12;
162 Amended by No II of the Ordinance of 17 Nov. 1999 (AS 2000 107). Corrected by Annex 7 No 3 of the Nuclear Energy Ordinance of 10 Dec. 2004 (AS 2005 601), Annex 4 No 44 of the Customs Ordinance of 1 Nov. 2006 (AS 2007 1469), No III Para. 1 of the Ordinance of 24 Oct. 2007 (AS 2007 5651) and Annex 6 No 3 of the Ordinance of 20 Sept.
2013 on Clinical Trials, in force since 1 Jan. 2014 (AS 2013 3407).
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55
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d. areas in which people may accumulate an effective dose of more than 1 mSv per year as a result of external exposure; e. areas in which equipment is operated without a full protection system; f.
areas designated as such by the supervisory authority.
Articles of daily use Articles such as linen and clothing, furniture, fittings, etc., but excluding building
materials.
Becquerel (Bq) Unit of activity of a radionuclide. 1 Bq = 1 disintegration per second. The becquerel
supersedes the curie (1 Ci = 3.7 1010 Bq).
Condition inspection Inspection of the condition of a product in use to assess compliance with specified
requirements.
Constancy tests Testing of specific parameters for deviations from reference values, carried out at
regular intervals.
Contamination, radioactive
Presence of radioactive substances in a material, where this is unintended or undesirable.
Discharge Controlled release of radioactive substances to the environment, mainly in the form
of gases and aerosols via the exhaust air pathway, or in the form of liquids via the liquid effluent pathway. The emplacement of radioactive wastes in a repository is not considered to be a discharge to the environment within the meaning of Article 79.
Dose Quantity used to assess the health risks of ionising radiation. Unless indicated to the
contrary, the term is used in this Ordinance to mean "effective dose".
Dose, absorbed The amount of energy deposited per unit mass of material as a result of interaction
with ionising radiation. The unit of absorbed dose is given the special name gray (Gy); 1 Gy = 1 J/kg.
Dose, ambient The ambient dose is taken to be
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a. the quantity H*(10) (ambient dose equivalent) for strongly penetrating radiation;
b. the quantity H′(0.07) (directional dose equivalent) for weakly penetrating radiation.
Dose, ambient equivalent, H*(10) The ambient dose equivalent H*(10) at the point of interest in the real radiation field
is the dose equivalent that would be produced by the corresponding expanded and aligned field in the ICRU sphere at a depth of 10 mm on the radius opposing the direction of the aligned field.
Dose, committed effective (E50) The effective dose that accumulates in the body over a period of 50 years as a result
of the intake of a nuclide.
Dose, directional equivalent H′(0.07) The directional dose equivalent H′(0.07) at the point of interest in the real radiation
field is the dose equivalent that would be produced by the corresponding expanded field in the ICRU sphere at a depth of 0.07 mm on a radius in a specified direction.
Dose, effective (E) The sum of the equivalent doses in all organs and tissues weighted with the factor
wT.
E =
T wT HT = T wT R wR DT,R DT,R = absorbed dose in tissue T due to radiation R wR = radiation weighting factor wT = tissue weighting factor (contribution of tissue/organ T to the overall risk) HT = equivalent dose for tissue/organ T The special name for the unit of effective dose is the sievert (Sv); 1 Sv = 1 J/kg.
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Radiation weighting factors Radiation type and energy range Radiation
weighting
factor, wR
Photons, all energies Electrons and muons, all energies Neutrons, energy
- <
10
keV
- 10 keV to 100 keV - 100 keV to 2 MeV
- 2 MeV to 20 MeV
- > 20 MeV
1
1
5
10
20
10
5
Protons, other than recoil protons, energy - > 2 MeV 5
Alpha particles, fission fragments, heavy nuclei 20
Tissue weighting factors Tissue or organ
Tissue weighting
factors, wT
Gonads 0.20
Bone marrow (red)
0.12
Colon 0.12
Lung 0.12
Stomach 0.12
Bladder 0.05
Breast 0.05
Liver 0.05
Oesophagus 0.05
Thyroid 0.05
Skin 0.01
Bone surface
0.01
Remainder 0.05
Dose, equivalent (H) The product of the absorbed dose DT,R due to radiation R in tissue T and the radiation weighting factor wR (cf. Dose, effective). The special name for the unit of equivalent dose is the sievert (Sv); 1 Sv = 1 J/kg. HT,R = wR · DT,R; for a mixture of radia-
tion types: HT = R wR · DT,R Dose, personal deep, Hp(10) [short form: Hp] Equivalent dose in soft tissue at a depth of 10 mm in the thoracic region.
Dose, personal surface, Hp(0.07) [short form: Hs] Equivalent dose in soft tissue at a depth of 0.07 mm in the thoracic region.
Dosimeter Instrument used to measure ambient or personal doses.
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Full protection system Shielding of an ionising radiation generator and of sealed source equipment which
ensures that, during operation, useful, stray and incidental radiation is completely contained and shielded to such an extent that the ambient dose rate at a distance of 10 cm from the outer surface is reduced to less than 1 microsievert per hour and that, in all accessible areas, the dose limits applicable for non-occupationally exposed persons cannot be exceeded.
Gray (Gy) The special name for the unit of absorbed dose. 1 Gy = 1 J/kg.
Guidance value General term for a value which is derived from a limit; exceeding this value triggers
certain measures, while compliance with it also ensures compliance with the associated limit.
The guidance value for concentrations of radon gas is regarded as a value to be aimed for. Exceeding this value has no legal implications.
Half-life The time taken for the activity of a radionuclide to lose half its value by decay.
High-dose diagnostic procedures Examinations of the axial skeleton, pelvis and abdomen, and direct or indirect
cross-sectional imaging studies. Such procedures also include fluoroscopy, fluoroscopic contrast studies and fluoroscopy-guided interventions. Fluoroscopic examinations of the peripheral extremities, including the elbow and ankle, are not considered to be high-dose diagnostic procedures.
ICRU sphere A sphere defined as having a diameter of 30 cm, a density of 1 g/cm3 and a mass
composition of 76.2% oxygen, 11.1% carbon, 10.1% hydrogen and 2.6% nitrogen (simulating soft tissue).
Import/export Import or export is deemed to be such whether it is definitive or temporary. The
term "import" also applies to storage in a customs bonded warehouse, a bulk goods warehouse or a duty-free warehouse.
Ingestion Intake of radioactive substances via the gastrointestinal tract.
Inhalation Intake of radioactive substances through breathing.
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814.501
Intake
Act or process of taking radioactive substances into the body by ingestion or inhalation, or through the skin or wounds.
Ionizing radiation
Radiation that has sufficient energy to eject electrons from an atomic shell (ionisation).
Ionizing radiation generators Equipment and devices used to generate photon or particle radiation with an energy
greater than 5 kiloelectronvolts.
Irradiator A device used for irradiation purposes, containing a sealed radioactive source. The
radiation source is enclosed within shielding, to which it remains mechanically connected irrespective of the operating state.
Management of radioactive waste
Activities whereby radioactive waste is prepared for surrender to the federal collection centre.
Non-occupationally exposed persons People who could be exposed to higher-than-background levels of controllable
radiation as a result of circumstances not related to work or training.
Occupationally exposed persons People who: a. could accumulate an effective dose of more than 1 mSv per year in the course of their work or training through controllable radiation exposure; or b. regularly work or undergo training in controlled areas.
Preparation of a radiopharmaceutical Process in which the final radiopharmaceutical product is produced by following the
radiolabelling instructions specified by the licence of a radiolabelling kit for diagnostic purposes.
Quality assurance Planning, monitoring, testing and adjusting the execution of a product or activity
with the goal of fulfilling specified quality requirements.
Radioactivity Spontaneous disintegration of nuclides, accompanied by the emission of ionising
radiation.
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Radiation sources Equipment and articles containing radioactive substances (sealed and unsealed
radioactive sources) and installations capable of emitting ionising radiation.
Radionuclide Nuclide that disintegrates spontaneously, emitting radiation.
Radionuclide generator
Radioactive source with a fixed parent radionuclide producing a daughter radionuclide which can be removed by elution or by any other method.
Radiopharmaceuticals Drugs containing radionuclides whose radiation is used for diagnostic or therapeutic
purposes.
For the purposes of this Ordinance, the following are considered to be radiopharmaceuticals: a. medicinal products containing one or more radionuclides in a form which can be directly used; b. non-radioactive components (kits) used to produce radiopharmaceuticals by reconstitution of or combination with radionuclides immediately prior to use in humans; c. radionuclide generators with a fixed parent radionuclide producing a daughter radionuclide which is removed by elution or by any other method and used in a radiopharmaceutical;
d. radionuclides used directly or as precursors for the radiolabelling of other substances (carrier compounds, cells, plasma proteins) prior to their administration.
Radiopharmaceuticals with increased hazard potential Radiolabelling kit for therapeutic purposes, positron emission tomography (PET)
radiopharmaceuticals and radiopharmaceuticals produced in-house (with or without kits).
Screening measurement Procedure for detecting possible intakes without determining the effective dose. If a
predefined threshold is exceeded, personal dosimetry must be performed to assess the committed effective dose.
Screening, radiological Radiological examination carried out systematically on a large number of people in
the absence of a specific indication. Routine occupational health examinations are not regarded as screening.
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814.501
Servicing Ensuring the functionality and safety of equipment by means of preventive
measures.
Sievert (Sv) The special name for the unit of equivalent dose or effective dose. 1 Sv = 1 J/kg.
Sources, radioactive Sealed and unsealed sources.
Sources, sealed radioactive Radiation sources which contain radioactive substances and whose structure is such
as to prevent, under normal conditions of use, any release of the radioactive substances and thus preclude any risk of contamination. The source encapsulation must satisfy the requirements of the ISO standards for the intended use and be classified as such.
Sources, unsealed radioactive Radiation sources containing radioactive substances that are capable of spreading
and causing contamination.
Standard Measuring instrument or embodiment of a measurement, used as a reference for
testing other measuring instruments.
Stray radiation
Ionising radiation emitted from a device not primarily intended as an ionising radiation generator, or from components thereof, as a by-product of normal operation or as a result of faults.
Substances, radioactive Substances containing radionuclides whose activity exceeds the exemption limits
specified in Annex 3, Column 9.
Summation rule Rule used to assess compliance with activity limits for mixtures of nuclides. Here,
the various nuclides are weighted according to the hazard they pose. If the following inequalities are satisfied, then the mixtures are respectively below the exemption limit or below the guidance value for surface contamination.
1
LE
a
LE
a
LE
a
n
n
2
2
1
1
a1,a2,…an: specific activities of nuclides 1, 2, … n in Bq/kg LE1,LE2,…LEn: exemption limits for nuclides 1, 2, … n in Bq/kg as specified in Annex 3 Column 9
Radiological Protection 62
814.501
1
CS
c
CS
c
CS
c
n
n
2
2
1
1
c1,c2,…cn: contamination values for nuclides 1, 2, … n in Bq/cm2 CS1,CS2,…CSn: guidance values for surface contamination for nuclides 1, 2, … n in Bq/cm2 as specified in Annex 3, Column 12 Synthesis of a finished radiopharmaceutical product
All the steps involved in the synthesis of a ready-to-use radiopharmaceutical (finished radiopharmaceutical product), in particular the incorporation of the radioisotope into a molecule (e.g. formation of a covalent bond, complexation or attainment of the required radionuclide oxidation state by reduction/oxidation).
Traceability The property of the result of a measurement or the value of a standard whereby it
can be related to the stated references, usually national or international standards, through an unbroken chain of comparisons all having stated uncertainties.
Verification
Official testing and certification that a particular radiation measuring device (measuring instrument) complies with the legal requirements.
Waste, radioactive Radioactive substances or radioactively contaminated materials which will not be
reused.
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814.501
Annex 2163
(Article 1 paragraph 1 and Article 2 paragraph 1) Scope
1. Substances and articles The Ordinance is applicable when, for a substance or article, all the values in at least
one row are exceeded.
For ores, minerals, and rock collections, only the row specifically concerned with this category is relevant.
Substances, articles Specific activity
Absolute activity,
mass
Concentration,
contamination,
dose rate
Solids Exemption
limit
specified in
Annex 3 Column 9
Exemption limit
specified in
Annex 3 Column 9
Solids
Ambient
dose
rate
at
10 cm from the surface after subtraction of
background:
0.1 µSv per hour
Solids
Guidance
value
specified in
Annex 3 Column 12
Liquids Exemption
limit
specified in
Annex 3 Column 9
Exemption limit
specified in
Annex 3 Column 9
Water
1% of the exemption limit specified in
Annex 3 Column 9
Exemption limit
specified in
Annex 3 Column 9
Gases and air (including radon)
1/300 of the guidance value specified in
Annex 3 Column 11
Foodstuffs Tolerance or
limit
values specified in the DHA Ordinanceof
26 June 1995164 on
Contaminants and
Constituents in Foodstuffs
163 Amended by No II of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
164 SR
817.021.23
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814.501
Substances, articles Specific activity Absolute activity,
mass
Concentration,
contamination,
dose rate
Articles of daily use 1% of the exemption
limit specified in
Annex 3 Column 9 for artificially produced radionuclides
Exemption limit
specified in
Annex 3 Column 9
Ores, minerals and
rock collections
1000 times the exemption limit specified in
Annex 3 Column 9
10 g natural thorium or 100 g natural uranium 2. Wastes and wastewater The Ordinance is applicable when, for wastes or wastewater, all the values in at least
one row are exceeded.
The monthly values relate to discharges to the environment.
Wastes, wastewater
Specific activity Absolute activity
per licence
Contamination,
dose rate
Solid wastes
Exemption limit
specified in
Annex 3 Column 9
100 times the exemption limit specified in
Annex 3 Column 9 per month
Solid wastes
Ambient dose rate at 10 cm from the surface after subtraction of
background:
0.1 µSv per hour
Solid wastes
Guidance value specified in
Annex 3 Column 12
Liquid wastes
Exemption limit
specified in
Annex 3 Column 9
100 times the exemption limit specified in
Annex 3 Column 9 per month
Wastewater
1% of the exemption limit specified in
Annex 3 Column 9
(weekly average in
working area
wastewater)
100 times the exemption limit specified in
Annex 3 Column 9 per month
Gaseous wastes,
contained
Licensing limit specified in
Annex 3 Column 10
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814.501
Annex 3165
Data for Operational Radiation Protection Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
H-3 12.35
y
4.1 E-11 4.2 E-11 <0.001 <1
<0.1
2 E+05
1 E+08
2 E+05
1000
H-3, HTO
12.35 y
1.8 E-11 1.8 E-11 <0.001 <1
<0.1
6 E+05
3 E+08
5 E+05
1000
H-3, gas [7]
12.35
y
1.8 E-15
<0.001
<1
<0.1
3 E+12
5 E+09
Be-7 53.3
d
, 4.6 E-11 2.8 E-11 0.008 <1
0.1
4 E+05
1 E+08
1 E+05
1000
Be-10 1.6
E6
y
1.9 E-08 1.1 E-09 <0.001 2000
1.6
9 E+03
3 E+05
9 E+01
3
C-11 20.38
m
, 3.2 E-12 2.4 E-11 0.160 1000
1.7
4 E+05
7 E+07
7 E+04 [3]
3
C-11 monoxide
20.38 m
, 1.2 E-12 1.2 E-12
7 E+07
7 E+04 [3]
C-11 dioxide
20.38 m
, 2.2 E-12 2.2 E-12
7 E+07
7 E+04 [3]
C-14 5730
y
5.8 E-10 5.8 E-10 <0.001 200
0.3
2 E+04
9 E+06
1 E+04
30
C-14 monoxide
5730 y
8.0 E-13 8.0 E-13
6 E+09
1 E+07
C-14 dioxide
5730 y
6.5 E-12 6.5 E-12
8 E+08
1 E+06
N-13 9.965
m
, 0.160
1000
1.7
7 E+07
7 E+04 [3]
3
O-15 122.24
s
, 0.161
1000
1.7
7 E+07
7 E+04 [3]
3
F-18 109.77
m
, 9.3 E-11 4.9 E-11 0.160 2000
1.7
2 E+05
5 E+07
7 E+04 [3]
3
Na-22 2.602
y
, , 2.0 E-09 3.2 E-09 0.330 2000
1.6
3 E+03
3 E+06
4 E+03
3
Na-24 15
h
, 5.3 E-10 4.3 E-10 0.506 1000
1.9
2 E+04
9 E+06
3 E+04
3
Mg-28/Al-28 20.91
h
, 1.7 E-09 2.2 E-09 0.529 2000
3.1
5 E+03
3 E+06
6 E+03
3
165 Amended by No II of the Ordinance of 17 Nov. 1999 (AS 2000 107). Corrected in accordance with No II of the Ordinance of 15 Nov. 2000, in force since 1 Jan. 2001 (AS 2000 2894).
Radiological Protection 66
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Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Al-26 7.16
E5
y
, , 1.4 E-08 3.5 E-09 0.382 1000
1.5
3 E+03
4 E+05
4 E+02
3
Si-31 157.3
m
, 1.1 E-10 1.6 E-10 <0.001 1000
1.6
6 E+04
5 E+07
1 E+05
3
Si-32 450
y
5.5 E-08 5.6 E-10 <0.001 500
0.6
2 E+04
9 E+04
3 E+01
3
P-32
P-30 2.499
m
, , 0.371
900
1.7
3
P-32 14.29
d
2.9 E-09 2.4 E-09 <0.001 1000
1.6
4 E+03
2 E+06
2 E+03
3
P-33 25.4
d
1.3 E-09 2.4 E-10 <0.001 700
0.8
4 E+04
4 E+06
1 E+04
10
S-35 (inorg.) 87.44 d
1.1 E-09 1.9 E-10 <0.001 200
0.3
5 E+04
5 E+06
1 E+04
30
S-35 (org.) 87.44
d
1.2 E-10 7.7 E-10 <0.001 200
0.3
1 E+04
4 E+07
7 E+04
30
Cl-36 3.01
E5
y
, , 5.1 E-09 9.3 E-10 <0.001 1000
1.5
1 E+04
1 E+06
1 E+03
3
Cl-38 37.21
m
, 7.3 E-11 1.2 E-10 1.551 1000
1.8
8 E+04
7 E+07
4 E+04 [3]
3
Cl-39 55.6
m
, 7.6 E-11 8.5 E-11 0.241 1000
1.7
1 E+05
7 E+07
2 E+05
3
Ar-39
Ar-37 35.
02
d
<0.001
<1
<0.1
1 E+14
1 E+11
Ar-39 269
y
<0.001
2000
1.5
3 E+10
7 E+06 [4]
Ar-41 1.827
h
, 0.188
1000
1.7
5 E+07
5 E+04
K-38 7.636
m
, , 0.480
1000
1.8
3
K-40 1.28
E9
y
, , 3.0 E-09 6.2 E-09 0.022 1000
1.5
2 E+03
2 E+06
3 E+03
3
K-42 12.36
h
, 2.0 E-10 4.3 E-10 0.464 1000
1.7
2 E+04
3 E+07
2 E+04
3
K-43 22.6
h
, 2.6 E-10 2.5 E-10 0.152 1000
1.6
4 E+04
2 E+07
4 E+04
3
K-44 22.13
m
, 3.7 E-11 8.4 E-11 1.553 1000
1.8
1 E+05
1 E+08
3 E+05
3
K-45 20
m
, 2.8 E-11 5.4 E-11 0.302 1000
1.7
2 E+05
2 E+08
5 E+05
3
Ca-41 1.4
E5
y
1.9 E-10 2.9 E-10 <0.001 <1
<0.1
3 E+04
3 E+07
3 E+04
300
Ca-45 163
d
, 2.3 E-09 7.6 E-10 <0.001 700
0.8
1 E+04
2 E+06
5 E+03
10
Ca-47
4.53 d
, 2.1 E-09 1.6 E-09 0.156 1000
1.6
6 E+03
2 E+06
4 E+03
3
Sc-47
Sc-43 3.891
h
, , 1.8 E-10 1.9 E-10 0.174 1000
1.4
5 E+04
3 E+07
1 E+05
3
Sc-44 3.927
h
, , 3.0 E-10 3.5 E-10 0.324 1000
1.7
3 E+04
2 E+07
7 E+04
3
Sc-44m 58.6
h
, 2.0 E-09 2.4 E-09 0.045 200
0.2
4 E+03
3 E+06
4 E+03
3
Sc-44 [6]
Ordinance
67
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Sc-46 83.83
d
, 4.8 E-09 1.5 E-09 0.299 1000
1.2
7 E+03
1 E+06
1 E+03
3
Sc-47 3.351
d
, 7.3 E-10 5.4 E-10 0.017 1000
1.3
2 E+04
7 E+06
1 E+04
3
Sc-48 43.7
h
, 1.6 E-09 1.7 E-09 0.495 2000
1.7
6 E+03
3 E+06
7 E+03
3
Sc-49 57.4
m
, 6.1 E-11 8.2 E-11 0.001 1000
1.6
1 E+05
8 E+07
3 E+05
3
Ti-44 47.3
y
, 7.2 E-08 5.8 E-09 0.026 2
<0.1
2 E+03
7 E+04
3 E+02
30
Sc-44 [6]
Ti-45 3.08
h
, , 1.5 E-10 1.5 E-10 0.136 1000
1.5
7 E+04
3 E+07
2 E+05
3
V-47 32.6
m
, , 5.0 E-11 6.3 E-11 0.156 1000
1.7
2 E+05
1 E+08
4 E+05
3
V-48 16.238
d
, , 2.7 E-09 2.0 E-09 0.432 900
1.0
5 E+03
2 E+06
3 E+03
3
V-49 330
d
2.6 E-11 1.8 E-11 <0.001 <1
<0.1
6 E+05
2 E+08
9 E+04
100
Cr-48 22.96
h
, , 2.5 E-10 2.0 E-10 0.071 50
0.1
5 E+04
2 E+07
3 E+04
100
V-48 [6]
Cr-49 42.09
m
, , 5.9 E-11 6.1 E-11 0.166 1000
1.7
2 E+05
8 E+07
1 E+05
3
V-49
Cr-51 27.704
d
, 3.6 E-11 3.8 E-11 0.005 3
<0.1
3 E+05
1 E+08
2 E+05
100
Mn-51 46.2
m
, , 6.8 E-11 9.3 E-11 0.159 1000
1.7
1 E+05
7 E+07
1 E+05
3
Cr-51
Mn-52 5.591
d
, , 1.8 E-09 1.8 E-09 0.510 600
0.7
6 E+03
3 E+06
5 E+03
10
Mn-52m 21.1
m
, , 5.0 E-11 6.9 E-11 0.389 1000
1.7
1 E+05
1 E+08
2 E+05
3
Mn-52
Mn-53 3.7
E6
y
3.6 E-11 3.0 E-11 <0.001 20
<0.1
3 E+05
1 E+08
2 E+05
1000
Mn-54 312.5
d
, 1.2 E-09 7.1 E-10 0.126 10
0.1
1 E+04
4 E+06
7 E+03
100
Mn-56 2.5785
h
, 2.0 E-10 2.5 E-10 0.275 1000
1.7
4 E+04
3 E+07
4 E+04
3
Fe-52 8.275
h
, , 9.5 E-10 1.4 E-09 0.116 900
1.0
7 E+03
5 E+06
9 E+03
3
Mn-52m [6] Fe-55 2.70
y
9.2 E-10 3.3 E-10 <0.001 20
<0.1
3 E+04
5 E+06
9 E+03
300
Fe-59 44.529
d
, 3.2 E-09 1.8 E-09 0.175 1000
1.1
6 E+03
2 E+06
3 E+03
3
Fe-60 1
E5
y
3.3 E-07 1.1 E-07 <0.001 90
0.3
9 E+01
2 E+04
3 E+01
3
Co-60m
Co-55 17.54
h
, , 8.3 E-10 1.1 E-09 0.302 1000
1.4
9 E+03
6 E+06
1 E+04
3
Fe-55
Co-56 78.76
d
, , 4.9 E-09 2.5 E-09 0.485 300
0.6
4 E+03
1 E+06
2 E+03
10
Co-57 270.9
d
, 6.0 E-10 2.1 E-10 0.021 100
0.1
5 E+04
8 E+06
1 E+04
100
Co-58 70.80
d
, , 1.7 E-09 7.4 E-10 0.147 300
0.3
1 E+04
3 E+06
5 E+03
30
Co-58m 9.15
h
1.7 E-11 2.4 E-11 <0.001 10
<0.1
4 E+05
3 E+08
5 E+05
1000
Co-58 [6]
Radiological Protection 68
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Co-60 5.271
y
, 1.7 E-08 3.4 E-09 0.366 1000
1.1
1 E+031669 E+04
5 E+02
3
Co-60m 10.47
m
, 1.2 E-12 1.7 E-12 0.001 20
<0.1
6 E+06
4 E+09
7 E+06
300
Co-60 [6]
Co-61 1.65
h
, 7.5 E-11 7.4 E-11 0.017 1000
1.6
1 E+05
7 E+07
1 E+05
3
Co-62m 13.91
m
, 3.7 E-11 4.7 E-11 0.436 1000
1.8
2 E+05
1 E+08
2 E+05
3
Ni-56 6.10
d
, 9.6 E-10 8.6 E-10 0.260 60
0.1
1 E+04
5 E+06
9 E+03
30
Co-56 [6]
Ni-57 36.08
h
, , 7.6 E-10 8.7 E-10 0.278 700
0.8
1 E+04
7 E+06
1 E+04
10
Co-57
Ni-59 7.5
E4
y
2.2 E-10 6.3 E-11 <0.001 10
<0.1
2 E+05
2 E+07
4 E+04
1000
Ni-63 96
y
5.2 E-10 1.5 E-10 <0.001 <1
<0.1
7 E+04
1 E+07
2 E+04
1000
Ni-65 2.520
h
, 1.3 E-10 1.8 E-10 0.081 1000
1.6
6 E+04
4 E+07
6 E+04
3
Ni-66 / Cu-66
54.6 h
, 1.9 E-09 3.0 E-09 0.039 2000
2.2
3 E+03
3 E+06
4 E+03
3
Cu-60 23.2
m
, , 6.2 E-11 7.0 E-11 0.596 1000
1.8
1 E+05
8 E+07
1 E+05
3
Cu-61 3.408
h
, , 1.2 E-10 1.2 E-10 0.128 900
1.1
8 E+04
4 E+07
7 E+04
3
Cu-64 12.701
h
, , , 1.5 E-10 1.2 E-10 0.030 900
0.8
8 E+04
3 E+07
6 E+04
10
Cu-67 61.86
h
, 5.8 E-10 3.4 E-10 0.018 1000
1.4
3 E+04
9 E+06
1 E+04
3
Zn-62 / Cu-62
9.26 h
, , 6.6 E-10 9.4 E-10 0.319 1000
1.9
1 E+04
8 E+06
1 E+04
3
Zn-63 38.1
m
, , 6.1 E-11 7.9 E-11 0.175 1000
1.6
1 E+05
8 E+07
1 E+05
3
Zn-65 243.9
d
, , 2.8 E-09 3.9 E-09 0.086 40
0.1
3 E+03
2 E+06
3 E+03
30
Zn-69 57
m
, 4.3 E-11 3.1 E-11 <0.001 1000
1.6
3 E+05
1 E+08
2 E+05
3
Zn-69m 13.76
h
, 3.3 E-10 3.3 E-10 0.067 70
0.1
3 E+04
2 E+07
3 E+04
3
Zn-69
Zn-71m 3.92
h
, 2.4 E-10 2.4 E-10 0.240 1000
1.7
4 E+04
2 E+07
3 E+04
3
Zn-72 46.5
h
, 1.5 E-09 1.4 E-09 0.026 900
0.9
7 E+03
3 E+06
6 E+03
3
Ga-72 [6]
Ga-65 15.2
m
, , 2.9 E-11 3.7 E-11 0.183 1000
1.6
3 E+05
2 E+08
3 E+05
3
Zn-65
Ga-66 9.40
h
, , 7.1 E-10 1.2 E-09 0.877 600
1.1
8 E+03
7 E+06
1 E+04
3
Ga-67 78.26
h
, 2.8 E-10 1.9 E-10 0.025 30
0.3
5 E+04
2 E+07
3 E+04
30
Ga-68 68.0
m
, , 8.1 E-11 1.0 E-10 0.149 1000
1.5
1 E+05
6 E+07
1 E+05
3
166 AS 2000 934
Ordinance
69
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Ga-70 21.15
m
, , 2.6 E-11 3.1 E-11 0.001 1000
1.6
3 E+05
2 E+08
3 E+05
3
Ga-72 14.1
h
, 8.4 E-10 1.1 E-09 0.386 1000
1.7
9 E+03
6 E+06
1 E+04
3
Ga-73 4.91
h
, 2.0 E-10 2.6 E-10 0.052 1000
1.6
4 E+04
3 E+07
4 E+04
3
Ge-66 2.27
h
, , 1.3 E-10 1.0 E-10 0.108 400
0.5
1 E+05
4 E+07
6 E+04
10
Ga-66 [6]
Ge-67 18.7
m
, , 4.2 E-11 6.5 E-11 0.407 1000
1.7
2 E+05
1 E+08
2 E+05
3
Ga-67
Ge-68 288d
7.9 E-09 1.3 E-09 <0.001 10
<0.1
8 E+03
6 E+05
1 E+03
3
Ga-68 [6]
Ge-69 39.05
h
, , 3.7 E-10 2.4 E-10 0.132 500
0.6
4 E+04
1 E+07
2 E+04
10
Ge-71 11.8
d
1.1 E-11 1.2 E-11 <0.001 10
<0.1
8 E+05
5 E+08
8 E+05
1000
Ge-75 82.78
m
, 5.4 E-11 4.6 E-11 0.006 1000
1.6
2 E+05
9 E+07
2 E+05
3
Ge-77 11.3
h
, 4.5 E-10 3.3 E-10 0.163 1000
1.6
3 E+04
1 E+07
2 E+04
3
Ge-78 87
m
, 1.4 E-10 1.2 E-10 0.045 1000
1.5
8 E+04
4 E+07
6 E+04
3
As-78 [6]
As-69 15.2
m
, , 3.5 E-11 5.7 E-11 0.250 900
1.7
2 E+05
1 E+08
2 E+05
3
Ge-69
As-70 52.6
m
, , 1.2 E-10 1.3 E-10 0.603 1000
1.7
8 E+04
4 E+07
7 E+04
3
As-71 64.8
h
, , 5.0 E-10 4.6 E-10 0.088 700
0.7
2 E+04
1 E+07
2 E+04
10
Ge-71
As-72 26.0
h
, , 1.3 E-09 1.8 E-09 0.339 900
1.6
6 E+03
4 E+06
6 E+03
3
As-73 80.30
d
, 6.5 E-10 2.6 E-10 0.003 20
<0.1
4 E+04
8 E+06
1 E+04
300
As-74 17.76
d
, , , 1.8 E-09 1.3 E-09 0.117 900
1.1
8 E+03
3 E+06
5 E+03
3
As-76 26.32
h
, 9.2 E-10 1.6 E-09 0.132 1000
1.6
6 E+03
5 E+06
9 E+03
3
As-77 38.8
h
, 4.2 E-10 4.0 E-10 0.001 1000
1.5
3 E+04
1 E+07
2 E+04
3
As-78 90.7
m
, 1.4 E-10 2.1 E-10 0.804 1000
1.7
5 E+04
4 E+07
6 E+04
3
Se-70 41.0
m
, , 1.2 E-10 1.4 E-10 0.158 900
1.3
7 E+04
4 E+07
7 E+04
3
As-70 [6]
Se-73 7.15
h
, , 2.4 E-10 3.9 E-10 0.174 900
1.2
3 E+04
2 E+07
3 E+04
3
As-73
Se-73m 39
m
, , 2.7 E-11 4.1 E-11 0.038 300
0.4
2 E+05
2 E+08
3 E+05
10
Se-73
Se-75 119.8
d
, 1.7 E-09 2.6 E-09 0.064 80
0.1
4 E+03
3 E+06
5 E+03
30
Se-79 6.5
E4
y
, 3.1 E-09 2.9 E-09 <0.001 200
0.4
3 E+03
2 E+06
3 E+03
10
Se-81 18.5
m
, 2.4 E-11 2.7 E-11 0.002 1000
1.6
4 E+05
2 E+08
3 E+05
3
Se-81m 57.25
m
, 6.8 E-11 5.9 E-11 0.004 100
1.1
2 E+05
7 E+07
1 E+05
3
Se-81
Se-83 22.5
m
, 5.3 E-11 5.1 E-11 0.362 1000
1.7
2 E+05
9 E+07
2 E+05
3
Br-83
Radiological Protection 70
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Br-74 25.3
m
, , 6.8 E-11 8.4 E-11 1.022 1000
1.8
1 E+05
7 E+07
1 E+05
3
Br-74m 41.5
m
, , 1.1 E-10 1.4 E-10 1.347 900
1.8
7 E+04
5 E+07
8 E+04
3
Br-75 98
m
, , 8.5 E-11 7.9 E-11 0.189 900
1.3
1 E+05
6 E+07
1 E+05
3
Se-75
Br-76 16.2
h
, , 5.8 E-10 4.6 E-10 0.503 700
1.1
2 E+04
9 E+06
1 E+04
3
Br-77 56
h
, , 1.3 E-10 9.6 E-11 0.051 60
0.1
1 E+05
4 E+07
6 E+04
100
Br-80 17.4
m
, , , 1.7 E-11 3.1 E-11 0.013 1000
1.5
3 E+05
3 E+08
5 E+05
3
Br-80m 4.42
h
1.0 E-10 1.1 E-10 0.012 10
<0.1
9 E+04
5 E+07
8 E+04
3
Br-80
Br-82 35.30
h
, 8.8 E-10 5.4 E-10 0.395 1000
1.4
2 E+04
6 E+06
9 E+03
3
Br-83 2.39
h
, 6.7 E-11 4.3 E-11 0.001 1000
1.5
2 E+05
7 E+07
1 E+05
3
Br-84 31.80
m
, 6.2 E-11 8.8 E-11 0.923 1000
1.7
1 E+05
8 E+07
1 E+05
3
Kr-79 35.04
h
, , 0.042
100
0.2
3 E+08
3 E+05
Kr-81 2.1
E5
y
, 0.004
8
<0.1
7 E+09
7 E+06
Kr-83m 1.83
h
0.002
3
<0.1
1 E+12
1 E+09
Kr-85 10.72
y
, 0.001
1000
1.5
5 E+07 [8] 5 E+06 [4] Kr-85m 4.48
h
, 0.026
1000
1.4
5 E+08
5 E+05
Kr-85
Kr-87 76.3
m
, 0.501
1000
1.7
8 E+07
8 E+04
Rb-87
Kr-88 2.84
h
, 0.264
1000
1.5
2 E+07
2 E+04 [1]
Rb-88 [6]
Kr-89 3.18
m
, 2.047
900
1.8
3 E+07
3 E+04
Rb-89 [6]
Rb-79 22.9
m
, , 3.0 E-11 5.0 E-11 0.217 2000
2.1
2 E+05
2 E+08
3 E+05
3
Kr-79
Rb-81 4.58
h
, , 6.8 E-11 5.4 E-11 0.101 1000
1.2
2 E+05
7 E+07
1 E+05
3
Kr-81
Rb-81m 32
m
1.3 E-11 9.7 E-12 0.006 5
0.3
1 E+06
4 E+08
6 E+05
30
Rb-81 [6]
Rb-82m 6.2
h
, , 2.2 E-10 1.3 E-10 0.436 400
0.6
8 E+04
2 E+07
4 E+04
10
Rb-83 86.2
d
, 1.0 E-09 1.9 E-09 0.082 20
<0.1
5 E+03
5 E+06
8 E+03
100
Rb-84 32.77
d
, , , 1.5 E-09 2.8 E-09 0.141 400
0.6
4 E+03
3 E+06
6 E+03
10
Rb-86 18.66
d
, 1.3 E-09 2.8 E-09 0.014 1000
1.6
4 E+03
4 E+06
6 E+03
3
Rb-87 4.7
E10
y
7.6 E-10 1.5 E-09 <0.001 1000
1.2
7 E+03
7 E+06
1 E+04
3
Rb-88 17.8
m
, 2.8 E-11 9.0 E-11 2.314 900
1.7
1 E+05
2 E+08
3 E+05
3
Rb-89 15.2
m
, 2.5 E-11 4.7 E-11 0.659 1000
1.8
2 E+05
2 E+08
3 E+05
3
Sr-89
Ordinance
71
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Sr-80 / Rb-80
100m
, , 2.1 E-10 3.5 E-10 1.750 900
1.7
3 E+04
2 E+07
4 E+04
3
Sr-81 25.5
m
, , 6.1 E-11 7.8 E-11 0.247 1000
1.6
1 E+05
8 E+07
1 E+05
3
Rb-81 [6]
Sr-82 / Rb-82
25.0 d
, , 7.7 E-09 6.1 E-09 0.434 900
1.6
2 E+03
6 E+05
1 E+03
3
Sr-83 32.4
h
, , 4.9 E-10 5.8 E-10 0.127 400
0.5
2 E+04
1 E+07
2 E+04
10
Rb-83
Sr-85 64.84
d
, 6.4 E-10 5.6 E-10 0.086 20
0.1
2 E+04
8 E+06
1 E+04
100
Sr-85m 69.5
m
, 7.4 E-12 6.1 E-12 0.035 70
0.1
2 E+06
7 E+08
1 E+06
100
Sr-85
Sr-87m 2.805
h
, 3.5 E-11 3.3 E-11 0.053 300
0.3
3 E+05
1 E+08
2 E+05
30
Rb-87
Sr-89 50.5
d
, 5.6 E-09 2.6 E-09 <0.001 1000
1.6
4 E+03
9 E+05
1 E+03
3
Sr-90 29.12
y
7.7 E-08 2.8 E-08 <0.001 1000
1.4
4 E+02
6 E+04
1 E+02
3
Y-90 [6]
Sr-91 9.5
h
, 5.7 E-10 7.6 E-10 0.117 1000
1.6
1 E+04
9 E+06
1 E+04
3
Y-91m, Y-91 Sr-92 2.71
h
, 3.4 E-10 4.9 E-10 0.194 1000
1.4
2 E+04
1 E+07
2 E+04
3
Y-92 [6]
Y-86 14.74
h
, , 8.1 E-10 9.6 E-10 0.515 500
0.8
1 E+04
6 E+06
1 E+04
10
Y-86m 48
m
, , 4.9 E-11 5.6 E-11 0.034 200
0.1
2 E+05
1 E+08
2 E+05
30
Y-86 [6]
Y-87 80.3
h
, , 5.3 E-10 5.5 E-10 0.080 20
<0.1
2 E+04
9 E+06
2 E+04
100
Y-88 106.64
d
, , 3.3 E-09 1.3 E-09 0.380 40
0.2
8 E+03
2 E+06
3 E+03
30
Y-90 64.0
h
, 1.7 E-09 2.7 E-09 0.007 1000
1.6
4 E+03
3 E+06
5 E+03
3
Y-90m 3.19
h
1.3 E-10 1.7 E-10 0.098 200
0.2
6 E+04
4 E+07
6 E+04
30
Y-90
Y-91 58.51
d
, 6.1 E-09 2.4 E-09 0.001 1000
1.6
4 E+03
8 E+05
1 E+03
3
Y-91m 49.71
m
1.5 E-11 1.1 E-11 0.082 70
0.1
9 E+05
3 E+08
6 E+05
30
Y-91
Y-92 3.54
h
, 2.8 E-10 4.9 E-10 0.546 1000
1.7
2 E+04
2 E+07
3 E+04
3
Y-93 10.1
h
, 6.0 E-10 1.2 E-09 0.098 1000
1.6
8 E+03
8 E+06
1 E+04
3
Zr-93
Y-94 19.1
m
, 4.6 E-11 8.1 E-11 1.111 900
1.7
1 E+05
1 E+08
2 E+05
3
Y-95 10.7
m
, 2.6 E-11 4.6 E-11 1.219 1000
1.7
2 E+05
2 E+08
3 E+05
3
Zr-95 [6]
Zr-86 16.5
h
, 7.0 E-10 8.6 E-10 0.069 100
0.1
1 E+04
7 E+06
1 E+04
30
Y-86 [6]
Zr-88 83.4
d
, 4.1 E-09 3.3 E-10 0.076 50
0.1
3 E+04
1 E+06
2 E+03
100
Y-88 [6]
Zr-89 78.43
h
, , 7.5 E-10 7.9 E-10 0.182 400
0.5
1 E+04
7 E+06
1 E+04
10
Zr-93 1.53
E6
y
2.9 E-08 2.8 E-10 <0.001 <1
<0.1
4 E+04
2 E+05
3 E+02
100
Nb-93m
Zr-95 63.98
d
, 4.2 E-09 8.8 E-10 0.112 1000
1.1
1 E+04
1 E+06
2 E+03
3
Nb-95 [6]
Radiological Protection 72
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Zr-97 16.90
h
, 1.4 E-09 2.1 E-09 0.027 1000
1.6
5 E+03
4 E+06
6 E+03
3
Nb-97
Nb-88 14.3
m
, , 5.0 E-11 6.3 E-11 0.719 1000
1.8
2 E+05
1 E+08
2 E+05
3
Zr-88
Nb-89-1 [2] 66
m
, , 1.2 E-10 1.4 E-10 0.306 900
1.5
7 E+04
4 E+07
7 E+04
3
Zr-89
Nb-89-2 [2]
122 m
, , 1.9 E-10 3.0 E-10 0.392 700
1.3
3 E+04
3 E+07
4 E+04
3
Zr-89
Nb-90 14.60
h
, , 1.1 E-09 1.2 E-09 0.574 2000
1.9
8 E+03
5 E+06
8 E+03
3
Nb-91 680
y
4.1 E-09 6.4 E-11
2 E+05
1 E+06
2 E+03
Nb-91m 62
d
, 2.3 E-09 6.3 E-10
2 E+04
2 E+06
4 E+03
Nb-92m 10.15
d
, 5.9 E-10 6.0 E-10
2 E+04
8 E+06
1 E+04
Nb-93m 13.6
y
8.6 E-10 1.2 E-10 0.003 <1
<0.1
8 E+04
6 E+06
1 E+04
1000
Nb-94 2.03
E4
y
, 2.5 E-08 1.7 E-09 0.237 1000
1.5
6 E+03
2 E+05
3 E+02
3
Nb-95 35.15
d
, 1.3 E-09 5.8 E-10 0.116 100
0.3
2 E+04
4 E+06
6 E+03
30
Nb-95m 86.6
h
8.5 E-10 5.6 E-10 0.021 2000
1.4
2 E+04
6 E+06
1 E+04
3
Nb-95 [6]
Nb-96 23.35
h
, 9.7 E-10 1.1 E-09 0.372 1000
1.6
9 E+03
5 E+06
9 E+03
3
Nb-97 72.1
m
, 7.2 E-11 6.8 E-11 0.099 1000
1.6
1 E+05
7 E+07
1 E+05
3
Nb-98 51.5
m
, 9.9 E-11 1.1 E-10 0.393 1000
1.8
9 E+04
5 E+07
8 E+04
3
Mo-90 5.67
h
, , 5.6 E-10 6.2 E-10 0.147 1000
1.4
2 E+04
9 E+06
1 E+04
3
Nb-90 [6]
Mo-93 3.5
E3
y
1.4 E-09 2.6 E-09 0.016 4
<0.1
4 E+03
4 E+06
6 E+03
300
Mo-93m 6.85
h
3.0 E-10 2.8 E-10 0.330 800
0.8
4 E+04
2 E+07
3 E+04
10
Mo-93
Mo-99 66.0
h
, 1.1 E-09 1.2 E-09 0.024 1000
1.6
8 E+03
5 E+06
8 E+03
3
Tc-99m, Tc-99 Mo-101 14.62
m
, 4.5 E-11 4.2 E-11 0.196 1000
1.7
2 E+05
1 E+08
2 E+05
3
Tc-101
Tc-93 2.75
h
, 6.5 E-11 4.9 E-11 0.222 20
0.1
2 E+05
8 E+07
1 E+05
100
Mo-93
Tc-93m 43.5
m
, 3.1 E-11 2.4 E-11 0.098 300
0.4
4 E+05
2 E+08
3 E+05
10
Tc-93, Mo-93 Tc-94 293
m
, , 2.2 E-10 1.8 E-10 0.414 200
0.4
6 E+04
2 E+07
4 E+04
10
Tc-94m 52
m
, , 8.0 E-11 1.1 E-10 0.285 700
1.3
9 E+04
6 E+07
1 E+05
3
Tc-95 20.0
h
, 1.8 E-10 1.6 E-10 0.135 20
0.1
6 E+04
3 E+07
5 E+04
100
Tc-95m 61
d
, , 8.6 E-10 6.2 E-10 0.117 100
0.1
2 E+04
6 E+06
1 E+04
30
Tc-95
Tc-96 4.28
d
, 1.0 E-09 1.1 E-09 0.388 40
0.2
9 E+03
5 E+06
8 E+03
30
Tc-96m 51.5
m
, 1.1 E-11 1.3 E-11 0.016 3
<0.1
8 E+05
5 E+08
8 E+05
1000
Tc-96
Ordinance
73
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Tc-97 2.6
E6
y
1.6 E-10 8.3 E-11 0.017 4
<0.1
1 E+05
3 E+07
5 E+04
1000
Tc-97m 87
d
2.7 E-09 6.6 E-10 0.014 30
0.7
2 E+04
2 E+06
3 E+03
10
Tc-97
Tc-98 4.2
E6
y
, 6.1 E-09 2.3 E-09 0.215 2000
1.5
4 E+03
8 E+05
1 E+03
3
Tc-99 2.13
E5
y
3.2 E-09 7.8 E-10 <0.001 1000
1.1
1 E+04
2 E+06
3 E+03
3
Tc-99m 6.02
h
2.9 E-11 2.2 E-11 0.022 300
0.2
5 E+05
2 E+08
3 E+05
30
Tc-99
Tc-101 14.2
m
, 2.1 E-11 1.9 E-11 0.055 1000
1.6
5 E+05
2 E+08
4 E+05
3
Tc-104 18.2
m
, 4.8 E-11 8.1 E-11 1.219 1000
1.8
1 E+05
1 E+08
2 E+05
3
Ru-94 51.8
m
, 7.4 E-11 9.4 E-11 0.100 20
0.1
1 E+05
7 E+07
1 E+05
100
Tc-94
Ru-97 2.9
d
, 1.6 E-10 1.5 E-10 0.055 100
0.1
7 E+04
3 E+07
5 E+04
100
Tc-97
Ru-103 39.28
d
, 2.2 E-09 7.3 E-10 0.073 500
0.6
1 E+04
2 E+06
4 E+03
10
Ru-105 4.44
h
, 2.5 E-10 2.6 E-10 0.119 1000
1.6
4 E+04
2 E+07
3 E+04
3
Rh-105
Ru-106 / Rh-106 368.2 d , 3.5 E-08 7.0 E-09 0.357 1000
1.6
1 E+03
1 E+05
2 E+02
3
Rh-99 16
d
, , 8.9 E-10 5.1 E-10 0.115 100
0.2
2 E+04
6 E+06
9 E+03
30
Rh-99m 4.7
h
, , 7.3 E-11 6.6 E-11 0.122 100
0.2
2 E+05
7 E+07
1 E+05
30
Rh-100 20.8
h
, , 6.3 E-10 7.1 E-10 0.392 100
0.3
1 E+04
8 E+06
1 E+04
30
Rh-101 3.200
y
, 3.1 E-09 5.5 E-10 0.062 300
0.4
2 E+04
2 E+06
3 E+03
10
Rh-101m 4.34
d
, 2.7 E-10 2.2 E-10 0.066 200
0.2
5 E+04
2 E+07
3 E+04
30
Rh-101
Rh-102 2.900
y
, , 9.0 E-09 2.6 E-09 0.339 50
0.2
4 E+03
6 E+05
9 E+02
30
Rh-102m 207
d
, , , 4.2 E-09 1.2 E-09 0.085 400
0.6
8 E+03
1 E+06
2 E+03
10
Rh-102
Rh-103m 56.12
m
2.5 E-12 3.8 E-12 0.002 <1
<0.1
3 E+06
2 E+09
3 E+06
1000
Rh-105 35.36
h
, 4.4 E-10 3.7 E-10 0.013 1000
1.2
3 E+04
1 E+07
2 E+04
3
Rh-106m 132
m
, 1.9 E-10 1.6 E-10 0.436 1000
1.7
6 E+04
3 E+07
4 E+04
3
Rh-107 21.7
m
, 2.8 E-11 2.4 E-11 0.051 1000
1.6
4 E+05
2 E+08
3 E+05
3
Pd-107
Pd-100 3.63
d
, 9.7 E-10 9.4 E-10 0.050 20
0.1
1 E+04
5 E+06
9 E+03
100
Rh-100 [6] Pd-101 8.27
h
, , 1.0 E-10 9.4 E-11 0.081 100
0.2
1 E+05
5 E+07
8 E+04
30
Rh-101m
Pd-103 16.96
d
, 3.0 E-10 1.9 E-10 0.019 3
<0.1
5 E+04
2 E+07
3 E+04
300
Rh-103m
Pd-107 6.5
E6
y
2.9 E-10 3.7 E-11 <0.001 <1
<0.1
3 E+05
2 E+07
3 E+04
1000
Pd-109 13.427
h
5.0 E-10 5.5 E-10 0.010 1000
2.0
2 E+04
1 E+07
2 E+04
3
Radiological Protection 74
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Ag-102 12.9
m
, , 3.2 E-11 4.0 E-11 0.546 800
1.4
3 E+05
2 E+08
3 E+05
3
Ag-103 65.7
m
, , 4.5 E-11 4.3 E-11 0.125 500
0.8
2 E+05
1 E+08
2 E+05
10
Pd-103
Ag-104 69.2
m
, , 7.1 E-11 6.0 E-11 0.410 300
0.5
2 E+05
7 E+07
1 E+05
10
Ag-104m 33.5
m
, , 4.5 E-11 5.4 E-11 0.188 400
0.8
2 E+05
1 E+08
2 E+05
10
Ag-104 [6] Ag-105 41.0
d
, , 8.0 E-10 4.7 E-10 0.102 50
0.1
2 E+04
6 E+06
1 E+04
100
Ag-106 23.96
m
, , 2.7 E-11 3.2 E-11 0.117 700
1.0
3 E+05
2 E+08
3 E+05
10
Ag-106m 8.41
d
, 1.6 E-09 1.5 E-09 0.435 60
0.2
7 E+03
3 E+06
5 E+03
30
Ag-108m / Ag-108 127 y , , , 1.9 E-08 2.3 E-09 0.263 100
0.3
4 E+03
3 E+05
4 E+02
30
Ag-110m / Ag-110 249.9 d , , 7.3 E-09 2.8 E-09 0.409 500
0.6
4 E+03
7 E+05
1 E+03
10
Ag-111 7.45
d
, 1.6 E-09 1.3 E-09 0.004 1000
1.6
8 E+03
3 E+06
5 E+03
3
Ag-112 3.12
h
, 2.6 E-10 4.3 E-10 0.640 1000
1.7
2 E+04
2 E+07
3 E+04
3
Ag-115 20.0
m
, 4.4 E-11 6.0 E-11 0.181 1000
1.7
2 E+05
1 E+08
2 E+05
3
Cd-115, Cd-115m Cd-104 57.7
m
, , 6.3 E-11 5.8 E-11 0.062 20
0.1
2 E+05
8 E+07
1 E+05
100
Ag-104 [6] Cd-107 6.49
h
, , 1.1 E-10 6.2 E-11 0.030 20
0.6
2 E+05
5 E+07
8 E+04
10
Cd-109 464
d
, 9.6 E-09 2.0 E-09 0.027 5
0.4
5 E+03
5 E+05
9 E+02
10
Cd-113 9.3
E15
y
1.4 E-07 2.5 E-08 <0.001 1000
0.9
4 E+02
4 E+04
6 E+01
10
Cd-113m 13.6
y
1.3 E-07 2.3 E-08 <0.001 1000
1.4
4 E+02
4 E+04
6 E+01
3
Cd-115 53.46
h
, 1.3 E-09 1.4 E-09 0.037 1000
1.5
7 E+03
4 E+06
6 E+03
3
In-115
Cd-115m 44.6
d
, 6.4 E-09 3.3 E-09 0.003 1000
1.6
3 E+03
8 E+05
1 E+03
3
In-115
Cd-117 2.49
h
, 2.5 E-10 2.8 E-10 0.158 1000
1.5
4 E+04
2 E+07
3 E+04
3
In-117m, In-117 Cd-117m 3.36
h
, 3.2 E-10 2.8 E-10 0.282 1000
1.5
4 E+04
2 E+07
3 E+04
3
In-117, In-117m In-109 4.2
h
, , 7.3 E-11 6.6 E-11 0.117 300
0.3
2 E+05
7 E+07
1 E+05
30
Cd-109
In-110L [2]
4.9 h
, 2.5 E-10 2.4 E-10 0.468 60
0.2
4 E+04
2 E+07
3 E+04
30
In-110S [2] 69.1
m
, , 8.1 E-11 1.0 E-10 0.238 700
1.1
1 E+05
6 E+07
1 E+05
3
In-111 2.83
d
, 3.1 E-10 2.9 E-10 0.082 400
0.3
3 E+04
2 E+07
3 E+04
10
In-112 14.4
m
, , , 1.3 E-11 1.0 E-11 0.047 900
1.0
1 E+06
4 E+08
6 E+05
10
In-113m 1.658
h
3.2 E-11 2.8 E-11 0.047 500
0.6
4 E+05
2 E+08
3 E+05
10
In-114m / In-114 49.51 d , , , 1.1 E-08 4.1 E-09 0.023 3000
3.2
2 E+03
5 E+05
8 E+02
3
Ordinance
75
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
In-115 5.1
E14
y
4.5 E-07 3.2 E-08 <0.001 1000
1.3
3 E+02
1 E+04
2 E+01
3
In-115m 4.486
h
, 8.7 E-11 8.6 E-11 0.033 900
1.0
1 E+05
6 E+07
1 E+05
10
In-115
In-116m 54.15
m
, 8.0 E-11 6.4 E-11 0.356 1000
1.7
2 E+05
6 E+07
1 E+05
3
In-117 43.8
m
, 4.8 E-11 3.1 E-11 0.109 2000
1.8
3 E+05
1 E+08
2 E+05
3
In-117m 116.5
m
, 1.1 E-10 1.2 E-10 0.019 1000
1.4
8 E+04
5 E+07
8 E+04
3
In-117 [6] In-119m / In-119 18.0 m , 2.9 E-11 4.7 E-11 0.033 1000
1.7
2 E+05
2 E+08
3 E+05
3
Sn-110 4.0
h
, 2.6 E-10 3.5 E-10 0.064 70
0.1
3 E+04
2 E+07
3 E+04
100
In-110S [6] Sn-111 35.3
m
, , 2.2 E-11 2.3 E-11 0.087 400
0.6
4 E+05
2 E+08
4 E+05
10
In-111
Sn-113 115.1
d
, 1.9 E-09 7.3 E-10 0.019 4
<0.1
1 E+04
3 E+06
4 E+03
100
In-113m
Sn-117m 13.61
d
2.2 E-09 7.1 E-10 0.038 3000
2.4
1 E+04
2 E+06
4 E+03
3
Sn-119m 293.0
d
1.5 E-09 3.4 E-10 0.011 1
<0.1
3 E+04
3 E+06
6 E+03
300
Sn-121 27.06
h
2.8 E-10 2.3 E-10 <0.001 1000
1.1
4 E+04
2 E+07
3 E+04
3
Sn-121m 55
y
, 3.3 E-09 3.8 E-10 0.004 300
0.3
3 E+04
2 E+06
3 E+03
30
Sn-121
Sn-123 129.2
d
, 5.6 E-09 2.1 E-09 0.001 1000
1.6
5 E+03
9 E+05
1 E+03
3
Sn-123m 40.08
m
, 4.4 E-11 3.8 E-11 0.024 2000
1.9
3 E+05
1 E+08
2 E+05
3
Sn-125 9.64
d
, 2.8 E-09 3.1 E-09 0.053 1000
1.5
3 E+03
2 E+06
3 E+03
3
Sb-125
Sn-126 1.0
E5
y
, 1.8 E-08 4.7 E-09 0.017 1000
1.2
2 E+03
3 E+05
5 E+02
3
Sb-126 [6] Sn-127 2.10
h
, 2.0 E-10 2.0 E-10 0.313 1000
1.6
5 E+04
3 E+07
4 E+04
3
Sb-127 [6] Sn-128 59.1
m
, 1.5 E-10 1.5 E-10 0.138 1000
1.5
7 E+04
3 E+07
6 E+04
3
Sb-128S [6] Sb-115 31.8
m
, , 2.3 E-11 2.4 E-11 0.151 400
0.6
4 E+05
2 E+08
4 E+05
10
Sb-116 15.8
m
, , 2.3 E-11 2.6 E-11 0.321 500
0.9
4 E+05
2 E+08
4 E+05
10
Sb-116m 60.3
m
, , 8.5 E-11 6.7 E-11 0.487 400
0.9
1 E+05
6 E+07
1 E+05
10
Sb-117 2.80
h
, , 2.7 E-11 1.8 E-11 0.045 400
0.3
6 E+05
2 E+08
3 E+05
10
Sb-118m 5.00
h
, , 2.3 E-10 2.1 E-10 0.411 200
0.3
5 E+04
2 E+07
4 E+04
30
Sb-119 38.1
h
, 5.9 E-11 8.1 E-11 0.022 3
<0.1
1 E+05
8 E+07
1 E+05
1000
Sb-120-1 [2]
15.89 m
, , 1.2 E-11 1.4 E-11 0.079 500
0.7
7 E+05
4 E+08
7 E+05
10
Sb-120-2 [2] 5.76
d
, 1.3 E-09 1.2 E-09 0.386 400
0.4
8 E+03
4 E+06
6 E+03
10
Sb-122 2.70
d
, , 1.2 E-09 1.7 E-09 0.068 1000
1.6
6 E+03
4 E+06
7 E+03
3
Radiological Protection 76
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Sb-124 60.20
d
, 4.7 E-09 2.5 E-09 0.261 1000
1.5
4 E+03
1 E+06
2 E+03
3
Sb-124m-2 [2]
20.2 m
8.3 E-12 8.0 E-12 <0.001 <1
<0.1
1 E+06
6 E+08
1 E+06
100
Sb-124 [6] Sb-125 2.77
y
, 3.3 E-09 1.1 E-09 0.076 700
0.7
9 E+03
2 E+06
3 E+03
10
Te-125m
Sb-126 12.4
d
, 3.2 E-09 2.4 E-09 0.434 1000
1.5
4 E+03
2 E+06
3 E+03
3
Sb-126m 19.0
m
, 3.3 E-11 3.6 E-11 0.239 1000
1.5
3 E+05
2 E+08
3 E+05
3
Sb-126 [6] Sb-127 3.85
d
, 1.7 E-09 1.7 E-09 0.106 1000
1.6
6 E+03
3 E+06
5 E+03
3
Te-127, Te-127m Sb-128S [2]
10.4 m
, 2.6 E-11 3.3 E-11 0.313 1000
1.8
3 E+05
2 E+08
3 E+05
3
Sb-128L [2]
9.01 h
, 6.7 E-10 7.6 E-10 0.472 1000
1.8
1 E+04
7 E+06
1 E+04
3
Sb-129 4.32
h
, 3.5 E-10 4.2 E-10 0.212 1000
1.6
2 E+04
1 E+07
2 E+04
3
Te-129, Te-129m Sb-130 40
m
, 9.1 E-11 9.1 E-11 0.505 2000
2.1
1 E+05
5 E+07
9 E+04
3
Sb-131 23
m
, 8.3 E-11 1.0 E-10 0.278 1000
1.7
1 E+05
6 E+07
1 E+05
3
Te-131, Te-131m Te-116 2.49
h
, 1.7 E-10 1.7 E-10 0.033 8
0.2
6 E+04
3 E+07
5 E+04
10
Sb-116 [6] Te-119m 16
h
, , 6.3 E-10 8.3 E-10
1 E+04
8 E+06
1 E+04
10
Te-121 17
d
, 4.4 E-10 4.3 E-10 0.104 20
0.1
2 E+04
1 E+07
2 E+04
100
Te-121m 154
d
, 3.6 E-09 2.3 E-09 0.043 200
0.4
4 E+03
1 E+06
2 E+03
10
Te-121 [6] Te-123 1
E13
y
5.0 E-09 4.4 E-09 0.017 2
<0.1
2 E+03
1 E+06
2 E+03
300
Te-123m 119.7
d
3.4 E-09 1.4 E-09 0.032 400
0.8
7 E+03
1 E+06
2 E+03
10
Te-123
Te-125m 58
d
2.9 E-09 8.7 E-10 0.027 500
1.1
1 E+04
2 E+06
3 E+03
3
Te-127 9.35
h
, 1.8 E-10 1.7 E-10 0.001 1000
1.4
6 E+04
3 E+07
5 E+04
3
Te-127m 109
d
, 6.2 E-09 2.3 E-09 0.009 40
0.5
4 E+03
8 E+05
1 E+03
10
Te-127
Te-129 69.6
m
, 5.7 E-11 6.3 E-11 0.012 1000
1.6
2 E+05
9 E+07
1 E+05
3
I-129
Te-129m 33.6
d
, 5.4 E-09 3.0 E-09 0.011 600
1.2
3 E+03
9 E+05
2 E+03
3
Te-129
Te-131 25
m
, 6.1 E-11 8.7 E-11 0.067 2000
2.0
1 E+05
8 E+07
1 E+05
3
I-131
Te-131m 30
h
, 1.6 E-09 1.9 E-09 0.208 2000
1.5
5 E+03
3 E+06
5 E+03
3
I-131, Te-131 Te-132 78.2
h
, 3.0 E-09 3.7 E-09 0.050 700
0.7
3 E+03
2 E+06
3 E+03
10
I-132 [6]
Te-133 12.45
m
, 4.4 E-11 7.2 E-11 0.151 1000
1.7
1 E+05
1 E+08
2 E+05
3
I-133
Te-133m 55.4
m
, 1.9 E-10 2.8 E-10 0.344 1000
1.8
4 E+04
3 E+07
4 E+04
3
I-133, Te-133 Te-134 41.8
m
1.1 E-10 1.1 E-10 0.142 2000
1.7
9 E+04
5 E+07
8 E+04
3
I-134 [6]
Ordinance
77
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
I-120 81.0
m
, , 1.9 E-10 3.4 E-10 1.155 800
1.5
3 E+04
3 E+07
4 E+04
3
I-120m 53
m
, , 1.4 E-10 2.1 E-10 1.108 800
1.7
5 E+04
4 E+07
6 E+04
3
I-121 2.12
h
, , 3.9 E-11 8.2 E-11 0.077 400
0.4
1 E+05
1 E+08
2 E+05
10
Te-121
I-123 13.2
h
, 1.1 E-10 2.1 E-10 0.043 400
0.3
5 E+04
5 E+07
8 E+04
10
Te-123
I-124 4.18
d
, , 6.3 E-09 1.3 E-08 0.170 300
0.5
8 E+02
8 E+05
1 E+03
10
I-125 60.14
d
, 7.3 E-09 1.5 E-08 0.033 4
<0.1
7 E+02
7 E+05
1 E+03
10
I-126 13.02
d
, , , 1.4 E-08 2.9 E-08 0.078 700
0.7
3 E+02
4 E+05
6 E+02
3
I-128 24.99
m
, , , 2.2 E-11 4.6 E-11 0.016 1000
1.5
2 E+05
2 E+08
4 E+05
3
I-129 1.57
E7
y
, 5.1 E-08 1.1 E-07 0.016 100
0.3
9 E+01
1 E+05
2 E+02
1
Xe-129
I-130 12.36
h
, 9.6 E-10 2.0 E-09 0.325 1000
1.6
5 E+03
5 E+06
9 E+03
3
I-131 8.04
d
, 1.1 E-08 2.2 E-08 0.062 1000
1.4
5 E+02
5 E+05
8 E+02
3
Xe-131m
I-132 2.30
h
, 2.0 E-10 2.9 E-10 0.338 1000
1.7
3 E+04
3 E+07
4 E+04
3
I-132m 83.6
m
, 1.1 E-10 2.2 E-10 0.055 300
1.0
5 E+04
5 E+07
8 E+04
10
I-132 [6]
I-133 20.8
h
, 2.1 E-09 4.3 E-09 0.093 1000
1.6
2 E+03
2 E+06
4 E+03
3
Xe-133, Xe-133m I-134 52.6
m
, 7.9 E-11 1.1 E-10 0.385 1000
1.8
9 E+04
6 E+07
1 E+05
3
I-135 6.61
h
, 4.6 E-10 9.3 E-10 0.223 1000
1.6
1 E+04
1 E+07
2 E+04
3
Xe-135, Xe-135m Xe-122 / I-122
20.1 h
, , 0.284
800
1.3
7 E+07
7 E+04
Xe-123 2.08
h
, , 0.107
800
0.9
1 E+08
1 E+05
I-123
Xe-125 17.0
h
, , 0.060
300
0.2
3 E+08
3 E+05
I-125
Xe-127 36.41
d
, 0.059
400
0.3
3 E+08
3 E+05
Xe-129m 8.0
d
0.030
3000
1.9
4 E+09
4 E+06
Xe-131m 11.9
d
0.012
3000
2.1
9 E+09
9 E+06
Xe-133 5.245
d
, 0.016
1000
1.0
2 E+09
2 E+06
Xe-133m 2.188
d
0.016
2000
1.7
2 E+09
2 E+06
Xe-133
Xe-135 9.09
h
, 0.040
2000
1.6
3 E+08
3 E+05
Cs-135
Xe-135m 15.29
m
, 0.069
200
0.4
2 E+08
2 E+05
Cs-135
Xe-137 3.83
m
, 1.167
2
1.7
3 E+08
3 E+05
Xe-138 14.17
m
, 0.166
1000
1.7
6 E+07
6 E+04
Cs-138 [6]
Radiological Protection 78
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Cs-125 45
m
, , 2.3 E-11 3.5 E-11 0.114 500
0.7
3 E+05
2 E+08
4 E+05
10
Xe-125
Cs-127 6.25
h
, , 4.0 E-11 2.4 E-11 0.079 100
0.2
4 E+05
1 E+08
2 E+05
30
Xe-127
Cs-129 32.06
h
, , 8.1 E-11 6.0 E-11 0.063 30
<0.1
2 E+05
6 E+07
1 E+05
100
Cs-130 29.9
m
, , 1.5 E-11 2.8 E-11 0.087 500
0.8
4 E+05
3 E+08
6 E+05
10
Cs-131 9.69
d
4.5 E-11 5.8 E-11 0.016 2
<0.1
2 E+05
1 E+08
2 E+05
1000
Cs-132 6.475
d
, , , 3.8 E-10 5.0 E-10 0.119 50
0.1
2 E+04
1 E+07
2 E+04
100
Cs-134 2.062
y
, , 9.6 E-09 1.9 E-08 0.236 1000
1.1
5 E+02
5 E+05
9 E+02
3
Cs-134m 2.90
h
2.6 E-11 2.0 E-11 0.009 1000
1.5
5 E+05
2 E+08
3 E+05
3
Cs-134 [6] Cs-135 2.3
E6
y
9.9 E-10 2.0 E-09 0.000 600
0.7
5 E+03
5 E+06
8 E+03
10
Cs-135m 53
m
2.4 E-11 1.9 E-11 0.239 70
0.2
5 E+05
2 E+08
3 E+05
30
Cs-135
Cs-136 13.1
d
, 1.9 E-09 3.0 E-09 0.327 1000
1.5
3 E+03
3 E+06
4 E+03
3
Cs-137 / Ba-137m 30.0 y , 6.7 E-09 1.3 E-08 0.092 2000
1.5
8 E+02
7 E+05
1 E+03
3
Cs-138 32.2
m
, 4.6 E-11 9.2 E-11 0.445 1000
1.8
1 E+05
1 E+08
2 E+05
3
Ba-126 / Cs-126
96.5 m
, , 1.2 E-10 2.6 E-10 0.805 900
1.6
4 E+04
4 E+07
7 E+04
3
Ba-128 / Cs-128
2.43 d
, , 1.3 E-09 2.7 E-09 0.209 700
1.2
4 E+03
4 E+06
6 E+03
3
Ba-131 11.8
d
, , 3.5 E-10 4.5 E-10 0.087 300
0.4
2 E+04
1 E+07
2 E+04
10
Cs-131
Ba-131m 14.6
m
6.4 E-12 4.9 E-12 0.019 50
0.4
2 E+06
8 E+08
1 E+06
10
Ba-131
Ba-133 10.74
y
, 1.8 E-09 1.0 E-09 0.085 70
0.1
1 E+04
3 E+06
5 E+03
30
Ba-133m 38.9
h
2.8 E-10 5.5 E-10 0.019 2000
1.5
2 E+04
2 E+07
3 E+04
3
Ba-133
Ba-135m 28.7
h
2.3 E-10 4.5 E-10 0.018 2000
1.5
2 E+04
2 E+07
4 E+04
3
Ba-139 82.7
m
, 5.5 E-11 1.2 E-10 0.012 1000
1.7
8 E+04
9 E+07
2 E+05
3
Ba-140 12.74
d
, 1.6 E-09 2.5 E-09 0.031 1000
1.5
4 E+03
3 E+06
5 E+03
3
La-140 [6] Ba-141 18.27
m
, 3.5 E-11 7.0 E-11 0.152 1000
1.9
1 E+05
1 E+08
2 E+05
3
La-141
Ba-142 10.6
m
, 2.7 E-11 3.5 E-11 0.160 1000
1.7
3 E+05
2 E+08
3 E+05
3
La-142 [6] La-131 59
m
, , 3.6 E-11 3.5 E-11 0.116 400
0.6
3 E+05
1 E+08
2 E+05
10
Ba-131
La-132 4.8
h
, , 2.8 E-10 3.9 E-10 0.379 400
0.8
3 E+04
2 E+07
3 E+04
10
La-135 19.5
h
, , 2.5 E-11 3.0 E-11 0.017 2
<0.1
3 E+05
2 E+08
3 E+05
1000
La-137 6
E4
y
1.0 E-08 8.1 E-11 0.014 2
<0.1
1 E+05
5 E+05
8 E+02
1000
Ordinance
79
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
La-138 1.35E11
y
, , 1.8 E-07 1.1 E-09 0.185 400
0.4
9 E+03
3 E+04
5 E+01
10
La-140 40.272
h
, 1.5 E-09 2.0 E-09 0.332 1000
1.8
5 E+03
3 E+06
6 E+03
3
La-141 3.93
h
, 2.2 E-10 3.6 E-10 0.016 1000
1.6
3 E+04
2 E+07
4 E+04
3
Ce-141
La-142 92.5
m
, 1.5 E-10 1.8 E-10 0.490 1000
1.8
6 E+04
3 E+07
6 E+04
3
La-143 14.23
m
, 3.3 E-11 5.6 E-11 0.219 1000
1.6
2 E+05
2 E+08
3 E+05
3
Ce-143
Ce-134 / La-134
72.0 h
, , 1.6 E-09 2.5 E-09 0.149 600
1.0
4 E+03
3 E+06
5 E+03
10
Ce-135 17.6
h
, , 7.6 E-10 7.9 E-10 0.271 2000
1.8
1 E+04
7 E+06
1 E+04
3
La-135
Ce-137 9.0
h
, 1.9 E-11 2.5 E-11 0.016 10
<0.1
4 E+05
3 E+08
4 E+05
1000
La-137
Ce-137m 34.4
h
, 5.9 E-10 5.4 E-10 0.016 2000
1.6
2 E+04
8 E+06
1 E+04
3
Ce-137, La-137 Ce-139 137.66
d
, 1.4 E-09 2.6 E-10 0.036 500
0.5
4 E+04
4 E+06
6 E+03
10
Ce-141 32.501
d
3.1 E-09 7.1 E-10 0.014 2000
1.6
1 E+04
2 E+06
3 E+03
3
Ce-143 33.0
h
, 1.0 E-09 1.1 E-09 0.053 1000
1.6
9 E+03
5 E+06
8 E+03
3
Pr-143
Ce-144 / Pr-144m 284.3 d
, 2.9 E-08 5.2 E-09 0.005 800
0.9
2 E+03
2 E+05
3 E+02
10
Pr-144
Pr-136 13.1
m
, , 2.5 E-11 3.3 E-11 0.375 600
1.1
3 E+05
2 E+08
3 E+05
3
Pr-137 76.6
m
, , 3.5 E-11 4.0 E-11 0.083 300
0.5
3 E+05
1 E+08
2 E+05
10
Ce-137
Pr-138m 2.1
h
, , 1.3 E-10 1.3 E-10 0.379 600
0.8
8 E+04
4 E+07
6 E+04
10
Pr-139 4.51
h
, , 3.0 E-11 3.1 E-11 0.028 100
0.1
3 E+05
2 E+08
3 E+05
30
Ce-139
Pr-142 19.13
h
, , 7.4 E-10 1.3 E-09 0.011 1000
1.6
8 E+03
7 E+06
1 E+04
3
Pr-142m 14.6
m
9.4 E-12 1.7 E-11 <0.001 <1
<0.1
6 E+05
5 E+08
9 E+05
10
Pr-142
Pr-143 13.56
d
, 2.2 E-09 1.2 E-09 0.000 1000
1.5
8 E+03
2 E+06
4 E+03
3
Pr-144 17.28
m
, 3.0 E-11 5.0 E-11 0.099 1000
1.6
2 E+05
2 E+08
3 E+05
3
Pr-145 5.98
h
, 2.6 E-10 3.9 E-10 0.002 1000
1.6
3 E+04
2 E+07
3 E+04
3
Pr-147 13.6
m
, 3.0 E-11 3.3 E-11 0.144 1000
1.8
3 E+05
2 E+08
3 E+05
3
Nd-147
Nd-136 50.65
m
, , 8.9 E-11 9.9 E-11 0.061 200
0.3
1 E+05
6 E+07
9 E+04
30
Pr-136 [6] Nd-138 / Pr-138 5.04
h
, , 3.8 E-10 6.4 E-10 0.398 700
1.3
2 E+04
1 E+07
2 E+04
3
Nd-139 29.7
m
, , 1.7 E-11 2.0 E-11 0.070 300
0.4
5 E+05
3 E+08
5 E+05
10
Pr-139
Nd-139m 5.5
h
, , 2.5 E-10 2.5 E-10 0.246 500
0.6
4 E+04
2 E+07
3 E+04
10
Pr-139, Nd-139 Nd-140 3.37
d
2.0 E-09 2.8 E-09
4 E+03
3 E+06
4 E+03
3
Radiological Protection 80
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Nd-141 2.49
h
, , 8.8 E-12 8.3 E-12 0.021 50
0.1
1 E+06
6 E+08
9 E+05
100
Nd-147 10.98
d
, 2.1 E-09 1.1 E-09 0.027 1000
1.5
9 E+03
2 E+06
4 E+03
3
Pm-147
Nd-149 1.73
h
, 1.3 E-10 1.2 E-10 0.063 2000
1.8
8 E+04
4 E+07
6 E+04
3
Pm-149
Nd-151 12.44
m
2.9 E-11 3.0 E-11 0.137 1000
1.7
3 E+05
2 E+08
3 E+05
3
Pm-151
Pm-141 20.90
m
, , 2.5 E-11 3.6 E-11 0.137 500
0.9
3 E+05
2 E+08
3 E+05
10
Nd-141, Nd-141m Pm-143 265
d
, 9.6 E-10 2.3 E-10 0.057 7
<0.1
4 E+04
5 E+06
9 E+03
300
Pm-144 363
d
, 5.4 E-09 9.7 E-10 0.248 40
0.1
1 E+04
9 E+05
2 E+03
100
Pm-145 17.7
y
, 2.4 E-09 1.1 E-10 0.013 10
<0.1
9 E+04
2 E+06
3 E+03
1000
Pm-146 2020
d
, , 1.3 E-08 9.0 E-10 0.122 500
0.6
1 E+04
4 E+05
6 E+02
10
Sm-146
Pm-147 2.6234
y
, 3.5 E-09 2.6 E-10 <0.001 500
0.6
4 E+04
1 E+06
2 E+03
10
Sm-147
Pm-148 5.37
d
, 2.2 E-09 2.7 E-09 0.091 1000
1.6
4 E+03
2 E+06
4 E+03
3
Pm-148m 41.3
d
, 4.3 E-09 1.8 E-09 0.306 1000
1.4
6 E+03
1 E+06
2 E+03
3
Sm-148
Pm-149 53.08
h
, 8.2 E-10 9.9 E-10 0.002 1000
1.6
1 E+04
6 E+06
1 E+04
3
Pm-150 2.68
h
, 2.1 E-10 2.6 E-10 0.226 1000
1.8
4 E+04
2 E+07
4 E+04
3
Pm-151 28.4
h
, 6.4 E-10 7.3 E-10 0.052 1000
1.5
1 E+04
8 E+06
1 E+04
3
Sm-151
Sm-141 10.2
m
, , 2.7 E-11 3.9 E-11 0.287 500
1.0
3 E+05
2 E+08
3 E+05
10
Pm-141 [6] Sm-141m 22.6
m
, , 5.6 E-11 6.5 E-11 0.338 900
1.1
2 E+05
9 E+07
1 E+05
3
Pm-141, Sm-141 Sm-142 / Pm-142 72.49 m , , 1.1 E-10 1.9 E-10 0.752 800
1.5
5 E+04
5 E+07
8 E+04
3
Sm-145 340
d
, 1.1 E-09 2.1 E-10 0.026 20
<0.1
5 E+04
5 E+06
8 E+03
100
Pm-145
Sm-146 1.03
E8
y
6.7 E-06 5.4 E-08 <0.001 <1
<0.1
2 E+02
7 E+02
1 E+00
1
Sm-147 1.06E11
y
6.1 E-06 4.9 E-08 <0.001 <1
<0.1
2 E+02
8 E+02
1 E+00
1
Sm-151 90
y
, 2.6 E-09 9.8 E-11 <0.001 <1
<0.1
1 E+05
2 E+06
3 E+03
100
Sm-153 46.7
h
, 6.8 E-10 7.4 E-10 0.016 1000
1.6
1 E+04
7 E+06
1 E+04
3
Sm-155 22.1
m
, 2.8 E-11 2.9 E-11 0.019 1000
1.6
3 E+05
2 E+08
3 E+05
3
Eu-155
Sm-156 9.4
h
, 2.8 E-10 2.5 E-10 0.022 1000
1.4
4 E+04
2 E+07
3 E+04
3
Eu-156 [6] Eu-145 5.94
d
, , 7.3 E-10 7.5 E-10 0.217 60
0.2
1 E+04
7 E+06
1 E+04
30
Sm-145
Eu-146 4.61
d
, , 1.2 E-09 1.3 E-09 0.375 100
0.3
8 E+03
4 E+06
7 E+03
30
Sm-146
Eu-147 24
d
, , , 1.0 E-09 4.4 E-10 0.085 300
0.3
2 E+04
5 E+06
8 E+03
30
Sm-147, Pm-143
Ordinance
81
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Eu-148 54.5
d
, , , 2.3 E-09 1.3 E-09 0.327 70
0.2
8 E+03
2 E+06
4 E+03
30
Pm-144
Eu-149 93.1
d
, 2.3 E-10 1.0 E-10 0.018 20
<0.1
1 E+05
2 E+07
4 E+04
300
Eu-150-1 12.62
h
, , , 2.8 E-10 3.8 E-10 0.008 1000
1.4
3 E+04
2 E+07
3 E+04
3
Eu-150-2 34.2
y
, 3.4 E-08 1.3 E-09 0.238 100
0.2
8 E+03
1 E+05
2 E+02
30
Eu-152 13.33
y
, , , 2.7 E-08 1.4 E-09 0.179 700
0.8
7 E+03
2 E+05
3 E+02
10
Gd-152
Eu-152m 9.32
h
, , , 3.2 E-10 5.0 E-10 0.047 900
1.3
2 E+04
2 E+07
3 E+04
3
Gd-152
Eu-154 8.80
y
, , 3.5 E-08 2.0 E-09 0.185 2000
1.8
5 E+03
1 E+05
2 E+02
3
Eu-155 4.96
y
, 4.7 E-09 3.2 E-10 0.012 200
0.3
3 E+04
1 E+06
2 E+03
30
Eu-156 15.19
d
, 3.0 E-09 2.2 E-09 0.188 1000
1.5
5 E+03
2 E+06
3 E+03
3
Eu-157 15.15
h
, 4.4 E-10 6.0 E-10 0.049 1000
1.6
2 E+04
1 E+07
2 E+04
3
Eu-158 45.9
m
, 7.5 E-11 9.4 E-11 0.220 1000
1.8
1 E+05
7 E+07
1 E+05
3
Gd-145 22.9
m
, , 3.5 E-11 4.4 E-11 0.360 500
0.9
2 E+05
1 E+08
2 E+05
10
Eu-145 [6] Gd-146 48.3
d
, 5.2 E-09 9.6 E-10 0.057 600
0.9
1 E+04
1 E+06
2 E+03
10
Eu-146 [6] Gd-147 38.1
h
, , 5.9 E-10 6.1 E-10 0.206 400
0.4
2 E+04
8 E+06
1 E+04
10
Eu-147
Gd-148 93
y
3.0 E-05 5.5 E-08 <0.001 <1
<0.1
2 E+02
2 E+02 [5] 3 E-01
1
Gd-149 9.4
d
, 7.9 E-10 4.5 E-10 0.076 400
0.6
2 E+04
6 E+06
1 E+04
10
Eu-149
Gd-151 120
d
, , 9.3 E-10 2.0 E-10 0.018 200
0.2
5 E+04
5 E+06
9 E+03
30
Sm-147
Gd-152 1.08E14
y
2.2 E-05 4.1 E-08 <0.001 <1
<0.1
2 E+02
2 E+02 [5] 4 E-01
1
Gd-153 242
d
, 2.5 E-09 2.7 E-10 0.029 30
0.1
4 E+04
2 E+06
3 E+03
30
Gd-159 18.56
h
, 3.9 E-10 4.9 E-10 0.010 1000
1.5
2 E+04
1 E+07
2 E+04
3
Tb-147 1.65
h
, , 1.2 E-10 1.6 E-10 0.356 400
0.8
6 E+04
4 E+07
7 E+04
10
Gd-147 [6] Tb-149 4.15
h
, , , 3.1 E-09 2.5 E-10 0.241 400
0.6
4 E+04
2 E+06
3 E+03
10
Gd-149, Eu-145 Tb-150 3.27
h
, , 1.8 E-10 2.5 E-10 0.346 400
0.8
4 E+04
3 E+07
5 E+04
10
Tb-151 17.6
h
, , , 3.3 E-10 3.4 E-10 0.147 400
0.6
3 E+04
2 E+07
3 E+04
10
Gd-151, Eu-147 Tb-153 2.34
d
, , 2.4 E-10 2.5 E-10 0.045 100
0.1
4 E+04
2 E+07
3 E+04
30
Gd-153
Tb-154 21.4
h
, , 6.0 E-10 6.5 E-10 0.313 400
0.6
2 E+04
8 E+06
1 E+04
10
Tb-155 5.32
d
, 2.5 E-10 2.1 E-10 0.031 200
0.2
5 E+04
2 E+07
3 E+04
30
Tb-156 5.34
d
, 1.4 E-09 1.2 E-09 0.277 500
0.8
8 E+03
4 E+06
6 E+03
10
Radiological Protection 82
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Tb-156m-1 [2]
5.0 h
1.3 E-10 8.1 E-11 0.001 8
0.6
1 E+05
4 E+07
6 E+04
10
Tb-156 [6] Tb-156m-2 [2]
24.4 h
2.3 E-10 1.7 E-10 0.007 4
<0.1
6 E+04
2 E+07
4 E+04
1000
Tb-157 150
y
, 7.9 E-10 3.4 E-11 0.001 6
<0.1
3 E+05
6 E+06
1 E+04
1000
Tb-158 150
y
, , 3.0 E-08 1.1 E-09 0.127 400
0.6
9 E+03
2 E+05
3 E+02
10
Tb-160 72.3
d
, 5.4 E-09 1.6 E-09 0.169 1000
1.7
6 E+03
9 E+05
2 E+03
3
Tb-161 6.91
d
, 1.2 E-09 7.2 E-10 0.013 1000
1.3
1 E+04
4 E+06
7 E+03
3
Dy-155 10.0
h
, , 1.2 E-10 1.3 E-10 0.094 100
0.1
8 E+04
4 E+07
7 E+04
30
Tb-155
Dy-157 8.1
h
, 5.5 E-11 6.1 E-11 0.065 40
0.1
2 E+05
9 E+07
2 E+05
100
Tb-157
Dy-159 144.4
d
, 2.5 E-10 1.0 E-10 0.015 10
<0.1
1 E+05
2 E+07
3 E+04
1000
Dy-165 2.334
h
, 8.7 E-11 1.1 E-10 0.005 1000
1.6
9 E+04
6 E+07
1 E+05
3
Dy-166 81.6
h
, 1.8 E-09 1.6 E-09 0.010 1000
1.1
6 E+03
3 E+06
5 E+03
3
Ho-166
Ho-155 48
m
, , 3.2 E-11 3.7 E-11 0.066 300
0.5
3 E+05
2 E+08
3 E+05
10
Dy-155
Ho-157 12.6
m
, , 7.6 E-12 6.5 E-12 0.088 300
0.3
2 E+06
7 E+08
1 E+06
30
Dy-157
Ho-159 33
m
, , 1.0 E-11 7.9 E-12 0.069 200
0.2
1 E+06
5 E+08
8 E+05
30
Dy-159
Ho-161 2.5
h
, 1.0 E-11 1.3 E-11 0.022 20
<0.1
8 E+05
5 E+08
8 E+05
300
Ho-162 15
m
, , 4.5 E-12 3.3 E-12 0.032 70
0.2
3 E+06
1 E+09
2 E+06
30
Ho-162m 68
m
, 3.3 E-11 2.6 E-11 0.094 300
0.3
4 E+05
2 E+08
3 E+05
30
Ho-162
Ho-164 29
m
, , 1.3 E-11 9.5 E-12 0.009 600
0.7
1 E+06
4 E+08
6 E+05
10
Ho-164m 37.5
m
1.6 E-11 1.6 E-11 0.014 20
<0.1
6 E+05
3 E+08
5 E+05
300
Ho-164
Ho-166 26.80
h
, 8.3 E-10 1.4 E-09 0.005 1000
1.7
7 E+03
6 E+06
1 E+04
3
Ho-166m 1.20
E3
y
, 7.8 E-08 2.0 E-09 0.268 800
0.9
5 E+03
6 E+04
1 E+02
10
Ho-167 3.1
h
, 1.0 E-10 8.3 E-11 0.061 1000
1.4
1 E+05
5 E+07
8 E+04
3
Er-161 3.24
h
, , 8.5 E-11 8.0 E-11 0.139 400
0.4
1 E+05
6 E+07
1 E+05
10
Ho-161
Er-165 10.36
h
1.4 E-11 1.9 E-11 0.011 7
<0.1
5 E+05
4 E+08
6 E+05
1000
Er-169 9.3
d
, 9.2 E-10 3.7 E-10 <0.001 1000
1.0
3 E+04
5 E+06
9 E+03
10
Er-171 7.52
h
, 3.0 E-10 3.6 E-10 0.064 2000
1.9
3 E+04
2 E+07
3 E+04
3
Tm-171
Er-172 49.3
h
, 1.2 E-09 1.0 E-09 0.084 1000
1.0
1 E+04
4 E+06
7 E+03
10
Tm-172
Tm-162 21.7
m
, , 2.7 E-11 2.9 E-11 0.261 300
0.9
3 E+05
2 E+08
3 E+05
10
Ordinance
83
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Tm-166 7.70
h
, , 2.8 E-10 2.8 E-10 0.270 200
0.4
4 E+04
2 E+07
3 E+04
10
Tm-167 9.24
d
, 1.0 E-09 5.6 E-10 0.029 2000
1.1
2 E+04
5 E+06
8 E+03
3
Tm-170 128.6
d
, , 5.2 E-09 1.3 E-09 0.001 1000
1.6
8 E+03
1 E+06
2 E+03
3
Tm-171 1.92
y
, 9.1 E-10 1.1 E-10 <0.001 <1
<0.1
9 E+04
5 E+06
9 E+03
1000
Tm-172 63.6
h
, 1.4 E-09 1.7 E-09 0.069 1000
1.5
6 E+03
4 E+06
6 E+03
3
Tm-173 8.24
h
, 2.6 E-10 3.1 E-10 0.063 1000
1.6
3 E+04
2 E+07
3 E+04
3
Tm-175 15.2
m
, 3.1 E-11 2.7 E-11 0.160 2000
2.0
4 E+05
2 E+08
3 E+05
3
Yb-175
Yb-162 18.9
m
, 2.3 E-11 2.3 E-11 0.027 60
0.1
4 E+05
2 E+08
4 E+05
100
Tm-162 [6] Yb-166 56.7
h
, 9.5 E-10 9.5 E-10 0.022 10
0.1
1 E+04
5 E+06
9 E+03
100
Tm-166 [6] Yb-167 17.5
m
, , 9.5 E-12 6.7 E-12 0.053 200
0.4
1 E+06
5 E+08
9 E+05
10
Tm-167
Yb-169 32.01
d
, 2.4 E-09 7.1 E-10 0.061 1000
1.0
1 E+04
2 E+06
3 E+03
10
Yb-175 4.19
d
, 7.0 E-10 4.4 E-10 0.007 1000
1.1
2 E+04
7 E+06
1 E+04
3
Yb-177 1.9
h
, 9.4 E-11 9.7 E-11 0.028 1000
1.5
1 E+05
5 E+07
9 E+04
3
Lu-177
Yb-178 74
m
, 1.1 E-10 1.2 E-10 0.006 1000
1.3
8 E+04
5 E+07
8 E+04
3
Lu-178
Lu-169 34.06
h
, , 4.9 E-10 4.6 E-10 0.154 100
0.2
2 E+04
1 E+07
2 E+04
30
Yb-169
Lu-170 2.00
d
, , 9.5 E-10 9.9 E-10 0.281 60
0.3
1 E+04
5 E+06
9 E+03
10
Lu-171 8.22
d
, 9.3 E-10 6.7 E-10 0.115 30
0.1
1 E+04
5 E+06
9 E+03
100
Lu-172 6.70
d
, , 1.8 E-09 1.3 E-09 0.283 300
0.5
8 E+03
3 E+06
5 E+03
10
Lu-173 1.37
y
, 1.5 E-09 2.6 E-10 0.028 30
0.1
4 E+04
3 E+06
6 E+03
100
Lu-174 3.31
y
, , 2.9 E-09 2.7 E-10 0.024 10
<0.1
4 E+04
2 E+06
3 E+03
100
Lu-174m 142
d
, 2.6 E-09 5.3 E-10 0.015 30
<0.1
2 E+04
2 E+06
3 E+03
300
Lu-174
Lu-176 3.60E10
y
, 4.6 E-08 1.8 E-09 0.081 2000
2.3
6 E+03
1 E+05
2 E+02
3
Lu-176m 3.68
h
, 1.6 E-10 1.7 E-10 0.003 1000
1.8
6 E+04
3 E+07
5 E+04
3
Lu-177 6.71
d
, 1.1 E-09 5.3 E-10 0.006 1000
1.3
2 E+04
5 E+06
8 E+03
3
Lu-177m 160.9
d
, 1.2 E-08 1.7 E-09 0.166 2000
2.6
6 E+03
4 E+05
7 E+02
3
Lu-177
Lu-178 28.4
m
, 4.1 E-11 4.7 E-11 0.022 1000
1.8
2 E+05
1 E+08
2 E+05
3
Lu-178m 22.7
m
, 5.6 E-11 3.8 E-11 0.182 2000
2.8
3 E+05
9 E+07
1 E+05
3
Lu-179 4.59
h
, 1.6 E-10 2.1 E-10 0.005 1000
1.6
5 E+04
3 E+07
5 E+04
3
Radiological Protection 84
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Hf-170 16.01
h
, 4.3 E-10 4.8 E-10 0.091 200
0.3
2 E+04
1 E+07
2 E+04
30
Lu-170 [6] Hf-172 1.87
y
, 3.7 E-08 1.0 E-09 0.030 100
0.1
1 E+04
1 E+05
2 E+02
100
Lu-172 [6] Hf-173 24.0
h
, , 2.2 E-10 2.3 E-10 0.071 300
0.3
4 E+04
2 E+07
4 E+04
30
Lu-173
Hf-175 70
d
, 8.8 E-10 4.1 E-10 0.065 200
0.2
2 E+04
6 E+06
9 E+03
30
Hf-177m 51.4
m
1.5 E-10 8.1 E-11 0.370 4000
4.5
1 E+05
3 E+07
6 E+04
1
Hf-178m 31
y
3.1 E-07 4.7 E-09 0.378 2000
2.1
2 E+03
2 E+04
3 E+01
3
Hf-179m 25.1
d
3.2 E-09 1.2 E-09 0.149 1000
1.6
8 E+03
2 E+06
3 E+03
3
Hf-180m 5.5
h
2.0 E-10 1.7 E-10 0.166 700
1.1
6 E+04
3 E+07
4 E+04
3
Hf-181 42.4
d
, 4.1 E-09 1.1 E-09 0.089 2000
1.9
9 E+03
1 E+06
2 E+03
3
Hf-182 9
E6
y
, 3.6 E-07 3.0 E-09 0.039 500
0.6
3 E+03
1 E+04
2 E+01
10
Ta-182 [6] Hf-182m 61.5
m
, 7.1 E-11 4.2 E-11 0.150 1000
1.8
2 E+05
7 E+07
1 E+05
3
Ta-182 [6], Hf182
Hf-183 64
m
, 8.3 E-11 7.3 E-11 0.116 1000
1.6
1 E+05
6 E+07
1 E+05
3
Ta-183
Hf-184 4.12
h
, 4.5 E-10 5.2 E-10 0.043 2000
2.2
2 E+04
1 E+07
2 E+04
3
Ta-184
Ta-172 36.8
m
, , 5.7 E-11 5.3 E-11 0.244 700
1.5
2 E+05
9 E+07
1 E+05
3
Hf-172 [6] Ta-173 3.65
h
, , 1.6 E-10 1.9 E-10 0.098 500
0.7
5 E+04
3 E+07
5 E+04
10
Hf-173
Ta-174 1.2
h
, , 6.6 E-11 5.7 E-11 0.106 700
1.2
2 E+05
8 E+07
1 E+05
3
Hf-174
Ta-175 10.5
h
, , 2.0 E-10 2.1 E-10 0.137 200
0.3
5 E+04
3 E+07
4 E+04
30
Hf-175
Ta-176 8.08
h
, , 3.3 E-10 3.1 E-10 0.280 100
0.5
3 E+04
2 E+07
3 E+04
10
Ta-177 56.6
h
, 1.3 E-10 1.1 E-10 0.015 100
0.2
9 E+04
4 E+07
6 E+04
30
Ta-178-1 [2] 9.31
m
, 0.021
10
0.2
30
Ta-178-2 [2]
2.2 h
, 1.1 E-10 7.8 E-11 0.172 700
1.2
1 E+05
5 E+07
8 E+04
3
Ta-179 664.9
d
2.9 E-10 6.5 E-11 0.008 6
<0.1
2 E+05
2 E+07
3 E+04
1000
Ta-180 1.0
E13
y
, 1.4 E-08 8.4 E-10 0.094 600
1.0
1 E+04
4 E+05
6 E+02
10
Ta-180m 8.1
h
, , 6.2 E-11 5.4 E-11 0.011 200
0.4
2 E+05
8 E+07
1 E+05
10
Ta-182 115.0
d
, 7.4 E-09 1.5 E-09 0.194 1000
1.8
7 E+03
7 E+05
1 E+03
3
Ta-182m 15.84
m
3.6 E-11 1.2 E-11 0.044 3000
2.7
8 E+05
1 E+08
2 E+05
3
Ta-182 [6] Ta-183 5.1
d
, 2.0 E-09 1.3 E-09 0.051 2000
2.3
8 E+03
3 E+06
4 E+03
3
Ordinance
85
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Ta-184 8.7
h
, 6.3 E-10 6.8 E-10 0.247 2000
2.8
1 E+04
8 E+06
1 E+04
3
Ta-185 49
m
, 7.2 E-11 6.8 E-11 0.033 2000
2.3
1 E+05
7 E+07
1 E+05
3
W-185
Ta-186 10.5
m
, 3.1 E-11 3.3 E-11 0.252 2000
2.5
3 E+05
2 E+08
3 E+05
3
W-176 2.3
h
, 7.6 E-11 1.1 E-10 0.036 20
0.1
9 E+04
7 E+07
1 E+05
30
Ta-176 [6] W-177 135
m
, , 4.6 E-11 6.1 E-11 0.140 300
0.4
2 E+05
1 E+08
2 E+05
10
Ta-177
W-178 / Ta-178-1 21.7 d , 1.2 E-10 2.5 E-10 0.024 20
0.2
4 E+04
4 E+07
7 E+04
30
W-179 37.5
m
, 1.8 E-12 3.3 E-12 0.019 10
<0.1
3 E+06
3 E+09
5 E+06
300
Ta-179
W-181 121.2
d
, 4.3 E-11 8.2 E-11 0.009 7
<0.1
1 E+05
1 E+08
2 E+05
1000
W-185 75.1
d
, 2.2 E-10 5.0 E-10 <0.001 1000
1.1
2 E+04
2 E+07
4 E+04
3
W-187 23.9
h
, 3.3 E-10 7.1 E-10 0.075 2000
1.6
1 E+04
2 E+07
3 E+04
3
Re-187
W-188 69.4
d
, 8.4 E-10 2.3 E-09 <0.001 1000
1.0
4 E+03
6 E+06
1 E+04
10
Re-188
Re-177 14.0
m
, , 2.2 E-11 2.2 E-11 0.100 300
0.8
5 E+05
2 E+08
4 E+05
10
W-177 [6]
Re-178 13.2
m
, , 2.4 E-11 2.5 E-11 0.256 700
1.6
4 E+05
2 E+08
3 E+05
3
W-178
Re-181 20
h
, , 3.7 E-10 4.2 E-10 0.124 500
0.6
2 E+04
1 E+07
2 E+04
10
W-181
Re-182-1 [2] 12.7
h
, , 3.0 E-10 2.7 E-10 0.282 900
1.7
4 E+04
2 E+07
3 E+04
3
Re-182-2 [2]
64.0 h
, 1.7 E-09 1.4 E-09 0.177 80
0.6
7 E+03
3 E+06
5 E+03
10
Re-183 71
d
, 1.8 E-09 7.6 E-10
1 E+04
3 E+06
5 E+03
10
Re-184 38.0
d
, 1.8 E-09 1.0 E-09 0.138 300
0.6
1 E+04
3 E+06
5 E+03
10
Re-184m 165
d
, 4.8 E-09 1.5 E-09 0.063 300
0.8
7 E+03
1 E+06
2 E+03
10
Re-184 [6] Re-186 90.64
h
, , 1.2 E-09 1.5 E-09 0.004 2000
1.6
7 E+03
4 E+06
7 E+03
3
Re-186m 2.0
E5
y
7.9 E-09 2.2 E-09 0.004 10
0.1
5 E+03
6 E+05
1 E+03
100
Re-186
Re-187 5
E10
y
4.6 E-12 5.1 E-12 <0.001 <1
<0.1
2 E+06
1 E+09
2 E+06
100
Re-188 16.98
h
, 7.4 E-10 1.4 E-09 0.010 1000
1.8
7 E+03
7 E+06
1 E+04
3
Re-188m 18.6
m
2.0 E-11 3.0 E-11 0.016 40
0.2
3 E+05
3 E+08
4 E+05
30
Re-188
Re-189 24.3
h
, 6.0 E-10 7.8 E-10 0.011 2000
1.6
1 E+04
8 E+06
1 E+04
3
Os-189m
Os-180 / Re-180
22 m
, , 2.5 E-11 1.7 E-11 0.199 300
1.0
6 E+05
2 E+08
3 E+05
10
Os-181 105
m
, , 1.0 E-10 8.9 E-11 0.186 400
0.6
1 E+05
5 E+07
8 E+04
10
Re-181 [6] Os-182 22
h
, 5.2 E-10 5.6 E-10 0.071 100
0.2
2 E+04
1 E+07
2 E+04
30
Re-182-1 [6]
Radiological Protection 86
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Os-185 94
d
, 1.4 E-09 5.1 E-10 0.112 40
0.1
2 E+04
4 E+06
6 E+03
100
Os-189m 6.0
h
7.9 E-12 1.8 E-11 <0.001 5
<0.1
6 E+05
6 E+08
1 E+06
1000
Os-191 15.4
d
, 1.5 E-09 5.7 E-10 0.015 400
0.4
2 E+04
3 E+06
6 E+03
10
Os-191m 13.03
h
1.4 E-10 9.6 E-11 0.002 5
0.1
1 E+05
4 E+07
6 E+04
100
Os-191
Os-193 30.0
h
, 6.8 E-10 8.1 E-10 0.012 1000
1.6
1 E+04
7 E+06
1 E+04
3
Os-194 6.0
y
, 4.2 E-08 2.4 E-09 0.001 2
<0.1
4 E+03
1 E+05
2 E+02
30
Ir-194
Ir-182 15
m
, , 4.0 E-11 4.8 E-11 0.584 1000
1.9
2 E+05
1 E+08
2 E+05
3
Os-182
Ir-184 3.02
h
, , 1.9 E-10 1.7 E-10 0.296 1000
1.5
6 E+04
3 E+07
4 E+04
3
Ir-185 14.0
h
, , 2.6 E-10 2.6 E-10 0.091 300
0.5
4 E+04
2 E+07
3 E+04
10
Os-185 [6] Ir-186-1 [2]
1.75 h
, , 7.1 E-11 6.1 E-11 0.152 900
0.9
2 E+05
7 E+07
1 E+05
10
Ir-186-2 [2]
15.8 h
, , 5.0 E-10 4.9 E-10 0.243 1000
1.0
2 E+04
1 E+07
2 E+04
10
Ir-187 10.5
h
, 1.2 E-10 1.2 E-10 0.059 100
0.1
8 E+04
4 E+07
7 E+04
30
Ir-188 41.5
h
, , 6.2 E-10 6.3 E-10 0.223 500
0.5
2 E+04
8 E+06
1 E+04
10
Ir-189 13.3
d
, 4.6 E-10 2.4 E-10 0.016 50
0.1
4 E+04
1 E+07
2 E+04
100
Ir-190 12.1
d
, 2.5 E-09 1.2 E-09 0.228 800
1.3
8 E+03
2 E+06
3 E+03
3
Ir-190m-1 [2]
3.1 h
, 1.4 E-10 1.2 E-10 0.247 900
0.9
8 E+04
4 E+07
6 E+04
10
Ir-190
Ir-190m-2 [2]
1.2 h
1.1 E-11 8.0 E-12 <0.001 5
<0.1
1 E+06
5 E+08
8 E+05
100
Ir-190 [6] Ir-192 74.02
d
, , 4.9 E-09 1.4 E-09 0.131 2000
1.6
7 E+03
1 E+06
2 E+03
3
Ir-192m 241
y
1.9 E-08 3.1 E-10 0.025 2
<0.1
3 E+04
3 E+05
4 E+02
300
Ir-192 [6] Ir-193m 10.6
d
1.0 E-09 2.7 E-10
4 E+04
5 E+06
8 E+03
100
Ir-194 19.15
h
, 7.5 E-10 1.3 E-09 0.017 1000
1.6
8 E+03
7 E+06
1 E+04
3
Ir-194m 171
d
, 8.2 E-09 2.1 E-09 0.367 1000
1.5
5 E+03
6 E+05
1 E+03
3
Ir-195 2.5
h
, 1.0 E-10 1.0 E-10 0.012 1000
1.7
1 E+05
5 E+07
8 E+04
3
Ir-195m 3.8
h
, 2.4 E-10 2.1 E-10 0.073 2000
2.6
5 E+04
2 E+07
3 E+04
3
Ir-195
Pt-186 2.0
h
, , 6.6 E-11 9.3 E-11 0.115 20
0.1
1 E+05 8 E+07
1 E+05
100
Ir-186-1 [6], Os-182
Pt-188 10.2
d
, 6.3 E-10 7.6 E-10 0.035 800
0.8
1 E+04
8 E+06
1 E+04
10
Ir-188 [6] Pt-189 10.87
h
, , 7.3 E-11 1.2 E-10 0.054 200
0.2
8 E+04
7 E+07
1 E+05
30
Ir-189
Ordinance
87
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Pt-190 6.1
E11
y
2.3 E-07 8.2 E-09
1 E+03
2 E+04
4 E+01
3
Pt-191 2.8
d
, 1.9 E-10 3.4 E-10 0.053 200
0.3
3 E+04
3 E+07
4 E+04
30
Pt-193 50
y
2.7 E-11 3.1 E-11 0.001 4
<0.1
3 E+05
2 E+08
3 E+05
1000
Pt-193m 4.33
d
2.1 E-10 4.5 E-10 0.003 2000
1.8
2 E+04
2 E+07
4 E+04
3
Pt-193
Pt-195m 4.02
d
3.1 E-10 6.3 E-10 0.016 2000
2.1
2 E+04
2 E+07
3 E+04
3
Pt-197 18.3
h
, 1.6 E-10 4.0 E-10 0.005 1000
1.5
3 E+04
3 E+07
5 E+04
3
Pt-197m 94.4
m
, 4.3 E-11 8.4 E-11 0.015 2000
1.6
1 E+05
1 E+08
2 E+05
3
Pt-197
Pt-199 30.8
m
, 2.2 E-11 3.9 E-11 0.031 1000
1.7
3 E+05
2 E+08
4 E+05
3
Au-199
Pt-200 12.5
h
, 4.0 E-10 1.2 E-09 0.011 1000
1.5
8 E+03
1 E+07
2 E+04
3
Au-200
Au-193 17.65
h
, 1.6 E-10 1.3 E-10 0.029 400
0.5
8 E+04
3 E+07
5 E+04
10
Pt-193
Au-194 39.5
h
, , 3.8 E-10 4.2 E-10 0.157 200
0.2
2 E+04
1 E+07
2 E+04
30
Au-195 183
d
, 1.2 E-09 2.5 E-10 0.017 40
0.2
4 E+04
4 E+06
7 E+03
30
Au-196 6.2
d
, , 3.7 E-10 4.4 E-10
2 E+04
1 E+07
2 E+04
10
Au-198 2.696
d
, 1.1 E-09 1.0 E-09 0.065 1000
1.6
1 E+04
5 E+06
8 E+03
3
Au-198m 2.30
d
2.0 E-09 1.3 E-09 0.094 3000
3.9
8 E+03
3 E+06
4 E+03
1
Au-198
Au-199 3.139
d
, 7.6 E-10 4.4 E-10 0.015 2000
1.5
2 E+04
7 E+06
1 E+04
3
Au-200 48.4
m
, 5.6 E-11 6.8 E-11 0.044 1000
1.6
1 E+05
9 E+07
1 E+05
3
Au-200m 18.7
h
, 1.0 E-09 1.1 E-09 0.323 2000
2.1
9 E+03
5 E+06
8 E+03
3
Au-200
Au-201 26.4
m
, 2.9 E-11 2.4 E-11 0.008 1000
1.6
4 E+05
2 E+08
3 E+05
3
Hg-193 3.5
h
, , 1.0 E-10 8.2 E-11 0.037 800
1.1
1 E+05
5 E+07
8 E+04
3
Au-193
Hg-193m 11.1
h
, , 3.8 E-10 4.0 E-10 0.162 1000
0.9
3 E+04
1 E+07
2 E+04
10
Hg-193
Hg-194 260
y
1.9 E-08 5.1 E-08 0.001 4
<0.1
2 E+02
3 E+05
4 E+02
3
Au-194 [6] Hg-195 9.9
h
, 9.2 E-11 9.7 E-11 0.034 60
0.1
1 E+05
5 E+07
9 E+04
100
Au-195
Hg-195m 41.6
h
, 6.5 E-10 5.6 E-10 0.037 1000
1.3
2 E+04
8 E+06
1 E+04
3
Hg-195, Au-195 Hg-197 64.1
h
, 2.8 E-10 2.3 E-10 0.014 20
0.1
4 E+04
2 E+07
3 E+04
100
Hg-197m 23.8
h
, 6.6 E-10 4.7 E-10 0.017 3000
2.7
2 E+04
8 E+06
1 E+04
3
Hg-197
Hg-199m 42.6
m
5.2 E-11 3.1 E-11 0.032 2000
2.3
3 E+05
1 E+08
2 E+05
3
Hg-203 46.60
d
, 1.9 E-09 1.9 E-09 0.039 800
0.9
5 E+03
3 E+06
4 E+03
10
Radiological Protection 88
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Tl-194 33
m
, 8.9 E-12 8.1 E-12 0.125 90
0.1
1 E+06
6 E+08
9 E+05
30
Hg-194
Tl-194m 32.8
m
, , 3.6 E-11 4.0 E-11 0.368 700
1.3
3 E+05
1 E+08
2 E+05
3
Hg-194
Tl-195 1.16
h
, , 3.0 E-11 2.7 E-11 0.159 200
0.3
4 E+05
2 E+08
3 E+05
30
Hg-195
Tl-197 2.84
h
, , 2.7 E-11 2.3 E-11 0.065 300
0.3
4 E+05
2 E+08
3 E+05
30
Hg-197
Tl-198 5.3
h
, , 1.2 E-10 7.3 E-11 0.280 100
0.2
1 E+05
4 E+07
7 E+04
30
Tl-198m 1.87
h
, , 7.3 E-11 5.4 E-11 0.188 2000
1.5
2 E+05
7 E+07
1 E+05
3
Tl-198 [6] Tl-199 7.42
h
, , 3.7 E-11 2.6 E-11 0.042 600
0.5
4 E+05
1 E+08
2 E+05
10
Tl-200 26.1
h
, , 2.5 E-10 2.0 E-10 0.198 100
0.2
5 E+04
2 E+07
3 E+04
30
Tl-201 3.044
d
, 7.6 E-11 9.5 E-11 0.018 100
0.2
1 E+05
7 E+07
1 E+05
30
Tl-202 12.23
d
, , 3.1 E-10 4.5 E-10 0.077 60
0.1
2 E+04
2 E+07
3 E+04
100
Tl-204 3.779
y
, 6.2 E-10 1.3 E-09 <0.001 1000
1.4
8 E+03
8 E+06
1 E+04
3
Pb-204
Tl-209 2.20
m
, 0.296
1000
1.9
3
Pb-209
Pb-195m 15.8
m
, , 3.0 E-11 2.9 E-11 0.254 600
1.9
3 E+05
2 E+08
3 E+05
3
Tl-195 [6] Pb-198 2.4
h
, 8.7 E-11 1.0 E-10 0.073 600
0.6
1 E+05
6 E+07
1 E+05
10
Tl-198 [6] Pb-199 90
m
, , 4.8 E-11 5.4 E-11 0.218 200
0.3
2 E+05
1 E+08
2 E+05
30
Tl-199
Pb-200 21.5
h
, 2.6 E-10 4.0 E-10 0.037 1000
1.0
3 E+04
2 E+07
3 E+04
10
Tl-200 [6] Pb-201 9.4
h
, , 1.2 E-10 1.6 E-10 0.120 300
0.3
6 E+04
4 E+07
7 E+04
30
Tl-201
Pb-202 3
E5
y
1.4 E-08 8.7 E-09 0.001 4
<0.1
1 E+03
4 E+05
6 E+02
10
Tl-202
Pb-202m 3.62
h
, 1.2 E-10 1.3 E-10 0.310 900
1.0
8 E+04
4 E+07
7 E+04
10
Pb-202, Tl-202 Pb-203 52.05
h
, 1.6 E-10 2.4 E-10 0.054 500
0.4
4 E+04
3 E+07
5 E+04
10
Pb-205 1.43
E7
y
4.1 E-10 2.8 E-10 0.001 4
<0.1
4 E+04
1 E+07
2 E+04
300
Pb-209 3.253
h
3.2 E-11 5.7 E-11 <0.001 1000
1.4
2 E+05
2 E+08
3 E+05
3
Pb-210 22.3
y
, 1.1 E-06 6.8 E-07 0.003 3
<0.1
1 E+01
5 E+03
8 E+00
0.3
Bi-210
Pb-211 / Bi-211
36.1 m
, , 5.6 E-09 1.8 E-10 0.016 1000
1.7
6 E+04
9 E+05
1 E+03
3
Pb-212 10.64
h
, 3.3 E-08 5.9 E-09 0.025 2000
1.8
2 E+03
2 E+05
3 E+02
3
Bi-212 [6] Pb-214 26.8
m
, 4.8 E-09 1.4 E-10 0.041 2000
1.9
7 E+04
1 E+06
2 E+03
3
Bi-214 [6] Bi-200 36.4
m
, , 5.6 E-11 5.1 E-11 0.371 600
0.7
2 E+05
9 E+07
1 E+05
10
Pb-200
Bi-201 108
m
, 1.1 E-10 1.2 E-10 0.205 500
0.8
8 E+04
5 E+07
8 E+04
10
Pb-201 [6]
Ordinance
89
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Bi-202 1.67
h
, , 1.0 E-10 8.9 E-11 0.367 500
0.6
1 E+05
5 E+07
8 E+04
10
Pb-202
Bi-203 11.76
h
, , 4.5 E-10 4.8 E-10 0.310 200
0.4
2 E+04
1 E+07
2 E+04
10
Pb-203
Bi-205 15.31
d
, 1.0 E-09 9.0 E-10 0.239 100
0.2
1 E+04
5 E+06
8 E+03
30
Pb-205
Bi-206 6.243
d
, 2.1 E-09 1.9 E-09 0.487 600
1.0
5 E+03
2 E+06
4 E+03
10
Bi-207 38
y
, , 3.2 E-09 1.3 E-09 0.233 100
0.3
8 E+03
2 E+06
3 E+03
30
Bi-208 3.68
E5
y
, 4.0 E-09 1.4 E-09
7 E+03
1 E+06
2 E+03
10
Bi-210 5.012
d
6.0 E-08 1.3 E-09 <0.001 1000
1.6
8 E+03
8 E+04
1 E+02
3
Po-210
Bi-210m 3.0
E6
y
, 2.1 E-06 1.5 E-08 0.042 500
0.4
7 E+02
2 E+03
4 E+00
10
Tl-206
Bi-212 / Po-212,
Tl-208
60.55 m
, , 3.9 E-08 2.6 E-10 0.180 1000
1.7
4 E+04
1 E+05
2 E+02
3
Bi-213 / Po-213,
Tl-209
45.65 m
, , 4.1 E-08 2.0 E-10 0.027 1000
1.6
5 E+04
1 E+05
2 E+02
3
Bi-214 19.9
m
, 2.1 E-08 1.1 E-10 0.239 1000
1.7
9 E+04
2 E+05
4 E+02
3
Po-214 Pb-210 Po-203 36.7
m
, , 6.1 E-11 5.2 E-11 0.245 1000
1.0
2 E+05
8 E+07
1 E+05
10
Bi-203 [6] Po-205 1.80
h
, , 8.9 E-11 5.9 E-11 0.233 200
0.3
2 E+05
6 E+07
9 E+04
30
Bi-205 [6], Pb-201 Po-206 8.8
d
, , 3.7 E-07 1.3 E-07
8 E+01
1 E+04
2 E+01
1
Bi-206 [6] Po-207 350
m
, , 1.5 E-10 1.4 E-10 0.201 200
0.3
7 E+04
3 E+07
6 E+04
30
Bi-207 [6] Po-208 2.898
y
, , 2.4 E-06 7.7 E-07
1 E+01
2 E+03
3 E+00
0.3
Bi-208
Po-209 102
y
, , 2.4 E-06 7.7 E-07
1 E+01
2 E+03
3 E+00
0.3
Pb-205
Po-210 138.38
d
, 2.2 E-06 2.4 E-07 <0.001 <1
<0.1
4 E+01
2 E+03
4 E+00
1.0
At-207 1.80
h
, , 1.9 E-09 2.3 E-10 0.198 500
0.5
4 E+04
3 E+06
4 E+03
10
Po-207 [6], Bi-203 At-211 7.214
h
, , 1.1 E-07 1.1 E-08 0.008 3
<0.1
9 E+02
5 E+04
5 E+01
10
Po-211, Bi-207 [6] Rn-220 55.6
s
, <0.001
<1
<0.1
1
E+03
Po-216 Pb-212 Rn-222 3.8235
d
, <0.001
<1
<0.1
3
E+03
Po-218 Pb-214 Fr-222 14.4
m
2.1 E-08 7.1 E-10 0.001 1000
1.6
1 E+04
2 E+05
4 E+02
3
Ra-222 etc.
Fr-223 21.8
m
, 1.3 E-09 2.3 E-09 0.017 2000
1.8
4 E+03
4 E+06
6 E+03
3
Ra-223
Radiological Protection 90
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Ra-223 11.434
d
, 5.7 E-06 1.0 E-07 0.024 600
0.5
1 E+02 9 E+02
1 E+00
1
Rn-219 Po-215 Pb-211
Ra-224 3.66
d
, 2.4 E-06 6.5 E-08 0.002 30
<0.1
2 E+02
2 E+03
3 E+00
3
Rn-220 etc.
Ra-225 14.8
d
, 4.8 E-06 9.5 E-08 0.007 1000
0.9
1 E+02
1 E+03
2 E+00
3
Ac-225
Ra-226 1600
y
, 2.2 E-06 2.8 E-07 0.001 50
<0.1
4 E+01
2 E+03
4 E+00
1
Rn-222
Ra-226
incl. daughters
1600 y
, , 0.283
5000
5.2
4 E+01
2 E+03
4 E+00
1
Ra-227 42.2
m
, 2.1 E-10 8.4 E-11 0.038 2000
1.8
1 E+05
2 E+07
4 E+04
3
Ac-227
Ra-228 5.75
y
, 1.7 E-06 6.7 E-07 <0.001 <1
<0.1
1 E+01
3 E+03
5 E+00
0.3
Ac-228
Ac-224 2.9
h
, , 9.9 E-08 7.0 E-10 0.038 100
0.2
1 E+04 5 E+04
8 E+01
30
Ra-224, Fr-220 etc.
Ac-225 10.0
d
, 6.5 E-06 2.4 E-08 0.005 20
0.1
4 E+02
8 E+02
1 E+00
3
Fr-221 etc.
Ac-226 29
h
, , , 1.0 E-06 1.0 E-08 0.024 1000
1.3
1 E+03
5 E+03
8 E+00
3
Th-226, Ra-226, Fr-222
Ac-227 21.773
y
, , 6.3 E-04 1.1 E-06 <0.001 <1
<0.1
9 E+00
9 E+00 [5] 1 E-02
0.1
Th-227, Fr-223 Ac-228 6.13
h
, 2.9 E-08 4.3 E-10 0.145 2000
1.8
2 E+04
2 E+05
3 E+02
3
Th-228
Th-226 30.9
m
, 7.8 E-08 3.6 E-10 0.002 100
0.3
3 E+04
6 E+04
1 E+02
30
Ra-222 etc.
Th-227 18.718
d
, 7.6 E-06 8.9 E-09 0.023 200
0.2
1 E+03
1 E+03 [5] 1 E+00
10
Ra-223
Th-228 1.9131
y
, 3.2 E-05 7.0 E-08 0.002 3
<0.1
1 E+02
2 E+02
3 E-01
0.1
Ra-224
Th-229 7340
y
, 6.9 E-05 4.8 E-07 0.027 300
0.5
2 E+01
7 E+01
1 E-01
0.1
Ra-225
Th-230 7.7
E4
y
, 2.8 E-05 2.1 E-07 0.001 3
<0.1
5 E+01
2 E+02
3 E-01
0.1
Ra-226
Th-231 25.52
h
, 4.0 E-10 3.4 E-10 0.019 700
0.8
3 E+04
1 E+07
2 E+04
10
Pa-231
Th-232 1.4
E10
y
, 2.9 E-05 2.2 E-07 0.001 3
<0.1
5 E+01
2 E+02
3 E-01
0.1
Ra-228
Th-234 / Pa-234m 24.10 d , 5.8 E-09 3.4 E-09 0.008 1000
1.9
3 E+03
9 E+05
1 E+03
3
Pa-234
Th nat
incl.daughters
(1.4 E10 y)
, , 0.355
6000
5.4
6 E+00
2 E+01
4 E-02
0.1
Pa-227 38.3
m
, , 9.7 E-08 4.5 E-10 0.007 5
<0.1
2 E+04
5 E+04
9 E+01
100
Ac-223
Pa-228 22
h
, , , 5.1 E-08 7.8 E-10 0.168 400
0.9
1 E+04
1 E+05
2 E+02
10
Th-228, Ac-224
Ordinance
91
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Pa-230 17.4
d
, , , 5.7 E-07 9.2 E-10 0.108 200
0.3
1 E+04
1 E+04 [5] 1 E+01
30
Th-230, U-230, Ac-226
Pa-231 3.3
E4
y
, 8.9 E-05 7.1 E-07 0.020 40
0.1
1 E+01
6 E+01
9 E-02
0.3
Ac-227
Pa-232 1.31
d
, 6.8 E-09 7.2 E-10 0.151 1000
1.3
1 E+04
7 E+05
1 E+03
3
U-232
Pa-233 27.0
d
, 3.2 E-09 8.7 E-10 0.041 2000
1.4
1 E+04
2 E+06
3 E+03
3
U-233
Pa-234 6.70
h
, 5.8 E-10 5.1 E-10 0.281 2000
2.9
2 E+04
9 E+06
1 E+04
3
U-234
U-230 20.8
d
, 1.2 E-05 5.5 E-08 0.003 6
<0.1
2 E+02
4 E+02
7 E-01
1
Th-226
U-231 4.2
d
, , 4.0 E-10 2.8 E-10 0.032 10
0.1
4 E+04
1 E+07
2 E+04
100
Pa-231, Th-227 U-232 72
y
, 2.6 E-05 3.3 E-07 0.002 6
<0.1
3 E+01
2 E+02
3 E-01
0.3
Th-228
U-233 1.6
E5
y
, 6.9 E-06 5.0 E-08 0.001 2
<0.1
2 E+02
7 E+02
1 E+00
1
Th-229
U-234 2.4
E5
y
, 6.8 E-06 4.9 E-08 0.002 3
<0.1
2 E+02
7 E+02
1 E+00
1
Th-230
U-235 7.0
E8
y
, 6.1 E-06 4.6 E-08 0.028 100
0.2
2 E+02
8 E+02
1 E+00
3
Th-231
U-236 2.3
E7
y
, 6.3 E-06 4.6 E-08 0.002 1
<0.1
2 E+02
8 E+02
1 E+00
1
Th-232
U-237 6.75
d
, 1.7 E-09 7.7 E-10 0.037 1000
1.6
1 E+04
3 E+06
5 E+03
3
Np-237
U-238 4.5
E9
y
, , 5.7 E-06 4.4 E-08 0.002 1
<0.1
2 E+02
9 E+02
1 E+00
1
Th-234
U-239 23.54
m
, 3.5 E-11 2.8 E-11 0.012 1000
1.6
4 E+05
1 E+08
2 E+05
3
Np-239
U-240 14.1
h
, 8.4 E-10 1.1 E-09 0.009 1000
1.0
9 E+03
6 E+06
1 E+04
Np-240
U nat incl. daughters
, , 0.296
6000
7.1
4 E+02
4 E+02
3 E-01
1
Np-232 14.7
m
, , 3.5 E-11 9.7 E-12 0.199 400
0.6
1 E+06
1 E+08
2 E+05
10
U-232
Np-233 36.2
m
, 3.0 E-12 2.2 E-12 0.022 40
<0.1
5 E+06
2 E+09
3 E+06
100
U-233
Np-234 4.4
d
, , 7.3 E-10 8.1 E-10 0.219 80
0.2
1 E+04
7 E+06
1 E+04
30
U-234
Np-235 396.1
d
, , 2.7 E-10 5.3 E-11 0.008 3
<0.1
2 E+05
2 E+07
3 E+04
1000
U-235, Pa-231 Np-236L [2] 1.15
E5
y
, , 2.0 E-06 1.7 E-08 0.046 1000
1.8
6 E+02
3 E+03
4 E+00
3
U-236, Pu-236 Np-236S [2]
22.5 h
, , 3.6 E-09 1.9 E-10 0.013 600
0.6
5 E+04
1 E+06
2 E+03
10
U-236, Pu-236 Np-237 2.14
E6
y
, 1.5 E-05 1.1 E-07 0.018 30
0.1
9 E+01
3 E+02
6 E-01
0.3
Pa-233
Np-238 2.117
d
, 1.7 E-09 9.1 E-10 0.089 1000
1.1
1 E+04
3 E+06
5 E+03
3
Pu-238
Np-239 2.355
d
, 1.1 E-09 8.0 E-10 0.039 2000
2.3
1 E+04
5 E+06
8 E+03
3
Pu-239
Radiological Protection 92
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Np-240 65
m
, 1.3 E-10 8.2 E-11 0.225 3000
3.4
1 E+05
4 E+07
6 E+04
1
Pu-240
Np-240m 7.4
m
, 0.060
1000
1.6
3
Pu-240
Pu-234 8.8
h
, , 1.8 E-08 1.6 E-10 0.018 6
<0.1
6 E+04
3 E+05
5 E+02
300
Np-234, U-230 Pu-235 25.3
m
, , 2.6 E-12 2.1 E-12 0.026 8
<0.1
5 E+06
2 E+09
3 E+06
300
Np-235, U-231 Pu-236 2.851
y
, , 1.3 E-05 8.6 E-08 0.003 1
<0.1
1 E+02
4 E+02
6 E-01
1
U-232
Pu-237 45.3
d
, , 3.0 E-10 1.0 E-10 0.018 6
<0.1
1 E+05
2 E+07
3 E+04
300
Np-237, U-233 Pu-238 87.74
y
, , 3.0 E-05 2.3 E-07 0.002 <1
<0.1
4 E+01
2 E+02
3 E-01
0.3
U-234
Pu-239 2.4
E4
y
, 3.2 E-05 2.5 E-07 0.001 <1
<0.1
4 E+01
2 E+02
3 E-01
0.3
U-235
Pu-240 6537
y
, , 3.2 E-05 2.5 E-07 0.002 <1
<0.1
4 E+01
2 E+02
3 E-01
0.3
U-236
Pu-241 14.4
y
, , 5.8 E-07 4.7 E-09 <0.001 <1
<0.1
2 E+03
9 E+03
1 E+01
10
Am-241, U-237 Pu-242 3.76
E5
y
, , 3.1 E-05 2.4 E-07 0.002 <1
<0.1
4 E+01
2 E+02
3 E-01
0.3
U-238
Pu-243 4.956
h
, 1.1 E-10 8.5 E-11 0.007 1000
1.3
1 E+05
5 E+07
8 E+04
3
Am-243
Pu-244 [9]
8.26 E7 y
, , 3.0 E-05 2.4 E-07 0.053 1
0.1
4 E+01
2 E+02
3 E-01
0.3
U-240
Pu-245 10.5
h
, 6.5 E-10 7.2 E-10 0.070 2000
2.0
1 E+04
8 E+06
1 E+04
3
Am-245
Pu-246 10.85
d
, 7.0 E-09 3.3 E-09 0.034 700
0.7
3 E+03
7 E+05
1 E+03
10
Am-246
Am-237 73.0
m
, , 3.6 E-11 1.8 E-11 0.073 800
0.7
6 E+05
1 E+08
2 E+05
10
Pu-237, Np-233 Am-238 98
m
, , 6.6 E-11 3.2 E-11 0.145 60
0.1
3 E+05
8 E+07
1 E+05
30
Pu-238, Np-234 Am-239 11.9
h
, , 2.9 E-10 2.4 E-10 0.059 1000
1.4
4 E+04
2 E+07
3 E+04
3
Pu-239, Np-235 Am-240 50.8
h
, , 5.9 E-10 5.8 E-10 0.171 50
0.3
2 E+04
8 E+06
1 E+04
30
Pu-240, Np-236 Am-241 432.2
y
, 2.7 E-05 2.0 E-07 0.019 6
<0.1
5 E+01
2 E+02
3 E-01
0.3
Np-237
Am-242 16.02
h
, , 1.2 E-08 3.0 E-10 0.009 1000
1.1
3 E+04
4 E+05
7 E+02
3
Cm-242, Pu-242 Am-242m 152
y
, 2.4 E-05 1.9 E-07 0.006 2
<0.1
5 E+01
2 E+02
3 E-01
0.3
Am-242, Np-238 Am-243 7380
y
, 2.7 E-05 2.0 E-07 0.014 2
<0.1
5 E+01
2 E+02
3 E-01
0.3
Np-239
Am-244 10.1
h
, 1.5 E-09 4.6 E-10 0.145 3000
2.9
2 E+04
3 E+06
6 E+03
3
Cm-244
Am-244m 26
m
, 6.2 E-11 2.9 E-11 0.002 1000
1.6
3 E+05
8 E+07
1 E+05
3
Cm-244
Am-245 2.05
h
, 7.6 E-11 6.2 E-11 0.007 2000
1.8
2 E+05
7 E+07
1 E+05
3
Cm-245
Am-246 39
m
, 1.1 E-10 5.8 E-11 0.135 4000
4.5
2 E+05
5 E+07
8 E+04
1
Cm-246
Am-246m 25.0
m
, 3.8 E-11 3.4 E-11 0.154 1000
1.7
3 E+05
1 E+08
2 E+05
3
Cm-246
Ordinance
93
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Cm-238 2.4
h
, 4.8 E-09 8.0 E-11 0.021 7
<0.1
1 E+05
1 E+06
2 E+03
300
Am-238, Pu-234 Cm-240 27
d
, 2.3 E-06 7.6 E-09 0.003 <1
<0.1
1 E+03
2 E+03
4 E+00
10
Pu-236
Cm-241 32.8
d
, , 2.6 E-08 9.1 E-10 0.100 600
0.7
1 E+04
2 E+05
3 E+02
10
Am-241, Pu-237 Cm-242 162.8
d
, , 3.7 E-06 1.2 E-08 0.002 <1
<0.1
8 E+02
1 E+03
2 E+00
10
Pu-238
Cm-243 28.5
y
, , 2.0 E-05 1.5 E-07 0.033 1000
1.1
7 E+01
3 E+02
4 E-01
0.3
Pu-239, Am-243 Cm-244 18.11
y
, , 1.7 E-05 1.2 E-07 0.002 <1
<0.1
8 E+01
3 E+02
5 E-01
0.3
Pu-240
Cm-245 8500
y
, 2.7 E-05 2.1 E-07 0.028 400
0.4
5 E+01
2 E+02
3 E-01
0.3
Pu-241
Cm-246 [9]
4370 y
, , 2.7 E-05 2.1 E-07 0.013 <1
<0.1
5 E+01
2 E+02
3 E-01
0.3
Pu-242
Cm-247 1.56
E7
y
, 2.5 E-05 1.9 E-07 0.053 100
0.1
5 E+01
2 E+02
3 E-01
0.3
Pu-243
Cm-248 [9]
3.39 E5 y
, , 9.5 E-05 7.7 E-07 3.8 <1
<0.1
1 E+01
5 E+01
9 E-02
0.1
Pu-244
Cm-249 64.15
m
, 5.1 E-11 3.1 E-11 0.003 1000
1.5
3 E+05
1 E+08
2 E+05
3
Bk-249
Cm-250 [9] 6900
y
, , 5.4 E-04 4.4 E-06 36
<1
<0.1
2 E+00
9 E+00
2 E-02
0.03
Pu-246, Bk-250 Bk-245 4.94
d
, , 1.8 E-09 5.7 E-10 0.054 2000
1.6
2 E+04
3 E+06
5 E+03
3
Cm-245, Am-241 Bk-246 1.83
d
, 4.6 E-10 4.8 E-10 0.161 30
0.1
2 E+04
1 E+07
2 E+04
30
Cm-246
Bk-247 1380
y
, 4.5 E-05 3.5 E-07 0.021 800
0.7
3 E+01
1 E+02
2 E-01
0.3
Am-243
Bk-249 320
d
, , , 1.0 E-07 9.7 E-10 <0.001 20
<0.1
1 E+04
5 E+04
8 E+01
100
Cf-249, Am-245 Bk-250 3.222
h
, 7.1 E-10 1.4 E-10 0.137 1000
1.5
7 E+04
7 E+06
1 E+04
3
Cf-250
Cf-244 19.4
m
, 1.8 E-08 7.0 E-11 0.003 <1
<0.1
1 E+05
3 E+05
5 E+02
300
Cm-240
Cf-246 35.7
h
, , 3.5 E-07 3.3 E-09 0.002 <1
<0.1
3 E+03
1 E+04
2 E+01
30
Cm-242
Cf-248 [9]
333.5 d
, , 6.1 E-06 2.8 E-08 0.003 <1
<0.1
4 E+02
8 E+02
1 E+00
3
Cm-244
Cf-249 350.6
y
, , 4.5 E-05 3.5 E-07 0.060 200
0.2
3 E+01
1 E+02
2 E-01
0.3
Cm-245
Cf-250 [9]
13.08 y
, , 2.2 E-05 1.6 E-07 0.035 <1
<0.1
6 E+01
2 E+02
4 E-01
0.3
Cm-246
Cf-251 898
y
, 4.6 E-05 3.6 E-07 0.037 1000
1.8
3 E+01
1 E+02
2 E-01
0.3
Cm-247
Cf-252 [9] 2.638
y
, , 1.3 E-05 9.0 E-08 1.3 <1
<0.1
1 E+02
4 E+02
6 E-01
1
Cm-248
Cf-253 17.81
d
, , 1.0 E-06 1.4 E-09 <0.001 800
0.8
7 E+03
7 E+03 [5] 8 E+00
10
Es-253, Cm-249 Cf-254 [9]
60.5 d
, , 2.2 E-05 4.0 E-07 42
<1
<0.1
3 E+01
2 E+02
4 E-01
0.3
Cm-250
Es-250 2.1
h
, 4.2 E-10 2.1 E-11 0.071 20
0.1
5 E+05
1 E+07
2 E+04
100
Cf-250
Es-251 33
h
, , 1.7 E-09 1.7 E-10 0.028 200
0.2
6 E+04
3 E+06
5 E+03
30
Cf-251, Bk-247
Radiological Protection 94
814.501
Assessment
quantities Exemption limit
Licensing
limit
Guidance values
Nuclide Half-life
Type
of
decay/
radiation
einh
Sv/Bq
eing
Sv/Bq
h10
(mSv/h)/GBq
at 1 m
h0,07
(mSv/h)/GBq
at 10 cm
hc0,07
(mSv/h)/
(kBq/cm2)
LE
Bq/kg
or LEabs Bq
LA
Bq
CA
Bq/m3
CS
Bq/cm2
Unstable
daughter nuclide
1 2
4 5 6 7 8 9 10
11
12
13
Es-253 20.47
d
, , 2.1 E-06 6.1 E-09 0.001 1
<0.1
2 E+03
2 E+03
4 E+00
10
Bk-249
Es-254 275.7
d
, 6.0 E-06 2.8 E-08 0.021 6
<0.1
4 E+02
8 E+02
1 E+00
3
Bk-250
Es-254m 39.3
h
, , 3.7 E-07 4.2 E-09 0.077 1000
1.4
2 E+03
1 E+04
2 E+01
3
Fm-254, Bk-250 Fm-252 22.7
h
, 2.6 E-07 2.7 E-09 0.002 <1
<0.1
4 E+03
2 E+04
3 E+01
30
Cf-248
Fm-253 3.00
d
, , 3.0 E-07 9.1 E-10 0.023 200
0.2
1 E+04
2 E+04
3 E+01
30
Es-253, Cf-249 Fm-254 3.240
h
, 7.7 E-08 4.4 E-10 0.002 <1
<0.1
2 E+04
6 E+04
1 E+02
300
Cf-250
Fm-255 20.07
h
, 2.6 E-07 2.5 E-09 0.016 5
0.1
4 E+03
2 E+04
3 E+01
30
Cf-251
Fm-257 100.5
d
, 5.2 E-06 1.5 E-08 0.032 600
0.8
7 E+02
1 E+03
2 E+00
3
Cf-253
Md-257 5.2
h
, , 2.0 E-08 1.2 E-10 0.027 30
<0.1
8 E+04
3 E+05
4 E+02
100
Fm-257, Es-253 Md-258 55
d
, 4.4 E-06 1.3 E-08 0.007 2
<0.1
8 E+02
1 E+03
2 E+00
10
Es-254
Ordinance
95
814.501
Explanatory notes on the individual columns 1-3 General data on the radionuclide [source: International Commission on Radiological Protection, ICRP 38]. Daughter nuclides with a half-life of less than ten minutes are not listed separately. Their properties are included in the row for the parent nuclide. 1
Radionuclide; m, metastable. A daughter nuclide with a half-life of less than ten minutes is given after a slash. [2]: Two nuclides with the same number of protons and neutrons but with different configurations and half-lives.
2
Half-life: s, second(s); m, minute(s); h, hour(s); y, year(s); E, exponential expression.
3
Type of decay/radiation: alpha radiation; +, -, beta radiation; , gamma radiation;
electron capture; , spontaneous fission.
4, 5
Dose coefficients for inhalation (breathing in) and ingestion (eating or drinking) for adults [source: Council Directive 96/29/Euratom of 13 May 1996 (Table C1, Col. h(g)5µm for inhalation, Col. h(g) for ingestion).
For individual nuclides not listed therein: International Commission on Radiological Protection, Oak Ridge National Laboratory, database for ICRP 61, K. F. Eckerman, February 1993, or National Radiological Protection Board, UK, NRPB-R245, 1991]. 4
Assessment quantity for inhalation: the inhalation of 1 Bq yields, at most, the committed effective dose (in Sv) indicated.
5
Assessment quantity for ingestion: the ingestion of 1 Bq yields, at most, the committed effective dose (in Sv) indicated.
6-8
Assessment quantities for external radiation [source: Petoussi et al., GSF Report 7/93, National Research Center for Environment and Health, Neuherberg]. If the daughter nuclide has a half-life of less than 10 minutes, the sum of the values for parent and daughter is given. 6
Dose rate at a depth of 10 mm in tissue (ambient dose equivalent rate) at a distance of 1 m from a source of radiation with an activity of 1 GBq (109 Bq).
7
Dose rate at a depth of 0.07 mm in tissue (directional dose equivalent rate) at a distance of 10 cm from a source of radiation with an activity of 1 GBq (109 Bq).
8
Assessment quantity for skin contamination: contamination of 1 kBq/cm2 (averaged over 100 cm2) yields the dose rate (directional dose equivalent rate) indicated.
9-12 Exemption limit, licensing limit and guidance values 9 Exemption limit for specific activity in Bq/kg and exemption limit for absolute activity in Bq. The exemption limits are derived from Column 5. The ingestion of 1 kg of a substance with a specific activity of LE (i.e. an activity of LEabs) yields a committed effective dose of 10 µSv.
Radiological Protection 96
814.501
10
Licensing limit for daily handling. The values for the licensing limits are derived from Column 4 since inhalation is the main risk when radionuclides are handled in the laboratory. The inhalation of an activity LA on a single occasion yields a committed effective dose of 5 mSv. In some cases, the value derived for LA is lower than the value for LE, which is not consistent. In such cases, the LA value has been replaced by the LE value [5].
For inert gases, the licensing limit corresponds to the activity in an enclosed space of 1000 m3 and a concentration CA specified in Column 11.
11
Guidance value for chronic occupational exposure to airborne activity.
Exposure to an airborne activity concentration CA for 40 hours per week and 50 weeks per year yields a committed effective dose of 20 mSv.
For inhalation: CA [Bq/m3] = 0.02 Sv / (einh . 2400 m3/year).
For inert gases, immersion in a semi-infinite hemispherical cloud for 40 hours per week and 50 weeks per year yields an effective dose of 20 mSv (gases and inert gases: D. C. Kocher, Oak Ridge National Laboratory, TN Jnl. 1981, NUREG/CR-1918).
In most cases, the CA value relates to the parent nuclide. The exceptional cases where the CA value is given for the daughter nuclide are indicated as such. Also indicated by a footnote are those cases where immersion leads to irradiation of the skin or all organs and where the dose resulting from immersion is greater than that from inhalation. [1]: In the case of Kr-88, values are given for the daughter nuclide for immersion. [3]: Derived from the effective dose for immersion. [4]: Derived from the skin dose for immersion.
12
Guidance value for surface contamination outside controlled areas, averaged over 100 cm2. To derive each value, irradiation of the skin, intake and the licensing limit (relation to inhalation) were considered and the most unfavourable case was selected: Irradiation of the skin for 8760 hours per year, exhaustion of one tenth of the limit for the skin, corresponding to an effective dose of 0.5 mSv per year.
Daily ingestion of the activity that may be present on an area of 10 cm2 (parts of the hand), corresponding to an effective dose of 0.5 mSv per year.
- CSinh = LA / 100 cm2= (5 mSv / [1000 . mSv/Sv einh]) / 100 cm2 13
Unstable daughter nuclide 13
Unstable daughter nuclide; means "decays into …"; in the case of branching, the different nuclides formed are separated by commas; a second arrow indicates a decay series. [6]: The h10 value of the daughter nuclide exceeds
0.1 (mSv/h)/GBq at a distance of 1 m (attention may need to be paid to the daughter nuclide!).
Ordinance
97
814.501
List of footnotes: [l] In the case of Kr-88, values are given for the daughter nuclide for immersion (Column 11).
[2]
Two nuclides with the same number of protons and neutrons but with different configurations and half-lives (Column 1).
[3]
Derived from the effective dose with immersion (Column 11).
[4]
Derived from the skin dose with immersion (Column 11).
[5]
The LA value has been replaced by the LE value (Column 10).
[6] The
h10 value of the daughter nuclide exceeds 0.1 (mSv/h)/GBq at a distance of 1 m (attention may need to be paid to the daughter nuclide!) (Column 13).
[7]
The H-3, HTO fraction is also to be considered.
[8]
For Kr-85, LA was selected so that the dose rate at a distance of 10 cm is 1 Sv/h.
[9]
Spontaneous fission is included in h10. The spontaneous fission rate is taken from Table of Isotopes (8th edition, 1996, John Wiley & Sons) and from the ENDF database, Brookhaven National Laboratory. For the average number of neutrons per fission and the dose coefficient, the values for Cf-252 were used. Photons produced during nuclear fission and photons emitted by the resultant fission products are not considered.
Nuclide mixtures
In the case of nuclide mixtures, the summation rule specified in Annex 1 is applicable for Columns 9, 11 and 12.
Radiological Protection 98
814.501
Annex 4167
(Art. 44 Para. 3)
Dose coefficients for members of the public 1. Inhalation
Nuclide
Infant (1 y)
Child (10 y)
Adult
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
H-3, HTO [1]
4.8 E-11
4.8 E-11
WB
2.3 E-11
2.3 E-11
WB
1.8 E-11
1.8 E-11
WB
H-3, OBT [2]
1.1 E-10
1.1 E-10
WB
5.5 E-11
5.5 E-11
WB
4.1 E-11
4.1 E-11
WB
C-14 organic
1.6 E-09
1.6 E-09
WB
7.9 E-10
7.9 E-10
WB
5.8 E-10
5.8 E-10
WB
Na-22
7.3 E-09
6.4 E-08
ET
2.4 E-09
2.0 E-08
ET
1.3 E-09
9.2 E-09
ET
Na-24
1.8 E-09
4.3 E-08
ET
5.7 E-10
1.3 E-08
ET
2.7 E-10
6.0 E-09
ET
Sc-47
2.8 E-09
1.4 E-08
Lu
1.1 E-09
6.7 E-09
Lu
7.3 E-10
5.1 E-09
Lu
Cr-51
1.9 E-10
8.2 E-10
ET
6.4 E-11
2.6 E-10
ET
3.2 E-11
1.4 E-10
Lu
Mn-54
6.2 E-09
2.5 E-08
ET
2.4 E-09
9.1 E-09
Lu
1.5 E-09
6.3 E-09
Lu
Fe-59
1.3 E-08
6.7 E-08
Lu
5.5 E-09
3.1 E-08
Lu
3.7 E-09
2.3 E-08
Lu
Co-57
2.2 E-09
1.2 E-08
Lu
8.5 E-10
4.8 E-09
Lu
5.5 E-10
3.3 E-09
Lu
Co-58
6.5 E-09
3.0 E-08
ET
2.4 E-09
1.2 E-08
Lu
1.6 E-09
8.9 E-09
Lu
Co-60
3.4 E-08
1.6 E-07
Lu
1.5 E-08
7.3 E-08
Lu
1.0 E-08
5.2 E-08
Lu
Zn-65
6.5 E-09
1.9 E-08
ET
2.4 E-09
7.5 E-09
Lu
1.6 E-09
5.1 E-09
Lu
Se-75
6.0 E-09
2.4 E-08
Ki
2.5 E-09
9.2 E-09
Ki
1.0 E-09
5.4 E-09
Ki
Br-82
3.0 E-09
5.0 E-08
ET
1.1 E-09
1.5 E-08
ET
6.3 E-10
7.0 E-09
ET
Sr-89
2.4 E-08
1.5 E-07
Lu
9.1 E-09
6.3 E-08
Lu
6.1 E-09
4.5 E-08
Lu
Sr-90
1.1 E-07
7.0 E-07
Lu
5.1 E-08
2.9 E-07
Lu
3.6 E-08
2.1 E-07
Lu
Y-91
3.0 E-08
1.7 E-07
Lu
1.1 E-08
6.9 E-08
Lu
7.1 E-09
5.0 E-08
Lu
Zr-95
1.6 E-08
9.1 E-08
Lu
6.8 E-09
4.2 E-08
Lu
4.8 E-09
3.1 E-08
Lu
Nb-95
5.2 E-09
2.8 E-08
Lu
2.2 E-09
1.3 E-08
Lu
1.5 E-09
9.5 E-09
Lu
167 Amended by No III of the Ordinance of 15 Nov. 2000 (AS 2000 2894). Corrected in accordance with No III Para. 1 of the Ordinance of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
Ordinance
99
814.501
Nuclide
Infant (1 y)
Child (10 y)
Adult
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
Mo-99
4.4 E-09
1.8 E-08
Co
1.5 E-09
7.2 E-09
Lu
8.9 E-10
5.3 E-09
Lu
Tc-99m
9.9 E-11
1.4 E-09
ET
3.4 E-11
4.3 E-10
ET
1.9 E-11
2.1 E-10
ET
Ru-103
8.4 E-09
5.3 E-08
Lu
3.5 E-09
2.4 E-08
Lu
2.4 E-09
1.8 E-08
Lu
Ru-106
1.1 E-07
7.1 E-07
Lu
4.1 E-08
2.8 E-07
Lu
2.8 E-08
2.0 E-07
Lu
Ag-110m
2.8 E-08
1.1 E-07
Lu
1.2 E-08
5.1 E-08
Lu
7.6 E-09
3.6 E-08
Lu
Sn-125
1.5 E-08
6.5 E-08
Lu
5.0 E-09
2.7 E-08
Lu
3.1 E-09
2.0 E-08
Lu
Sb-122
5.7 E-09
2.7 E-08
Co
1.8 E-09
7.5 E-09
Lu
1.0 E-09
5.5 E-09
Lu
Sb-124
2.4 E-08
1.4 E-07
Lu
9.6 E-09
6.1 E-08
Lu
6.4 E-09
4.4 E-08
Lu
Sb-125
1.6 E-08
1.0 E-07
Lu
6.8 E-09
4.5 E-08
Lu
4.8 E-09
3.2 E-08
Lu
Sb-127
7.3 E-09
3.1 E-08
Lu
2.7 E-09
1.4 E-08
Lu
1.7 E-09
1.1 E-08
Lu
Te-125m
1.1 E-08
7.4 E-08
Lu
4.8 E-09
3.5 E-08
Lu
3.4 E-09
2.6 E-08
Lu
Te-127m
2.6 E-08
1.7 E-07
Lu
1.1 E-08
7.7 E-08
Lu
7.4 E-09
5.6 E-08
Lu
Te-129m
2.6 E-08
1.5 E-07
Lu
9.8 E-09
6.6 E-08
Lu
6.6 E-09
4.8 E-08
Lu
Te-131m
5.8 E-09
3.2 E-08
ET
1.9 E-09
9.8 E-09
ET
9.4 E-10
4.6 E-09
Lu
Te-132
1.3 E-08
5.6 E-08
ET
4.0 E-09
1.7 E-08
ET
2.0 E-09
1.0 E-08
Lu
I-125
2.3 E-08
4.5 E-07
Th
1.1 E-08
2.2 E-07
Th
5.1 E-09
1.0 E-07
Th
I-125 organic
4.0 E-08
8.1 E-07
Th
2.2 E-08
4.4 E-07
Th
1.1 E-08
2.1 E-07
Th
I-125 elementary
5.2 E-08
1.0 E-06
Th
2.8 E-08
5.6 E-07
Th
1.4 E-08
2.7 E-07
Th
I-129
8.6 E-08
1.7 E-06
Th
6.7 E-08
1.3 E-06
Th
3.6 E-08
7.1 E-07
Th
I-129 organic
1.5 E-07
3.0 E-06
Th
1.3 E-07
2.7 E-06
Th
7.4 E-08
1.5 E-06
Th
I-129 elementary
2.0 E-07
3.9 E-06
Th
1.7 E-07
3.4 E-06
Th
9.6 E-08
1.9 E-06
Th
I-131
7.2 E-08
1.4 E-06
Th
1.9 E-08
3.7 E-07
Th
7.4 E-09
1.5 E-07
Th
I-131 organic
1.3 E-07
2.5 E-06
Th
3.7 E-08
7.4 E-07
Th
1.5 E-08
3.1 E-07
Th
I-131 elementary
1.6 E-07
3.2 E-06
Th
4.8 E-08
9.5 E-07
Th
2.0 E-08
3.9 E-07
Th
I-133
1.8 E-08
3.5 E-07
Th
3.8 E-09
7.4 E-08
Th
1.5 E-09
2.8 E-08
Th
I-133 organic
3.2 E-08
6.3 E-07
Th
7.6 E-09
1.5 E-07
Th
3.1 E-09
6.0 E-08
Th
I-133 elementary
4.1 E-08
8.0 E-07
Th
9.7 E-09
1.9 E-07
Th
4.0 E-09
7.6 E-08
Th
I-135
3.7 E-09
7.0 E-08
Th
7.9 E-10
1.5 E-08
Th
3.2 E-10
5.7 E-09
Th
I-135 organic
6.7 E-09
1.3 E-07
Th
1.6 E-09
3.1 E-08
Th
6.8 E-10
1.3 E-08
Th
I-135 elementary
8.5 E-09
1.6 E-07
Th
2.1 E-09
3.8 E-08
Th
9.2 E-10
1.5 E-08
Th
Cs-134
7.3 E-09
4.9 E-08
ET
5.3 E-09
1.8 E-08
ET
6.6 E-09
1.2 E-08
ET
Cs-136
5.2 E-09
5.9 E-08
ET
2.0 E-09
1.9 E-08
ET
1.2 E-09
8.8 E-09
ET
Cs-137
5.4 E-09
2.5 E-08
ET
3.7 E-09
9.7 E-09
ET
4.6 E-09
7.4 E-09
ET
Radiological Protection 100
814.501
Nuclide
Infant (1 y)
Child (10 y)
Adult
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
Ba-140
2.0 E-08
1.1 E-07
Lu
7.6 E-09
4.8 E-08
Lu
5.1 E-09
3.5 E-08
Lu
La-140
6.3 E-09
4.4 E-08
ET
2.0 E-09
1.3 E-08
ET
1.1 E-09
6.2 E-09
ET
Ce-141
1.1 E-08
6.9 E-08
Lu
4.6 E-09
3.2 E-08
Lu
3.2 E-09
2.4 E-08
Lu
Ce-144
1.6 E-07
6.5 E-07
Lu
5.5 E-08
2.6 E-07
Lu
3.6 E-08
1.9 E-07
Lu
Pr-143
8.4 E-09
4.6 E-08
Lu
3.2 E-09
2.1 E-08
Lu
2.2 E-09
1.5 E-08
Lu
Pb-210
3.7 E-06
2.2 E-05
Lu
1.5 E-06
1.1 E-05
BS
1.1 E-06
1.3 E-05
BS
Bi-210
3.0 E-07
2.4 E-06
Lu
1.3 E-07
1.1 E-06
Lu
9.3 E-08
7.7 E-07
Lu
Po-210
1.1 E-05
8.1 E-05
Lu
4.6 E-06
3.5 E-05
Lu
3.3 E-06
2.6 E-05
Lu
Ra-224
8.2 E-06
6.7 E-05
Lu
3.9 E-06
3.2 E-05
Lu
3.0 E-06
2.5 E-05
Lu
Ra-226
1.1 E-05
9.1 E-05
Lu
4.9 E-06
3.8 E-05
Lu
3.5 E-06
2.8 E-05
Lu
Th-227
3.0 E-05
2.5 E-04
Lu
1.4 E-05
1.2 E-04
Lu
1.0 E-05
8.7 E-05
Lu
Th-228
1.3 E-04
1.1 E-03
Lu
5.5 E-05
4.5 E-04
Lu
4.0 E-05
3.3 E-04
Lu
Th-230
3.5 E-05
2.6 E-04
BS
1.6 E-05
2.4 E-04
BS
1.4 E-05
2.8 E-04
BS
Th-232
5.0 E-05
3.5 E-04
Lu
2.6 E-05
2.6 E-04
BS
2.5 E-05
2.9 E-04
BS
Pa-231
2.3 E-04
1.0 E-02
BS
1.5 E-04
7.5 E-03
BS
1.4 E-04
6.8 E-03
BS
U-234
1.1 E-05
9.0 E-05
Lu
4.8 E-06
3.8 E-05
Lu
3.5 E-06
2.7 E-05
Lu
U-235
1.0 E-05
8.1 E-05
Lu
4.3 E-06
3.4 E-05
Lu
3.1 E-06
2.4 E-05
Lu
U-238
9.4 E-06
7.5 E-05
Lu
4.0 E-06
3.1 E-05
Lu
2.9 E-06
2.2 E-05
Lu
Np-237
4.0 E-05
8.3 E-04
BS
2.2 E-05
6.7 E-04
BS
2.3 E-05
1.0 E-03
BS
Np-239
4.2 E-09
1.8 E-08
ET
1.4 E-09
8.4 E-09
Lu
9.3 E-10
6.3 E-09
Lu
Pu-238
7.4 E-05
1.2 E-03
BS
4.8 E-05
9.8 E-04
BS
4.6 E-05
1.4 E-03
BS
Pu-239
7.7 E-05
1.3 E-03
BS
4.4 E-05
1.1 E-03
BS
5.0 E-05
1.5 E-03
BS
Pu-240
7.7 E-05
1.3 E-03
BS
4.8 E-05
1.1 E-03
BS
5.0 E-05
1.5 E-03
BS
Pu-241
9.7 E-07
2.2 E-05
BS
8.3 E-07
2.4 E-05
BS
9.0 E-07
3.1 E-05
BS
Am-241
6.9 E-05
1.4 E-03
BS
4.0 E-05
1.2 E-03
BS
4.2 E-05
1.7 E-03
BS
Cm-242
1.8 E-05
1.2 E-04
BS
7.3 E-06
4.8 E-05
Lu
5.2 E-06
3.5 E-05
Lu
Cm-244
5.7 E-05
9.6 E-04
BS
2.7 E-05
6.4 E-04
BS
2.7 E-05
9.2 E-04
BS
einh:
Committed effective dose; integration period: 50 years for adults, 70 years for children Dose coefficients taken from the ICRP CD-ROM (AMAD = 1 m)
Ordinance
101
814.501
Nuclide
Infant (1 y)
Child (10 y)
Adult
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
einh
Sv/Bq
hinh, organ
Sv/Bq
Organ
hinh, organ: Committed dose in the most affected organ [WB: whole body, Go: gonads, BM: bone marrow (red), Co: colon, Lu: lung, St: stomach, Bl: bladder, Br: breast, Li: liver, Oe: oesophagus, Th: thyroid, Sk: skin, BS: bone surface, remainder (ET: extrathoracic airways, Ut: uterus, Ki: kidney, Sp: spleen)]
Dose coefficients taken from the ICRP CD-ROM (AMAD = 1 m)
[1]
Tritiated water vapour [2] Organically bound tritium 2. Ingestion
Nuclide
Infant (1 y)
Child (10 y)
Adult
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
H-3, HTO
4.8E-11
4.8E-11
WB
2.3E-11
2.3E-11
WB
1.8E-11
1.8E-11
WB
H-3, OBT [2]
1.2E-10
1.6E-10
St
5.7E-11
6.7E-11
St
4.2E-11
4.7E-11
St
C-14 1.6E-09
1.9E-09
St
8.0E-10
8.9E-10
St
5.8E-10
6.3E-10
St
Na-22 1.5E-08
2.8E-08
BS
5.5E-09
1.1E-08
BS
3.2E-09
6.3E-09
BS
Na-24 2.3E-09
6.7E-09
St
7.7E-10
2.1E-09
St
4.3E-10
1.2E-09
St
Sc-47 3.9E-09
3.0E-08
Co
1.2E-09
9.0E-09
Co
5.4E-10
4.1E-09
Co
Cr-51 2.3E-10
1.4E-09
Co
7.8E-11
4.5E-10
Co
3.8E-11
2.1E-10
Co
Mn-54 3.1E-09
8.3E-09
Co
1.3E-09
3.3E-09
Co
7.1E-10
1.8E-09
Co
Fe-59 1.3E-08
3.5E-08
Co
4.7E-09
1.2E-08
Co
1.8E-09
5.8E-09
Co
Co-57 1.6E-09
5.6E-09
Co
5.8E-10
1.8E-09
Co
2.1E-10
9.4E-10
Co
Co-58 4.4E-09
1.4E-08
Co
1.7E-09
4.9E-09
Co
7.4E-10
2.8E-09
Co
Co-60 2.7E-08
5.1E-08
Co
1.1E-08
2.0E-08
Li
3.4E-09
8.7E-09
Co
Zn-65 1.6E-08
2.2E-08
BS
6.4E-09
8.9E-09
BS
3.9E-09
5.4E-09
BS
Se-75 1.3E-08
5.1E-08
Ki
6.0E-09
2.2E-08
Ki
2.6E-09
1.4E-08
Ki
Br-82 2.6E-09
4.0E-09
Co
9.5E-10
1.5E-09
Co
5.4E-10
8.3E-10
St
Sr-89 1.8E-08
9.2E-08
Co
5.8E-09
2.7E-08
Co
2.6E-09
1.4E-08
Co
Radiological Protection 102
814.501
Nuclide
Infant (1 y)
Child (10 y)
Adult
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
Sr-90 7.3E-08
7.3E-07
BS
6.0E-08
1.0E-06
BS
2.8E-08
4.1E-07
BS
Y-91 1.8E-08
1.4E-07
Co
5.2E-09
4.2E-08
Co
2.4E-09
1.9E-08
Co
Zr-95 5.6E-09
3.4E-08
Co
1.9E-09
1.1E-08
Co
9.5E-10
5.1E-09
Co
Nb-95 3.2E-09
1.6E-08
Co
1.1E-09
5.6E-09
Co
5.8E-10
2.8E-09
Co
Mo-99 3.5E-09
1.6E-08
Li
1.1E-09
5.5E-09
Li/Ki
6.0E-10
3.1E-09
Ki
Tc-99m 1.3E-10
4.7E-10
Th
4.3E-11
1.4E-10
Co
2.2E-11
6.7E-11
Co
Ru-103 4.6E-09
2.9E-08
Co
1.5E-09
9.2E-09
Co
7.3E-10
4.3E-09
Co
Ru-106 4.9E-08
3.3E-07
Co
1.5E-08
1.0E-07
Co
7.0E-09
4.5E-08
Co
Ag-110m 1.4E-08
4.6E-08
Co 5.2E-09
1.7E-08
Co
2.8E-09
8.5E-09
Co
Sn-125 2.2E-08
1.8E-07
Co
6.7E-09
5.2E-08
Co
3.1E-09
2.4E-08
Co
Sb-122 1.2E-08
9.1E-08
Co
3.7E-09
2.7E-08
Co
1.7E-09
1.2E-08
Co
Sb-124 1.6E-08
9.6E-08
Co
5.2E-09
3.0E-08
Co
2.5E-09
1.4E-08
Co
Sb-125 6.1E-09
3.3E-08
BS
2.1E-09
1.3E-08
BS
1.1E-09
9.0E-09
BS
Sb-127 1.2E-08
8.4E-08
Co
3.6E-09
2.5E-08
Co
1.7E-09
1.2E-08
Co
Te-125m 6.3E-09
9.0E-08
BS 1.9E-09
3.4E-08
BS
8.7E-10
2.0E-08
BS
Te-127m 1.8E-08
1.4E-07
BS 5.2E-09
5.5E-08
BS
2.3E-09
3.2E-08
BS
Te-129m 2.4E-08
1.1E-07
Co 6.6E-09
3.2E-08
Co
3.0E-09
1.4E-08
Co
Te-131m 1.4E-08
1.5E-07
Th 4.3E-09
4.5E-08
Th
1.9E-09
1.8E-08
Th
Te-132 3.0E-08
3.2E-07
Th
8.3E-09
7.5E-08
Th
3.8E-09
3.1E-08
Th
I-125 5.7E-08
1.1E-06
Th
3.1E-08
6.2E-07
Th
1.5E-08
3.0E-07
Th
I-129 2.2E-07
4.3E-06
Th
1.9E-07
3.8E-06
Th
1.1E-07
2.1E-06
Th
I-131 1.8E-07
3.6E-06
Th
5.2E-08
1.0E-06
Th
2.2E-08
4.3E-07
Th
I-133 4.4E-08
8.6E-07
Th
1.0E-08
2.0E-07
Th
4.3E-09
8.2E-08
Th
I-135 8.9E-09
1.7E-07
Th
2.2E-09
3.9E-08
Th
9.3E-10
1.6E-08
Th
Cs-134 1.6E-08
2.4E-08
Co
1.4E-08
1.7E-08
Co
1.9E-08
2.1E-08
Co
Cs-136 9.5E-09
1.3E-08
Co
4.4E-09
5.3E-09
Co
3.0E-09
3.4E-09
Co
Cs-137 1.2E-08
2.3E-08
Co
1.0E-08
1.3E-08
Co
1.3E-08
1.5E-08
Co
Ba-140 1.8E-08
1.2E-07
Co
5.8E-09
3.5E-08
Co
2.6E-09
1.7E-08
Co
La-140 1.3E-08
8.7E-08
Co
4.2E-09
2.7E-08
Co
2.0E-09
1.3E-08
Co
Ce-141 5.1E-09
4.0E-08
Co
1.5E-09
1.2E-08
Co
7.1E-10
5.5E-09
Co
Ce-144 3.9E-08
3.1E-07
Co
1.1E-08
9.2E-08
Co
5.2E-09
4.2E-08
Co
Pr-143 8.7E-09
7.0E-08
Co
2.6E-09
2.1E-08
Co
1.2E-09
9.3E-09
Co
Pb-210 3.6E-06
3.8E-05
BS
1.9E-06
4.4E-05
BS
6.9E-07
2.3E-05
BS
Ordinance
103
814.501
Nuclide
Infant (1 y)
Child (10 y)
Adult
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
eing
Sv/Bq
hing, organ
Sv/Bq
Organ
Bi-210 9.7E-09
7.6E-08
Co
2.9E-09
2.3E-08
Co
1.3E-09
1.0E-08
Co
Po-210 8.8E-06
7.6E-05
Sp 2.6E-06
2.5E-05
Sp
1.2E-06 1.3E-05 Ki
Ra-224 6.6E-07
2.3E-05
BS
2.6E-07
1.1E-05
BS
6.5E-08
1.7E-06
BS
Ra-226 9.6E-07
2.9E-05
BS
8.0E-07
3.9E-05
BS
2.8E-07
1.2E-05
BS
Th-227 7.0E-08
8.0E-07
BS
2.3E-08
3.9E-07
BS
8.8E-09
8.8E-08
BS
Th-228 3.7E-07
8.4E-06
BS
1.4E-07
4.3E-06
BS
7.2E-08
2.5E-06
BS
Th-230 4.1E-07
1.3E-05
BS
2.4E-07
1.1E-05
BS
2.1E-07
1.2E-05
BS
Th-232 4.5E-07
1.3E-05
BS
2.9E-07
1.2E-05
BS
2.3E-07
1.2E-05
BS
Pa-231 1.3E-06
6.0E-05
BS
9.2E-07
4.6E-05
BS
7.1E-07
3.6E-05
BS
U-234 1.3E-07
1.8E-06
BS
7.4E-08
1.5E-06
BS
4.9E-08
7.8E-07
BS
U-235 1.3E-07
1.7E-06
BS
7.1E-08
1.4E-06
BS
4.7E-08
7.4E-07
BS
U-238 1.2E-07
1.6E-06
BS
6.8E-08
1.4E-06
BS
4.5E-08
7.1E-07
BS
Np-237 2.1E-07
5.0E-06
BS
1.1E-07
4.1E-06
BS
1.1E-07
5.4E-06
BS
Np-239 5.7E-09
4.4E-08
Co
1.7E-09
1.3E-08
Co
8.0E-10
6.0E-09
Co
Pu-238 4.0E-07
6.9E-06
BS
2.4E-07
5.9E-06
BS
2.3E-07
7.4E-06
BS
Pu-239 4.2E-07
7.6E-06
BS
2.7E-07
6.8E-06
BS
2.5E-07
8.2E-06
BS
Pu-240 4.2E-07
7.6E-06
BS
2.7E-07
6.8E-06
BS
2.5E-07
8.2E-06
BS
Pu-241 5.7E-09
1.2E-07
BS
5.1E-09
1.4E-07
BS
4.8E-09
1.6E-07
BS
Am-241 3.7E-07
8.3E-06
BS
2.2E-07
7.3E-06
BS
2.0E-07
9.0E-06
BS
Cm-242 7.6E-08
9.7E-07
BS
2.4E-08
3.5E-07
BS
1.2E-08
1.9E-07
BS
Cm-244 2.9E-07
5.8E-06
BS
1.4E-07
3.9E-06
BS
1.2E-07
4.9E-06
BS
eing:
Committed effective dose; integration period: 50 years for adults, 70 years for children Dose coefficients taken from the ICRP CD-ROM (AMAD = 1 m)
hing, organ: Committed dose in the most affected organ [WB: whole body, Go: gonads, BM: bone marrow (red), Co: colon, Lu: lung, St: stomach, Bl: bladder, Br: breast, Li: liver, Oe: oesophagus, Th: thyroid, Sk: skin, BS: bone surface, remainder (ET: extrathoracic airways, Ut: uterus, Ki: kidney, Sp: spleen)]
Dose coefficients taken from the ICRP CD-ROM (AMAD = 1 m)
[2] Organically bound tritium
Radiological Protection 104
814.501
Annex 5168
(Art. 1 para.. 2, 42 and 44) Method for determination of the radiation dose 1. Principle
The effective dose and organ doses are generally determined with the aid of operational quantities.
2. Operational quantities The operational quantities used for individual monitoring for external exposure are a. the personal deep dose Hp(10), with the short form Hp; b. the personal surface dose Hp(0.07), with the short form Hs.
The operational quantities used for area monitoring are a. the ambient dose equivalent H*(10); b. the directional dose equivalent H′(0.07).
The operational quantity for internal exposure is the committed effective dose E50, calculated using standard models and the dose coefficients specified in Annexes 3 and 4.
3. Personal doses below the relevant dose limits The organ dose equivalent for external radiation is taken to be equal to the personal
deep dose equivalent Hp(10), or the ambient dose equivalent H*(10), for all tissues and organs with the exception of the skin.
The skin dose equivalent for external radiation is taken to be equal to the personal surface dose equivalent Hp(0.07), or the directional dose equivalent H′(0.07).
The effective dose is taken to be equal to the sum of a. the personal dose equivalent Hp(10), or the ambient dose equivalent H*(10), and
b. the committed effective dose E50.
4. Personal doses above the relevant dose limits If the dose levels determined in accordance with point 3 are above the relevant
limits, then the effective dose or organ doses for the person concerned are to be individually determined by an expert, in cooperation with the supervisory authority, 168 Amended by No II of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
Ordinance
105
814.501
using calculation methods and dose coefficients in accordance with the current state of science and technology. The value thus determined is decisive in establishing whether or not a dose limit has been exceeded.
5. Area monitoring Where ambient dose limits are specified by this Ordinance, the ambient dose is
taken to be
a. the quantity H*(10) (ambient dose equivalent) for strongly penetrating radiation;
b. the quantity H′(0.07) (directional dose equivalent) for weakly penetrating radiation.
Radiological Protection 106
814.501
Annex 6169
(Art. 30 and 58)
Controlled area markings Depending on the radiation sources used, signs are to be displayed in controlled areas indicating the following: 1. Unsealed radioactive sources: a. the most radiotoxic nuclide and its maximum activity; b. the classification of the working area (type A, B or C); c. the maximum degree of contamination caused by loose contamination on surfaces, expressed in Bq/cm2 or as the number of guidance values for the nuclide concerned; d. the ambient dose rate in mSv per hour in the accessible area, if appropriate; e. details of the protective clothing and protective measures required; f.
the hazard warning symbol.
2. Sealed radioactive sources: a. the most radiotoxic nuclide and its maximum activity, or the activity of and nuclide with the highest-energy gamma radiation; b. the ambient dose rate in mSv per hour in the accessible area, if appropriate; c. the hazard warning symbol.
3. Equipment (e.g. X-ray equipment, accelerators): a. the designation of the equipment; b. the type of radiation (e.g. electrons, X-rays, neutrons, where not apparent from the equipment designation); c. the ambient dose rate in mSv per hour in the accessible area, if appropriate; d. the hazard warning symbol.
Hazard warning symbol: Ratio of radii: 1:1.5:5 169 Amended by No II of the Ordinance of 17 Nov. 1999, in force since 1 Jan. 2000 (AS 2000 107).
Ordinance
107
814.501
Annex 7*
(Art. 44 Para. 3)
Dose coefficients for cloud and ground radiation Nuclide
External exposure to cloud radiation
External exposure to ground radiation
eimm
(mSv/h)/(Bq/m3)
esol
(mSv/h)/(Bq/m2)
H-3 0.0E+00
0.0E+00
C-11 1.4E-07
3.0E-09
C-14 6.7E-12
0.0E+00
O-15 1.4E-07
3.2E-09
F-18 1.4E-07
2.8E-09
Na-22 3.1E-07
5.8E-09
Na-24 6.7E-07
1.0E-08
Sc-47 1.5E-08
3.3E-10
Cr-51 4.3E-09
9.2E-11
Mn-54 1.2E-07
2.4E-09
Fe-59 1.7E-07
3.1E-09
Co-57 1.6E-08
3.6E-10
Co-58 1.4E-07
2.8E-09
Co-60 3.6E-07
6.4E-09
Zn-65 8.5E-08
1.5E-09
Se-75 5.2E-08
1.1E-09
Br-82 3.8E-07
7.3E-09
Kr-79 3.5E-08
7.2E-10
Kr-81 1.4E-09
3.3E-11
Kr-83m 6.9E-12
1.6E-12
Kr-85 7.8E-10
3.6E-11
Kr-85m 2.2E-08
5.1E-10
Kr-87 1.3E-07
2.5E-09
Kr-88 3.2E-07
5.0E-09
Nuclide
External exposure to cloud radiation
External exposure to ground radiation
eimm
(mSv/h)/(Bq/m3)
esol
(mSv/h)/(Bq/m2)
Kr-88/Rb-88
4.2E-07
7.2E-09
Kr-89
2.9E-07
5.1E-09
Kr-90
1.9E-07
3.8E-09
Sr-89
1.4E-09
2.4E-10
Sr-90
3.3E-10
5.0E-12
Sr-90/Y-90
2.6E-09
3.9E-10
Y-91
1.9E-09
2.6E-10
Zr-95
1.1E-07
2.1E-09
Nb-95
1.1E-07
2.2E-09
Mo-99
2.3E-08
5.7E-10
Mo-99/Tc-99m
3.8E-08
9.1E-10
Tc-99m
1.7E-08
3.8E-10
Ru-103
6.7E-08
1.4E-09
Ru-106
0.0E+00
0.0E+00
Ru-106/Rh-106
3.3E-08
1.1E-09
Ag-110m
4.0E-07
7.5E-09
Sn-125
4.7E-08
1.1E-09
Sb-122
6.4E-08
1.5E-09
Sb-124
2.8E-07
5.0E-09
Sb-125
5.9E-08
1.2E-09
Sb-127
9.4E-08
2.0E-09
Te-125m
9.1E-10
3.9E-11
Te-127m
3.0E-10
1.3E-11
Te-129m
5.2E-09
1.9E-10
Radiological Protection 108
814.501
Nuclide
External exposure to cloud radiation
External exposure to ground radiation
eimm
(mSv/h)/(Bq/m3)
esol
(mSv/h)/(Bq/m2)
Te-131m 2.1E-07
3.9E-09
Te-132 2.9E-08
6.4E-10
Te-132/I-132 3.6E-07 7.2E-09
I-125 1.0E-09
4.5E-11
I-129 8.0E-10
4.2E-11
I-130 3.0E-07
6.1E-09
I-131 5.2E-08
1.1E-09
I-132 3.3E-07
6.6E-09
I-133 8.6E-08
1.8E-09
I-134 3.9E-07
7.5E-09
I-135 2.3E-07
4.2E-09
Xe-122 7.9E-09
1.8E-10
Xe-123 8.8E-08
1.8E-09
Xe-125 3.3E-08
7.3E-10
Xe-127 3.5E-08
7.8E-10
Xe-129m 2.8E-09
9.8E-11
Xe-131m 1.1E-09
3.7E-11
Xe-133 4.3E-09
1.2E-10
Xe-133m 4.0E-09
9.9E-11
Xe-135 3.4E-08
7.9E-10
Xe-135m 5.9E-08
1.3E-09
Xe-137 3.1E-08
1.1E-09
Xe-138 1.8E-07
3.2E-09
Cs-134 2.2E-07
4.4E-09
Cs-136 3.1E-07
6.0E-09
Cs-137 2.6E-10
8.5E-12
Cs-137/Ba-137m 8.1E-08 1.6E-09
Ba-140 2.6E-08
6.0E-10
Ba-140/La-140 3.7E-07 6.8E-09
La-140 3.5E-07
6.2E-09
Ce-141 1.0E-08
2.3E-10
Nuclide
External exposure to cloud radiation
External exposure to ground radiation
eimm
(mSv/h)/(Bq/m3)
esol
(mSv/h)/(Bq/m2)
Ce-144
2.4E-09
5.4E-11
Ce-144/Pr-144
1.0E-08
5.9E-10
Pr-143
6.2E-10
7.2E-11
Pb-210
1.4E-10
5.9E-12
Bi-210
8.1E-10
1.2E-10
Po-210
1.3E-12
2.5E-14
Ra-224
1.3E-09
2.9E-11
Ra-226
9.0E-10
2.0E-11
Th-227
1.4E-08
3.1E-10
Th-228
2.5E-10
6.4E-12
Th-230
4.6E-11
1.8E-12
Th-232
2.1E-11
1.2E-12
Pa-231
4.0E-09
9.1E-11
U-234
1.6E-11
1.3E-12
U-235
2.0E-08
4.4E-10
U-238
1.0E-11
1.0E-12
Np-237
2.8E-09
7.5E-11
Np-239
2.2E-08
4.9E-10
Pu-238
7.3E-12
1.3E-12
Pu-239
9.0E-12
6.2E-13
Pu-240
7.2E-12
1.2E-12
Pu-241
0.0E+00
0.0E+00
Am-241
2.2E-09
6.7E-11
Cm-242
8.0E-12
1.4E-12
Cm-244
6.6E-12
1.2E-12
Ordinance
109
814.501
eimm
Dose coefficients for external exposure during immersion in a semiinfinite hemispherical cloud outdoors
esol
Dose coefficients for external exposure from ground deposition over a large area.
Zero values Values less than 4.0E-19 are given as 0.0E+00.
*
Inserted by No. III Para. 2 of the Amendment of 24 Oct. 2007, in force since 1 Jan. 2008 (AS 2007 5651).
Radiological Protection 110
814.501