1-3 General data on the radionuclide [source: International Commission on Radiological Protection, ICRP Publication 107]. 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 Half-life: s, second(s); min, minute(s); h, hour(s); d, day(s); a, year(s); E, exponential notation. Source: International Commission on Radiological Protection, ICRP Publication 107. For individual nuclides not listed therein: IAEA Safety Standards: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards (BSS), Revision of IAEA Safety Series No. 115, GOV/2011/42, 15 August 2011; Table III.2A.
3 Type of decay/radiation: α, alpha radiation; β+, β-, beta radiation; ec, electron capture; it, isomeric transition; sf, spontaneous fission. For «/radiation», «/ph» is given for each radionuclide where decay involves emission of photon radiation (γ or X-rays) with an energy of more than 10-4 MeV per decay.
4, 5 Dose coefficient for the committed effective dose resulting from inhalation or ingestion of a radionuclide in adults [source: IAEA Safety Standards: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, Revision of IAEA Safety Series No. 115, GOV/2011/42, 15 August 2011; Table III.2A, Column e(g)5 µm for inhalation and Column e(g) for ingestion. For individual nuclides not listed therein: ICRP Database of Dose Coefficients: Workers and Members of the Public, available on the ICRP website under «Free Educational CD Downloads».
4 Dose coefficient for the committed effective dose resulting from inhalation of a radionuclide. The inhalation of 1 Bq yields, at most, the committed effective dose (in Sv) indicated. The value given is the maximum for the various types (or rates) of absorption from the lung into the blood (fast, moderate or slow), with an activity median aerodynamic diameter (AMAD) of 5 µm
Note: For twelve radionuclides [Nb-91, Nb-91m, Nb-92m, Te-119m,
Nd-140, Re‑183, Pt-190, Au-196, Bi-208, Po-206, Po-208, Po-209] the einh values are not included either in the IAEA BSS or on the ICRP CD. For the RPO of 22 June 199466, the values for these radionuclides were taken from the National Radiological Protection Board report NRPB-R245 (1991). As this source is no longer up to date and these radionuclides are of only minor importance, dose coefficients are not given for these twelve radionuclides in this Ordinance.
5 Dose coefficient for the committed effective dose resulting from ingestion of a radionuclide. The ingestion of 1 Bq yields, at most, the committed effective dose (in Sv) indicated.
Note: For twelve radionuclides (as for einh) the eing values are not included either in the IAEA BSS or on the ICRP CD. For the RPO of 22 June 1994, the values for these radionuclides were taken from the National Radiological Protection Board report NRPB-R245 (1991). As this source is no longer up to date and these radionuclides are of only minor importance, dose coefficients are not given for these twelve radionuclides in this Ordinance.
6-8 Dose coefficient 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 radioactive source 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 radioactive source with an activity of 1 GBq.
8 Dose coefficient for skin contamination. Skin contamination of 1 kBq/cm2 (averaged over 100 cm2) yields the dose rate (directional dose equivalent rate) indicated.
9-12 Clearance limit, licensing limit and guidance values
9 Clearance limit for specific activity in Bq/g (LL). [Sources: IAEA, Safety Standards: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, Revision of IAEA Safety Series No. 115, GOV/2011/42, 15 August 2011; Table I.2; Brenk Systemplanung, Berechnung von Freigrenzen and Freigabewerten für Nuklide, für die keine Werte in den IAEA-BSS vorliegen, Endbericht, Aachen, 2012.] For radionuclides with a short half-life, the exemption levels calculated in the report by Brenk Systemplanung are often higher than the exemption levels for specific activity which are specified for moderate amounts of material in the IAEA BSS. In such cases, and for the small number of radionuclides for which no value was calculated by Brenk Systemplanung, the values specified for moderate amounts of material in the IAEA BSS are used in this Ordinance [source: IAEA, Safety Standards: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, Revision of IAEA Safety Series No. 115, GOV/2011/42, 15 August 2011; Table I.1, Column «Activity concentration»]. Radionuclides for which the exemption levels given for moderate amounts of material in the IAEA BSS are used are marked [1] in Column 9 of the Table.
Radionuclides for which the contribution of daughter nuclides was taken into account in determining the LL value are marked [2] in Column 9 of the Table. The Table below indicates, for each radionuclide for which a daughter nuclide was taken into account, the last radionuclide in the decay chain which was used together with the parent to calculate the LL value.
Example: Ra-226 -> Po-214 means that the daughter nuclides of Ra-226 up to Po-214 (i.e. Rn-222, Po-218, Pb-214, Bi-214 and Po-214) were taken into account, together with the parent, in calculating the clearance level.
For H-3 and S-35, which can occur in various chemical forms, the LL was calculated in the Brenk Systemplanung report using the more pessimistic dose coefficient for each exposure pathway (e.g. in the case of S-35, with eing for S‑35 org. and einh for S-35 inorg.). The LL values thus determined were applied to all chemical forms of the radionuclide.
10 Licensing limit (LA). The licensing limit values are derived from Column 4 since inhalation is the main risk when radionuclides are handled in the laboratory. The inhalation of activity at the licensing limit on a single occasion yields a committed effective dose of 5 mSv.
For inert gases, C-11, N-13, O-15, F-18 and Cl-38, the licensing limit corresponds to the activity in an enclosed space of 1000 m3 and a CA concentration as specified in Column 11.
11 Guidance value for chronic airborne activity for occupationally exposed persons (CA). 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/a).
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. (The dose coefficients for immersion eimm are taken from ICRP Publication 119 if they are not covered by Guideline ENSI-G14.) 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. [5]: 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. In this case, the dose coefficients eimm for the skin are taken from the publication: Federal Guidance Report No. 12, External exposure to radionuclides in air, water and soil, Keith F. Eckerman and Jeffrey C. Ryman, Sept. 1993.
12 Guidance value for surface contamination outside of controlled areas, averaged over 100 cm2 (CS).
The CS value is calculated on the basis of the following scenarios, with the most unfavourable being chosen:
- -
- chronic exposure throughout the year (8760 hours) resulting from skin contamination yields an equivalent dose of 50 mSv per year (1/10 of the dose limit for the skin);
- -
- daily ingestion of contamination on an area of 10 cm2 yields an effective dose of 0.5 mSv per year;
- -
- a single inhalation of 10% of the activity of contamination on an area of 100 cm2 yields a dose of 0.5 mSv (1/10 of the licensing limit);
- -
- a maximum value of 1000 Bq/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!).
List of footnotes:
[1] Radionuclides for which the values given for moderate amounts of material in the IAEA BSS are used as the clearance limit.
[2] Radionuclides for which the contribution of daughter nuclides was taken into account in determining the LL value (Column 9). The Table below indicates, for each of these radionuclides, the last radionuclide in the decay chain which was used together with the parent to calculate the LL value.
[3] Derived from the effective dose for immersion (Column 11).
[4] Derived from the skin dose for immersion (Column 11).
[5] In the case of Kr-88, values are given for the daughter nuclide for immersion (Column 11).
[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 must also be taken into account.
[8] For Kr-85, LA was chosen so that the dose rate at a distance of 10 cm
is 5 µSv/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.
[10] Potassium salts in quantities less than 1000 kg are exempted.
[11] For nuclide mixtures of uranium (U-238/U-235/U-234 + daughters) and of thorium (Th-232/Th-230/Th-228 + daughters), the licensing limit of the dominant nuclide applies.
Nuclide mixtures
In the case of nuclide mixtures, the summation rule applies for Columns 9, 11 and 12:
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 below the clearance limit or below the guidance value for surface contamination.
a1, a2, ... an: specific activities of nuclides 1, 2, ..., n in Bq/g.
LL1, LL2, ... LLn : clearance limits for nuclides 1, 2, ..., n in Bq/g as specified in Annex 3 Column 9.
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.
For Footnote [2]: Daughter nuclides taken into account in calculating the clearance limit
Nuclide
|
Daughter nuclides
|
Nuclide
|
Daughter nuclides
|
Nuclide
|
Daughter nuclides
|
Nuclide
|
Daughter nuclides
|
Nuclide
|
Daughter nuclides
|
Mg-28
|
-> Al-28
|
Mo-99
|
-> Tc-99m
|
I-135
|
-> Xe-135m
|
Hg-195m
|
-> Hg-195
|
Np-237
|
-> Pa-233
|
Si-32
|
-> P-32
|
Tc-95m
|
-> Tc-95
|
Cs-137
|
-> Ba-137m
|
Pb-202
|
-> Tl-202
|
Pu-239
|
-> U-235m
|
Ca-45
|
-> Sc-45m
|
Ru-103
|
-> Rh-103m
|
Ba-128
|
-> Cs-128
|
Pb-210
|
-> Bi-210
|
Pu-244
|
-> Np-240
|
Sc-44m
|
-> Sc-44
|
Ru-106
|
-> Rh-106
|
Ce-134
|
-> La-134
|
Pb-212
|
-> Tl-208
|
Pu-245
|
-> Am-245
|
Ti-44
|
-> Sc-44
|
Pd-100
|
-> Rh-100
|
Ce-137m
|
-> Ce-137
|
Bi-210m
|
-> Tl-206
|
Pu-246
|
-> Am-246m
|
Fe-52
|
-> Mn-52m
|
Pd-109
|
-> Ag-109m
|
Ce-144
|
-> Pr-144
|
At-211
|
-> Po-211
|
Am-242m
|
-> Np-238
|
Fe-60
|
-> Co-60
|
Ag-108m
|
-> Ag-108
|
Nd-138
|
-> Pr-138
|
Rn-222
|
-> Tl-210
|
Am-243
|
-> Np-239
|
Ni-66
|
-> Cu-66
|
Ag-110m
|
-> Ag-110
|
Nd-140
|
-> Pr-140
|
Fr-222
|
-> Po-214
|
Cm-247
|
-> Pu-243
|
Zn-62
|
-> Cu-62
|
Cd-109
|
-> Ag-109m
|
Gd-146
|
-> Eu-146
|
Ra-223
|
-> Tl-207
|
Cm-250
|
-> Am-246m
|
Zn-69m
|
-> Zn-69
|
Cd-113m
|
-> In-113m
|
Yb-178
|
-> Lu-178
|
Ra-224
|
-> Tl-208
|
Cf-253
|
-> Cm-249
|
Zn-72
|
-> Ga-72m
|
Cd-115
|
-> In-115m
|
Lu-177m
|
-> Lu-177
|
Ra-226
|
-> Po-214
|
|
|
Ge-68
|
-> Ga-68
|
Cd-115m
|
-> In-115m
|
Hf-172
|
-> Sn-121m
|
Ra-228
|
-> Ac-228
|
|
|
As-73
|
-> Ge-73m
|
In-111
|
-> Cd-111m
|
Hf-182
|
-> Ta-182
|
Ac-225
|
-> Pb-209
|
|
|
Br-80m
|
-> Br-80
|
In-114m
|
-> In-114
|
W-188
|
-> Re-188
|
Ac-226
|
-> Th-226
|
|
|
Br-83
|
-> Kr-83m
|
Sn-110
|
-> In-110m
|
Re-186m
|
-> Re-186
|
Ac-227
|
-> Bi-211
|
|
|
Rb-83
|
-> Kr-83m
|
Sn-113
|
-> In-113m
|
Re-189
|
-> Os-189m
|
Th-228
|
-> Tl-208
|
|
|
Sr-80
|
-> Rb-80
|
Sn-121m
|
-> Sn-121
|
Os-191
|
-> Ir-191m
|
Th-229
|
-> Pb-209
|
|
|
Sr-89
|
-> Y-89m
|
Sn-126
|
-> Sb-126
|
Os-194
|
-> Ir-194
|
Th-232
|
-> Tl-208
|
|
|
Sr-90
|
-> Y-90
|
Sb-125
|
-> Te-125m
|
Ir-189
|
-> Os-189m
|
Th-234
|
-> Pa-234
|
|
|
Sr-91
|
-> Y-91m
|
Sb-127
|
-> Te-127
|
Ir-190
|
-> Os-190m
|
U-230
|
-> Po-214
|
|
|
Y-87
|
-> Sr-87m
|
Te-127m
|
-> Te-127
|
Ir-194m
|
-> Ir-194
|
U-232
|
-> Tl-208
|
|
|
Zr-86
|
-> Y-86m
|
Te-129m
|
-> Te-129
|
Pt-191
|
-> Ir-191m
|
U-235
|
-> Th-231
|
|
|
Zr-95
|
-> Nb-95m
|
Te-131m
|
-> Te-131
|
Pt-200
|
-> Au-200
|
U-238
|
-> Pa-234
|
|
|
Zr-97
|
-> Nb-97
|
Te-132
|
-> I-132
|
Hg-194
|
-> Au-194
|
U-240
|
-> Np-240
|
|
|