Definitions of specific terms
A1 and A2
A1 means the activity value of special form radioactive material which is listed in the Table in 2.2.7.2.2.1 or derived in 2.2.7.2.2.2 and is used to determine the activity limits for the requirements of ADR.
A2 means the activity value of radioactive material, other than special form radioactive material, which is listed in the Table in 2.2.7.2.2.1 or derived in 2.2.7.2.2.2 and is used to determine the activity limits for the requirements of ADR.
Fissile nuclidesmeans uranium-233, uranium-235, plutonium-239 and plutonium-241. Fissile materialmeans a material containing any of the fissile nuclides. Excluded from the definition of fissile material are the following:
(a)Natural uranium or depleted uranium which is unirradiated;
(b)Natural uranium or depleted uranium which has been irradiated in thermal reactors only;
(c)Material with fissile nuclides less than a total of0.25g;
(d)Any combination of (a), (b) and/or (c).
These exclusions are only valid if there is no other material with fissile nuclides in the package or in the consignment if shipped unpackaged.
Low dispersible radioactive materialmeans either a solid radioactive material or a solid radioactive material in a sealed capsule, that has limited dispersibility and is not in powder form.
Low specific activity (LSA) materialmeans radioactive material which by its nature has a limited specific activity, or radioactive material for which limits of estimated average specific activity apply. External shielding materials surrounding the LSA material shall not be considered in determining the estimated average specific activity.
Low toxicity alpha emittersare: natural uranium; depleted uranium; natural thorium; uranium-235 or uranium-238; thorium-232; thorium-228 and thorium-230 when contained in ores or physical andchemical concentrates; or alpha emitters with a half-life of less than 10 days.
Special form radioactive materialmeans either:
(a)An indispersible solid radioactive material; or
(b)A sealed capsule containing radioactive material.
Specific activity of a radionuclidemeans the activity per unit mass of that nuclide. The specific activity of a material shall mean the activity per unit mass of the material in which the radionuclides are essentially uniformly distributed.
Surface contaminated object (SCO) means a solid object which is not itself radioactive but which has radioactive material distributed on its surface.Unirradiated thoriummeans thorium containing not more than 10-7g of uranium-233 per gram of thorium-232.
Unirradiated uraniummeans uraniumcontaining not more than 2 ×103Bq of plutonium per gram of uranium-235, not more than 9×106Bq of fission products per gram of uranium-235 and not more than 5 ×10-3g of uranium-236 per gram of uranium-235.
Uranium - natural, depleted, enrichedmeansthe following:
Natural uraniummeans uranium (which may be chemically separated) containing the naturally occurring distribution of uranium isotopes (approximately 99.28% uranium-238, and 0.72% uranium-235 by mass).
Depleted uraniummeans uranium containing a lesser mass percentage of uranium-235 than in natural uranium.
Enriched uraniummeans uranium containing a greater mass percentage of uranium-235than0.72%.
In all cases, a very small mass percentage of uranium-234 is present.
Classification
General provisions
Radioactive material shall be assigned to one of the UN numbers specified in Table 2.2.7.2.1.1, in accordance with 2.2.7.2.4 and 2.2.7.2.5, taking into account the material characteristics determined in 2.2.7.2.3.
Table 2.2.7.2.1.1 Assignment of UN numbers
|
UN No |
Proper shipping name and description a |
|
Excepted packages (1.7.1.5) |
|
|
UN 2908 |
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - EMPTY PACKAGING |
|
UN 2909 |
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - ARTICLES MANUFACTURED FROM NATURAL URANIUM or DEPLETED URANIUM or NATURAL THORIUM |
|
UN 2910 |
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - LIMITED QUANTITY OF MATERIAL |
|
UN 2911 |
RADYOAKTİF MALZEME, ADİ PAKET - ALETLER veya NESNELER |
|
UN 3507 |
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - INSTRUMENTS or ARTICLES UN 3507 URANIUM HEXAFLUORIDE, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE less than 0.1 kg per package, non-fissile or fissile-excepted b, c |
|
Low specific activity radioactive material (2.2.7.2.3.1) |
|
|
UN 2912 |
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I), non fissile or fissile-excepted b |
|
UN 3321 |
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), non fissile or fissile-excepted b |
|
UN 3322 |
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III), non fissile or fissile-excepted b |
|
UN 3324 |
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), FISSILE |
|
UN 3325 |
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY, (LSA-III), FISSILE |
|
Surface contaminated objects (2.2.7.2.3.2) |
|
|
UN 2913 |
RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II), non fissile or fissile-excepted b |
|
UN 3326 |
RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II), FISSILE |
|
Type A packages (2.2.7.2.4.4) |
|
|
UN 2915 |
RADIOACTIVE MATERIAL, TYPE A PACKAGE, non-special form, non fissile or fissile- excepted b |
|
UN 3327 |
RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE, non-special form |
|
UN 3332 |
RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, non fissile or fissile excepted b |
|
UN 3333 |
RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, FISSILE |
|
Type B(U) packages (2.2.7.2.4.6) |
|
|
UN 2916 |
RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, non fissile or fissile-excepted b |
|
UN 3328 |
RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, FISSILE |
|
Type B(M) packages (2.2.7.2.4.6) |
|
|
UN 2917 |
RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE, non fissile or fissile-excepted b |
|
UN 3329 |
RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE, FISSILE |
|
Type C packages (2.2.7.2.4.6) |
|
|
UN 3323 |
RADIOACTIVE MATERIAL, TYPE C PACKAGE, non fissile or fissile-excepted b |
|
UN 3330 |
RADIOACTIVE MATERIAL, TYPE C PACKAGE, FISSILE |
|
Special arrangement (2.2.7.2.5) |
|
|
UN 2919 |
RADIOACTIVE MATERIAL, TRANSPORTED UNDER SPECIAL ARRANGEMENT, non fissile or fissile-excepted b |
|
UN 3331 |
RADIOACTIVE MATERIAL, TRANSPORTED UNDER SPECIAL ARRANGEMENT, FISSILE |
|
Uranium hexafluoride (2.2.7.2.4.5) |
|
|
UN 2977 |
RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, FISSILE |
|
UN 2978 |
RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, non fissile or fissile-excepted b |
|
UN 3507 |
URANIUM HEXAFLUORIDE, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE less than 0.1 kg per package, non-fissile or fissile-excepted b, c |
_____________________
a The proper shipping name is found in the column “proper shipping name and description” and is restricted to that part shown in capital letters. In the cases of UN Nos. 2909, 2911, 2913 and 3326, where alternative proper shipping names are separated by the word “or” only the relevant proper shipping name shall be used.
b The term "fissile-excepted" refers only to material excepted under 2.2.7.2.3.5.
c For UN No. 3507, see also special provision 369 in Chapter 3.3.
Determination of basic radionuclide values
The following basic values for individual radionuclides are given in Table 2.2.7.2.2.1:
(a) A1and A2in TBq;
(b) Activity concentration limits for exempt material in Bq/g; and
(c) Activity limits for exempt consignments in Bq.
Table 2.2.7.2.2.1: Basic radionuclides values for individual radionuclides
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Actinium (89) |
||||
|
Ac-225 (a) |
8 x 10-1 |
6 x 10-3 |
1 x 101 |
1 x 104 |
|
Ac-227 (a) |
9 x 10-1 |
9 x 10-5 |
1 x 10-1 |
1 x 103 |
|
Ac-228 |
6 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Silver (47) |
||||
|
Ag-105 |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Ag-108m (a) |
7 x 10-1 |
7 x10-1 |
1 x101 (b) |
1 x 106 (b) |
|
Ag-110m (a) |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 106 |
|
Ag-111 |
2 x 100 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Aluminium (13) |
||||
|
Al-26 |
1 x 10-1 |
1 x 10-1 |
1 x 101 |
1 x 105 |
|
Americium (95) |
||||
|
Am-241 |
1 x 101 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Am-242m (a) |
1 x 101 |
1 x 10-3 |
1 x 100 (b) |
1 x 104 (b) |
|
Am-243 (a) |
5 x 100 |
1 x 10-3 |
1 x 100 (b) |
1 x 103 (b) |
|
Argon (18) |
||||
|
Ar-37 |
4 x 101 |
4 x 101 |
1 x 106 |
1 x 108 |
|
Ar-39 |
4 x 101 |
2 x 101 |
1 x 107 |
1 x 104 |
|
Ar-41 |
3 x 10-1 |
3 x 10-1 |
1 x 102 |
1 x 109 |
|
Arsenic (33) |
||||
|
As-72 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
As-73 |
4 x 101 |
4 x 101 |
1 x 103 |
1 x 107 |
|
As-74 |
1 x 100 |
9 x 10-1 |
1 x 101 |
1 x 106 |
|
As-76 |
3 x 10-1 |
3 x 10-1 |
1 x 102 |
1 x 105 |
|
As-77 |
2 x 101 |
7 x 10-1 |
1 x 103 |
1 x 106 |
|
Astatine (85) |
||||
|
At-211 (a) |
2 x 101 |
5 x 10-1 |
1 x 103 |
1 x 107 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Gold (79) |
||||
|
Au-193 |
7 x 100 |
2 x 100 |
1 x 102 |
1 x 107 |
|
Au-194 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Au-195 |
1 x 101 |
6 x 100 |
1 x 102 |
1 x 107 |
|
Au-198 |
1 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Au-199 |
1 x 101 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Barium (56) |
||||
|
Ba-131 (a) |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Ba-133 |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Ba-133m |
2 x 101 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Ba-140 (a) |
5 x 10-1 |
3 x 10-1 |
1 x 101 (b) |
1 x 105 (b) |
|
Beryllium (4) |
||||
|
Be-7 |
2 x 101 |
2 x 101 |
1 x 103 |
1 x 107 |
|
Be-10 |
4 x 101 |
6 x 10-1 |
1 x 104 |
1 x 106 |
|
Bismuth (83) |
||||
|
Bi-205 |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Bi-206 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Bi-207 |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Bi-210 |
1 x 100 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Bi-210m (a) |
6 x 10-1 |
2 x 10-2 |
1 x 101 |
1 x 105 |
|
Bi-212 (a) |
7 x 10-1 |
6 x 10-1 |
1 x 101 (b) |
1 x 105 (b) |
|
Berkelium (97) |
||||
|
Bk-247 |
8 x 100 |
8 x 10-4 |
1 x 100 |
1 x 104 |
|
Bk-249 (a) |
4 x 101 |
3 x 10-1 |
1 x 103 |
1 x 106 |
|
Bromine (35) |
||||
|
Br-76 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
Br-77 |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Br-82 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 106 |
|
Carbon (6) |
||||
|
C-11 |
1 x 100 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
C-14 |
4 x 101 |
3 x 100 |
1 x 104 |
1 x 107 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Calcium (20) |
||||
|
Ca-41 |
Unlimited |
Unlimited |
1 x 105 |
1 x 107 |
|
Ca-45 |
4 x 101 |
1 x 100 |
1 x 104 |
1 x 107 |
|
Ca-47 (a) |
3 x 100 |
3 x 10-1 |
1 x 101 |
1 x 106 |
|
Cadmium (48) |
||||
|
Cd-109 |
3 x 101 |
2 x 100 |
1 x 104 |
1 x 106 |
|
Cd-113m |
4 x 101 |
5 x 10-1 |
1 x 103 |
1 x 106 |
|
Cd-115 (a) |
3 x 100 |
4 x 10-1 |
1 x 102 |
1 x 106 |
|
Cd-115m |
5 x 10-1 |
5 x 10-1 |
1 x 103 |
1 x 106 |
|
Cerium (58) |
||||
|
Ce-139 |
7 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Ce-141 |
2 x 101 |
6 x 10-1 |
1 x 102 |
1 x 107 |
|
Ce-143 |
9 x 10-1 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Ce-144 (a) |
2 x 10-1 |
2 x 10-1 |
1 x 102 (b) |
1 x 105 (b) |
|
Californium (98) |
||||
|
Cf-248 |
4 x 101 |
6 x 10-3 |
1 x 101 |
1 x 104 |
|
Cf-249 |
3 x 100 |
8 x 10-4 |
1 x 100 |
1 x 103 |
|
Cf-250 |
2 x 101 |
2 x 10-3 |
1 x 101 |
1 x 104 |
|
Cf-251 |
7 x 100 |
7 x 10-4 |
1 x 100 |
1 x 103 |
|
Cf-252 |
1 x 10-1 |
3 x 10-3 |
1 x 101 |
1 x 104 |
|
Cf-253 (a) |
4 x 101 |
4 x 10-2 |
1 x 102 |
1 x 105 |
|
Cf-254 |
1 x 10-3 |
1 x 10-3 |
1 x 100 |
1 x 103 |
|
Chlorine (17) |
||||
|
Cl-36 |
1 x 101 |
6 x 10-1 |
1 x 104 |
1 x 106 |
|
Cl-38 |
2 x 10-1 |
2 x 10-1 |
1 x 101 |
1 x 105 |
|
Curium (96) |
||||
|
Cm-240 |
4 x 101 |
2 x 10-2 |
1 x 102 |
1 x 105 |
|
Cm-241 |
2 x 100 |
1 x 100 |
1 x 102 |
1 x 106 |
|
Cm-242 |
4 x 101 |
1 x 10-2 |
1 x 102 |
1 x 105 |
|
Cm-243 |
9 x 100 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Cm-244 |
2 x 101 |
2 x 10-3 |
1 x 101 |
1 x 104 |
|
Cm-245 |
9 x 100 |
9 x 10-4 |
1 x 100 |
1 x 103 |
|
Cm-246 |
9 x 100 |
9 x 10-4 |
1 x 100 |
1 x 103 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Cm-247 (a) |
3 x 100 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Cm-248 |
2 x 10-2 |
3 x 10-4 |
1 x 100 |
1 x 103 |
|
Cobalt (27) |
||||
|
Co-55 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Co-56 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Co-57 |
1 x 101 |
1 x 101 |
1 x 102 |
1 x 106 |
|
Co-58 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Co-58m |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 107 |
|
Co-60 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
Chromium (24) |
||||
|
Cr-51 |
3 x 101 |
3 x 101 |
1 x 103 |
1 x 107 |
|
Caesium (55) |
||||
|
Cs-129 |
4 x 100 |
4 x 100 |
1 x 102 |
1 x 105 |
|
Cs-131 |
3 x 101 |
3 x 101 |
1 x 103 |
1 x 106 |
|
Cs-132 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 105 |
|
Cs-134 |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 104 |
|
Cs-134m |
4 x 101 |
6 x 10-1 |
1 x 103 |
1 x 105 |
|
Cs-135 |
4 x 101 |
1 x 100 |
1 x 104 |
1 x 107 |
|
Cs-136 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 105 |
|
Cs-137 (a) |
2 x 100 |
6 x 10-1 |
1 x 101 (b) |
1 x 104 (b) |
|
Copper (29) |
||||
|
Cu-64 |
6 x 100 |
1 x 100 |
1 x 102 |
1 x 106 |
|
Cu-67 |
1 x 101 |
7 x 10-1 |
1 x 102 |
1 x 106 |
|
Dysprosium (66) |
||||
|
Dy-159 |
2 x 101 |
2 x 101 |
1 x 103 |
1 x 107 |
|
Dy-165 |
9 x 10-1 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Dy-166 (a) |
9 x 10-1 |
3 x 10-1 |
1 x 103 |
1 x 106 |
|
Erbium (68) |
||||
|
Er-169 |
4 x 101 |
1 x 100 |
1 x 104 |
1 x 107 |
|
Er-171 |
8 x 10-1 |
5 x 10-1 |
1 x 102 |
1 x 106 |
|
Europium (63) |
||||
|
Eu-147 |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Eu-148 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Eu-149 |
2 x 101 |
2 x 101 |
1 x 102 |
1 x 107 |
|
Eu-150 (short lived) |
2 x 100 |
7 x 10-1 |
1 x 103 |
1 x 106 |
|
Eu-150 (long lived) |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Eu-152 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Eu-152m |
8 x 10-1 |
8 x 10-1 |
1 x 102 |
1 x 106 |
|
Eu-154 |
9 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Eu-155 |
2 x 101 |
3 x 100 |
1 x 102 |
1 x 107 |
|
Eu-156 |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Fluorine (9) |
||||
|
F-18 |
1 x 100 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Iron (26) |
||||
|
Fe-52 (a) |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 106 |
|
Fe-55 |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 106 |
|
Fe-59 |
9 x 10-1 |
9 x 10-1 |
1 x 101 |
1 x 106 |
|
Fe-60 (a) |
4 x 101 |
2 x 10-1 |
1 x 102 |
1 x 105 |
|
Gallium(31) |
||||
|
Ga-67 |
7 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Ga-68 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 105 |
|
Ga-72 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
Gadolinium (64) |
||||
|
Gd-146 (a) |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Gd-148 |
2 x 101 |
2 x 10-3 |
1 x 101 |
1 x 104 |
|
Gd-153 |
1 x 101 |
9 x 100 |
1 x 102 |
1 x 107 |
|
Gd-159 |
3 x 100 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Germanium (32) |
||||
|
Ge-68 (a) |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 105 |
|
Ge-71 |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 108 |
|
Ge-77 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Hafnium (72) |
||||
|
Hf-172 (a) |
6 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Hf-175 |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Hf-181 |
2 x 100 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Hf-182 |
Unlimited |
Unlimited |
1 x 102 |
1 x 106 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Mercury (80) |
||||
|
Hg-194 (a) |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Hg-195m (a) |
3 x 100 |
7 x 10-1 |
1 x 102 |
1 x 106 |
|
Hg-197 |
2 x 101 |
1 x 101 |
1 x 102 |
1 x 107 |
|
Hg-197m |
1 x 101 |
4 x 10-1 |
1 x 102 |
1 x 106 |
|
Hg-203 |
5 x 100 |
1 x 100 |
1 x 102 |
1 x 105 |
|
Holmium (67) |
||||
|
Ho-166 |
4 x 10-1 |
4 x 10-1 |
1 x 103 |
1 x 105 |
|
Ho-166m |
6 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Iodine (53) |
||||
|
I-123 |
6 x 100 |
3 x 100 |
1 x 102 |
1 x 107 |
|
I-124 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
I-125 |
2 x 101 |
3 x 100 |
1 x 103 |
1 x 106 |
|
I-126 |
2 x 100 |
1 x 100 |
1 x 102 |
1 x 106 |
|
I-129 |
Unlimited |
Unlimited |
1 x102 |
1 x 105 |
|
I-131 |
3 x 100 |
7 x 10-1 |
1 x 102 |
1 x 106 |
|
I-132 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
I-133 |
7 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
I-134 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
I-135 (a) |
6 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Indium (49) |
||||
|
In-111 |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
In-113m |
4 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
In-114m (a) |
1 x 101 |
5 x 10-1 |
1 x 102 |
1 x 106 |
|
In-115m |
7 x 100 |
1 x 100 |
1 x 102 |
1 x 106 |
|
Iridium (77) |
||||
|
Ir-189 (a) |
1 x 101 |
1 x 101 |
1 x 102 |
1 x 107 |
|
Ir-190 |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Ir-192 |
1 x 100(c) |
6 x 10-1 |
1 x 101 |
1 x 104 |
|
Ir-194 |
3 x 10-1 |
3 x 10-1 |
1 x 102 |
1 x 105 |
|
Potassium (19) |
||||
|
K-40 |
9 x 10-1 |
9 x 10-1 |
1 x 102 |
1 x 106 |
|
K-42 |
2 x 10-1 |
2 x 10-1 |
1 x 102 |
1 x 106 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
K-43 |
7 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Krypton (36) |
||||
|
Kr-79 |
4 x 100 |
2 x 100 |
1 x 103 |
1 x 105 |
|
Kr-81 |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 107 |
|
Kr-85 |
1 x 101 |
1 x 101 |
1 x 105 |
1 x 104 |
|
Kr-85m |
8 x 100 |
3 x 100 |
1 x 103 |
1 x 1010 |
|
Kr-87 |
2 x 10-1 |
2 x 10-1 |
1 x 102 |
1 x 109 |
|
Lanthanum (57) |
||||
|
La-137 |
3 x 101 |
6 x 100 |
1 x 103 |
1 x 107 |
|
La-140 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
Lutetium (71) |
||||
|
Lu-172 |
6 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Lu-173 |
8 x 100 |
8 x 100 |
1 x 102 |
1 x 107 |
|
Lu-174 |
9 x 100 |
9 x 100 |
1 x 102 |
1 x 107 |
|
Lu-174m |
2 x 101 |
1 x 101 |
1 x 102 |
1 x 107 |
|
Lu-177 |
3 x 101 |
7 x 10-1 |
1 x 103 |
1 x 107 |
|
Magnesium (12) |
||||
|
Mg-28 (a) |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Manganese (25) |
||||
|
Mn-52 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Mn-53 |
Unlimited |
Unlimited |
1 x 104 |
1 x 109 |
|
Mn-54 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Mn-56 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Molybdenum (42) |
||||
|
Mo-93 |
4 x 101 |
2 x 101 |
1 x 103 |
1 x 108 |
|
Mo-99 (a) |
1 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Nitrogen (7) |
||||
|
N-13 |
9 x 10-1 |
6 x 10-1 |
1 x 102 |
1 x 109 |
|
Sodium (11) |
||||
|
Na-22 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Na-24 |
2 x 10-1 |
2 x 10-1 |
1 x 101 |
1 x 105 |
|
Niobium (41) |
||||
|
Nb-93m |
4 x 101 |
3 x 101 |
1 x 104 |
1 x 107 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Nb-94 |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Nb-95 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Nb-97 |
9 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Neodymium (60) |
||||
|
Nd-147 |
6 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Nd-149 |
6 x 10-1 |
5 x 10-1 |
1 x 102 |
1 x 106 |
|
Nickel (28) |
||||
|
Ni-59 |
Unlimited |
Unlimited |
1 x 104 |
1 x 108 |
|
Ni-63 |
4 x 101 |
3 x 101 |
1 x 105 |
1 x 108 |
|
Ni-65 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 106 |
|
Neptunium (93) |
||||
|
Np-235 |
4 x 101 |
4 x 101 |
1 x 103 |
1 x 107 |
|
Np-236 (short lived) |
2 x 101 |
2 x 100 |
1 x 103 |
1 x 107 |
|
Np-236 (short lived) |
9 x 100 |
2 x 10-2 |
1 x 102 |
1 x 105 |
|
Np-237 |
2 x 101 |
2 x 10-3 |
1 x 100 (b) |
1 x 103 (b) |
|
Np-239 |
7 x 100 |
4 x 10-1 |
1 x 102 |
1 x 107 |
|
Osmium (76) |
||||
|
Os-185 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Os-191 |
1 x 101 |
2 x 100 |
1 x 102 |
1 x 107 |
|
Os-191m |
4 x 101 |
3 x 101 |
1 x 103 |
1 x 107 |
|
Os-193 |
2 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Os-194 (a) |
3 x 10-1 |
3 x 10-1 |
1 x 102 |
1 x 105 |
|
Phosphorus (15) |
||||
|
P-32 |
5 x 10-1 |
5 x 10-1 |
1 x 103 |
1 x 105 |
|
P-33 |
4 x 101 |
1 x 100 |
1 x 105 |
1 x 108 |
|
Protactinium (91) |
||||
|
Pa-230 (a) |
2 x 100 |
7 x 10-2 |
1 x 101 |
1 x 106 |
|
Pa-231 |
4 x 100 |
4 x 10-4 |
1 x 100 |
1 x 103 |
|
Pa-233 |
5 x 100 |
7 x 10-1 |
1 x 102 |
1 x 107 |
|
Lead (82) |
||||
|
Pb-201 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Pb-202 |
4 x 101 |
2 x 101 |
1 x 103 |
1 x 106 |
|
Pb-203 |
4 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Pb-205 |
Unlimited |
Unlimited |
1 x 104 |
1 x 107 |
|
Pb-210 (a) |
1 x 100 |
5 x 10-2 |
1 x 101 (b) |
1 x 104 (b) |
|
Pb-212 (a) |
7 x 10-1 |
2 x 10-1 |
1 x 101 (b) |
1 x 105 (b) |
|
Palladium (46) |
||||
|
Pd-103 (a) |
4 x 101 |
4 x 101 |
1 x 103 |
1 x 108 |
|
Pd-107 |
Unlimited |
Unlimited |
1 x 105 |
1 x 108 |
|
Pd-109 |
2 x 100 |
5 x 10-1 |
1 x 103 |
1 x 106 |
|
Promethium (61) |
||||
|
Pm-143 |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Pm-144 |
7 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Pm-145 |
3 x 101 |
1 x 101 |
1 x 103 |
1 x 107 |
|
Pm-147 |
4 x 101 |
2 x 100 |
1 x 104 |
1 x 107 |
|
Pm-148m (a) |
8 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Pm-149 |
2 x 100 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Pm-151 |
2 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Polonium (84) |
||||
|
Po-210 |
4 x 101 |
2 x 10-2 |
1 x 101 |
1 x 104 |
|
Praseodymium (59) |
||||
|
Pr-142 |
4 x 10-1 |
4 x 10-1 |
1 x 102 |
1 x 105 |
|
Pr-143 |
3 x 100 |
6 x 10-1 |
1 x 104 |
1 x 106 |
|
Platinum (78) |
||||
|
Pt-188 (a) |
1 x 100 |
8 x 10-1 |
1 x 101 |
1 x 106 |
|
Pt-191 |
4 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Pt-193 |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 107 |
|
Pt-193m |
4 x 101 |
5 x 10-1 |
1 x 103 |
1 x 107 |
|
Pt-195m |
1 x 101 |
5 x 10-1 |
1 x 102 |
1 x 106 |
|
Pt-197 |
2 x 101 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Pt-197m |
1 x 101 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Plutonium (94) |
||||
|
Pu-236 |
3 x 101 |
3 x 10-3 |
1 x 101 |
1 x 104 |
|
Pu-237 |
2 x 101 |
2 x 101 |
1 x 103 |
1 x 107 |
|
Pu-238 |
1 x 101 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Pu-239 |
1 x 101 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Pu-240 |
1 x 101 |
1 x 10-3 |
1 x 100 |
1 x 103 |
|
Pu-241 (a) |
4 x 101 |
6 x 10-2 |
1 x 102 |
1 x 105 |
|
Pu-242 |
1 x 101 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Pu-244 (a) |
4 x 10-1 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Radium (88) |
||||
|
Ra-223 (a) |
4 x 10-1 |
7 x 10-3 |
1 x 102 (b) |
1 x 105 (b) |
|
Ra-224 (a) |
4 x 10-1 |
2 x 10-2 |
1 x 101 (b) |
1 x 105 (b) |
|
Ra-225 (a) |
2 x 10-1 |
4 x 10-3 |
1 x 102 |
1 x 105 |
|
Ra-226 (a) |
2 x 10-1 |
3 x 10-3 |
1 x 101 (b) |
1 x 104 (b) |
|
Ra-228 (a) |
6 x 10-1 |
2 x 10-2 |
1 x 101 (b) |
1 x 105 (b) |
|
Rubidium (37) |
||||
|
Rb-81 |
2 x 100 |
8 x 10-1 |
1 x 101 |
1 x 106 |
|
Rb-83 (a) |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Rb-84 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Rb-86 |
5 x 10-1 |
5 x 10-1 |
1 x 102 |
1 x 105 |
|
Rb-87 |
Unlimited |
Unlimited |
1 x 104 |
1 x 107 |
|
Rb (nat) |
Unlimited |
Unlimited |
1 x 104 |
1 x 107 |
|
Rhenium (75) |
||||
|
Re-184 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Re-184m |
3 x 100 |
1 x 100 |
1 x 102 |
1 x 106 |
|
Re-186 |
2 x 100 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Re-187 |
Unlimited |
Unlimited |
1 x 106 |
1 x 109 |
|
Re-188 |
4 x 10-1 |
4 x 10-1 |
1 x 102 |
1 x 105 |
|
Re-189 (a) |
3 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Re (nat) |
Unlimited |
Unlimited |
1 x 106 |
1 x 109 |
|
Rhodium (45) |
||||
|
Rh-99 |
2 x 100 |
2 x 100 |
1 x 101 |
1 x 106 |
|
Rh-101 |
4 x 100 |
3 x 100 |
1 x 102 |
1 x 107 |
|
Rh-102 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Rh-102m |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Rh-103m |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 108 |
|
Rh-105 |
1 x 101 |
8 x 10-1 |
1 x 102 |
1 x 107 |
|
Radon (86) |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Rn-222 (a) |
3 x 10-1 |
4 x 10-3 |
1 x 101 (b) |
1 x 108 (b) |
|
Ruthenium (44) |
||||
|
Ru-97 |
5 x 100 |
5 x 100 |
1 x 102 |
1 x 107 |
|
Ru-103 (a) |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Ru-105 |
1 x 100 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Ru-106 (a) |
2 x 10-1 |
2 x 10-1 |
1 x 102 (b) |
1 x 105 (b) |
|
Sulphur (16) |
||||
|
S-35 |
4 x 101 |
3 x 100 |
1 x 105 |
1 x 108 |
|
Antimony (51) |
||||
|
Sb-122 |
4 x 10-1 |
4 x 10-1 |
1 x 102 |
1 x 104 |
|
Sb-124 |
6 x 10-1 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Sb-125 |
2 x 100 |
1 x 100 |
1 x 102 |
1 x 106 |
|
Sb-126 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
Scandium (21) |
||||
|
Sc-44 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 105 |
|
Sc-46 |
5 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Sc-47 |
1 x 101 |
7 x 10-1 |
1 x 102 |
1 x 106 |
|
Sc-48 |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Selenium (34) |
||||
|
Se-75 |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Se-79 |
4 x 101 |
2 x 100 |
1 x 104 |
1 x 107 |
|
Silicon (14) |
||||
|
Si-31 |
6 x 10-1 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Si-32 |
4 x 101 |
5 x 10-1 |
1 x 103 |
1 x 106 |
|
Samarium (62) |
||||
|
Sm-145 |
1 x 101 |
1 x 101 |
1 x 102 |
1 x 107 |
|
Sm-147 |
Unlimited |
Unlimited |
1 x 101 |
1 x 104 |
|
Sm-151 |
4 x 101 |
1 x 101 |
1 x 104 |
1 x 108 |
|
Sm-153 |
9 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Tin (50) |
||||
|
Sn-113 (a) |
4 x 100 |
2 x 100 |
1 x 103 |
1 x 107 |
|
Sn-117m |
7 x 100 |
4 x 10-1 |
1 x 102 |
1 x 106 |
|
Sn-119m |
4 x 101 |
3 x 101 |
1 x 103 |
1 x 107 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Sn-121m (a) |
4 x 101 |
9 x 10-1 |
1 x 103 |
1 x 107 |
|
Sn-123 |
8 x 10-1 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Sn-125 |
4 x 10-1 |
4 x 10-1 |
1 x 102 |
1 x 105 |
|
Sn-126 (a) |
6 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
Strontium (38) |
||||
|
Sr-82 (a) |
2 x 10-1 |
2 x 10-1 |
1 x 101 |
1 x 105 |
|
Sr-85 |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Sr-85m |
5 x 100 |
5 x 100 |
1 x 102 |
1 x 107 |
|
Sr-87m |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Sr-89 |
6 x 10-1 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Sr-90 (a) |
3 x 10-1 |
3 x 10-1 |
1 x 102 (b) |
1 x 104 (b) |
|
Sr-91 (a) |
3 x 10-1 |
3 x 10-1 |
1 x 101 |
1 x 105 |
|
Sr-92 (a) |
1 x 100 |
3 x 10-1 |
1 x 101 |
1 x 106 |
|
Tritium (1) |
||||
|
T (H-3) |
4 x 101 |
4 x 101 |
1 x 106 |
1 x 109 |
|
Tantalum (73) |
||||
|
Ta-178 (long-lived) |
1 x 100 |
8 x 10-1 |
1 x 101 |
1 x 106 |
|
Ta-179 |
3 x 101 |
3 x 101 |
1 x 103 |
1 x 107 |
|
Ta-182 |
9 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 104 |
|
Terbium (65) |
||||
|
Tb-157 |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 107 |
|
Tb-158 |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Tb-160 |
1 x 100 |
6 x 10-1 |
1 x 101 |
1 x 106 |
|
Technetium (43) |
||||
|
Tc-95m (a) |
2 x 100 |
2 x 100 |
1 x 101 |
1 x 106 |
|
Tc-96 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 106 |
|
Tc-96m (a) |
4 x 10-1 |
4 x 10-1 |
1 x 103 |
1 x 107 |
|
Tc-97 |
Unlimited |
Unlimited |
1 x 103 |
1 x 108 |
|
Tc-97m |
4 x 101 |
1 x 100 |
1 x 103 |
1 x 107 |
|
Tc-98 |
8 x 10-1 |
7 x 10-1 |
1 x 101 |
1 x 106 |
|
Tc-99 |
4 x 101 |
9 x 10-1 |
1 x 104 |
1 x 107 |
|
Tc-99m |
1 x 101 |
4 x 100 |
1 x 102 |
1 x 107 |
|
Tellurium (52) |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Te-121 |
2 x 100 |
2 x 100 |
1 x 101 |
1 x 106 |
|
Te-121m |
5 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Te-123m |
8 x 100 |
1 x 100 |
1 x 102 |
1 x 107 |
|
Te-125m |
2 x 101 |
9 x 10-1 |
1 x 103 |
1 x 107 |
|
Te-127 |
2 x 101 |
7 x 10-1 |
1 x 103 |
1 x 106 |
|
Te-127m (a) |
2 x 101 |
5 x 10-1 |
1 x 103 |
1 x 107 |
|
Te-129 |
7 x 10-1 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Te-129m (a) |
8 x 10-1 |
4 x 10-1 |
1 x 103 |
1 x 106 |
|
Te-131m (a) |
7 x 10-1 |
5 x 10-1 |
1 x 101 |
1 x 106 |
|
Te-132 (a) |
5 x 10-1 |
4 x 10-1 |
1 x 102 |
1 x 107 |
|
Thorium (90) |
||||
|
Th-227 |
1 x 101 |
5 x 10-3 |
1 x 101 |
1 x 104 |
|
Th-228 (a) |
5 x 10-1 |
1 x 10-3 |
1 x 100 (b) |
1 x 104 (b) |
|
Th-229 |
5 x 100 |
5 x 10-4 |
1 x 100 (b) |
1 x 103 (b) |
|
Th-230 |
1 x 101 |
1 x 10-3 |
1 x 100 |
1 x 104 |
|
Th-231 |
4 x 101 |
2 x 10-2 |
1 x 103 |
1 x 107 |
|
Th-232 |
Unlimited |
Unlimited |
1 x 101 |
1 x 104 |
|
Th-234 (a) |
3 x 10-1 |
3 x 10-1 |
1 x 103 (b) |
1 x 105 (b) |
|
Th (nat) |
Unlimited |
Unlimited |
1 x 100 (b) |
1 x 103 (b) |
|
Titanium (22) |
||||
|
Ti-44 (a) |
5 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
Thallium (81) |
||||
|
Tl-200 |
9 x 10-1 |
9 x 10-1 |
1 x 101 |
1 x 106 |
|
Tl-201 |
1 x 101 |
4 x 100 |
1 x 102 |
1 x 106 |
|
Tl-202 |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Tl-204 |
1 x 101 |
7 x 10-1 |
1 x 104 |
1 x 104 |
|
Thulium (69) |
||||
|
Tm-167 |
7 x 100 |
8 x 10-1 |
1 x 102 |
1 x 106 |
|
Tm-170 |
3 x 100 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Tm-171 |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 108 |
|
Uranium (92) |
||||
|
U-230 (fast lung absorption) (a)(d) |
4 x 101 |
1 x 10-1 |
1 x 101 (b) |
1 x 105 (b) |
|
U-230 (medium lung absorption) (a)(e) |
4 x 101 |
4 x 10-3 |
1 x 101 |
1 x 104 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
U-230 (slow lung absorption)) (a)(f) |
3 x 101 |
3 x 10-3 |
1 x 101 |
1 x 104 |
|
U-232 (fast lung absorption) (d) |
4 x 101 |
1 x 10-2 |
1 x 100 (b) |
1 x 103 (b) |
|
U-232 (medium lung absorption) (e) |
4 x 101 |
7 x 10-3 |
1 x 101 |
1 x 104 |
|
U-232 (slow lung absorption)) (f) |
1 x 101 |
1 x 10-3 |
1 x 101 |
1 x 104 |
|
U-233 (fast lung absorption) (d) |
4 x 101 |
9 x 10-2 |
1 x 101 |
1 x 104 |
|
U-233 (medium lung absorption) (e) |
4 x 101 |
2 x 10-2 |
1 x 102 |
1 x 105 |
|
U-233 (slow lung absorption)) (f) |
4 x 101 |
6 x 10-3 |
1 x 101 |
1 x 105 |
|
U-234 (fast lung absorption) (d) |
4 x 101 |
9 x 10-2 |
1 x 101 |
1 x 104 |
|
U-234 (medium lung absorption) (e) |
4 x 101 |
2 x 10-2 |
1 x 102 |
1 x 105 |
|
U-234 (slow lung absorption)) (f) |
4 x 101 |
6 x 10-3 |
1 x 101 |
1 x 105 |
|
U-235 (all lung absorption types) (a)(d)(e)(f) |
Unlimited |
Unlimited |
1 x 101 (b) |
1 x 104 (b) |
|
U-236 (fast lung absorption) (d) |
Unlimited |
Unlimited |
1 x 101 |
1 x 104 |
|
U-236 (medium lung absorption) (e) |
4 x 101 |
2 x 10-2 |
1 x 102 |
1 x 105 |
|
U-236 (slow lung absorption)) (f) |
4 x 101 |
6 x 10-3 |
1 x 101 |
1 x 104 |
|
U-238 (all lung absorption types) (d)(e)(f) |
Unlimited |
Unlimited |
1 x 101 (b) |
1 x 104 (b) |
|
U (nat) |
Unlimited |
Unlimited |
1 x 100 (b) |
1 x 103 (b) |
|
U (enriched to 20% or less) (g) |
Unlimited |
Unlimited |
1 x 100 |
1 x 103 |
|
U (dep) |
Unlimited |
Unlimited |
1 x 100 |
1 x 103 |
|
Vanadium (23) |
||||
|
V-48 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 105 |
|
V-49 |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 107 |
|
Tungsten (74) |
||||
|
W-178 (a) |
9 x 100 |
5 x 100 |
1 x 101 |
1 x 106 |
|
W-181 |
3 x 101 |
3 x 101 |
1 x 103 |
1 x 107 |
|
W-185 |
4 x 101 |
8 x 10-1 |
1 x 104 |
1 x 107 |
|
W-187 |
2 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
W-188 (a) |
4 x 10-1 |
3 x 10-1 |
1 x 102 |
1 x 105 |
|
Xenon (54) |
||||
|
Xe-122 (a) |
4 x 10-1 |
4 x 10-1 |
1 x 102 |
1 x 109 |
|
Xe-123 |
2 x 100 |
7 x 10-1 |
1 x 102 |
1 x 109 |
|
Xe-127 |
4 x 100 |
2 x 100 |
1 x 103 |
1 x 105 |
|
Xe-131m |
4 x 101 |
4 x 101 |
1 x 104 |
1 x 104 |
|
Xe-133 |
2 x 101 |
1 x 101 |
1 x 103 |
1 x 104 |
|
Radionuclide (atomic number) |
A1 (TBq) |
A2 (TBq) |
Activity concentration limit for exempt material (Bq/g) |
Activity limit foranexempt consignment (Bq) |
|
Xe-135 |
3 x 100 |
2 x 100 |
1 x 103 |
1 x 1010 |
|
Yttrium (39) |
||||
|
Y-87 (a) |
1 x 100 |
1 x 100 |
1 x 101 |
1 x 106 |
|
Y-88 |
4 x 10-1 |
4 x 10-1 |
1 x 101 |
1 x 106 |
|
Y-90 |
3 x 10-1 |
3 x 10-1 |
1 x 103 |
1 x 105 |
|
Y-91 |
6 x 10-1 |
6 x 10-1 |
1 x 103 |
1 x 106 |
|
Y-91m |
2 x 100 |
2 x 100 |
1 x 102 |
1 x 106 |
|
Y-92 |
2 x 10-1 |
2 x 10-1 |
1 x 102 |
1 x 105 |
|
Y-93 |
3 x 10-1 |
3 x 10-1 |
1 x 102 |
1 x 105 |
|
Ytterbium (70) |
||||
|
Yb-169 |
4 x 100 |
1 x 100 |
1 x 102 |
1 x 107 |
|
Yb-175 |
3 x 101 |
9 x 10-1 |
1 x 103 |
1 x 107 |
|
Zinc (30) |
||||
|
Zn-65 |
2 x 100 |
2 x 100 |
1 x 101 |
1 x 106 |
|
Zn-69 |
3 x 100 |
6 x 10-1 |
1 x 104 |
1 x 106 |
|
Zn-69m (a) |
3 x 100 |
6 x 10-1 |
1 x 102 |
1 x 106 |
|
Zirconium (40) |
||||
|
Zr-88 |
3 x 100 |
3 x 100 |
1 x 102 |
1 x 106 |
|
Zr-93 |
Unlimited |
Unlimited |
1 x 103 (b) |
1 x 107 (b) |
|
Zr-95 (a) |
2 x 100 |
8 x 10-1 |
1 x 101 |
1 x 106 |
|
Zr-97 (a) |
4 x 10-1 |
4 x 10-1 |
1 x 101 (b) |
1 x 105 (b) |
(a)A1and/or A2values for these parent radionuclides include contributions from their progenywith half-lives less than10 days, as listed in the following:
|
Mg-28 |
Al-28 |
|
Ar-42 |
K-42 |
|
Ca-47 |
Sc-47 |
|
Ti-44 |
Sc-44 |
|
Fe-52 |
Mn-52m |
|
Fe-60 |
Co-60m |
|
Zn-69m |
Zn-69 |
|
Ge-68 |
Ga-68 |
|
Rb-83 |
Kr-83m |
|
Sr-82 |
Rb-82 |
|
Sr-90 |
Y-90 |
|
Sr-91 |
Y-91m |
|
Sr-92 |
Y-92 |
|
Y-87 |
Sr-87m |
|
Zr-95 |
Nb-95m |
|
Zr-97 |
Nb-97m, Nb-97 |
|
Mo-99 |
Tc-99m |
|
Tc-95m |
Tc-95 |
|
Tc-96m |
Tc-96 |
|
Ru-103 |
Rh-103m |
|
Ru-106 |
Rh-106 |
|
Pd-103 |
Rh-103m |
|
Ag-108m |
Ag-108 |
|
Ag-110m |
Ag-110 |
|
Cd-115 |
In-115m |
|
In-114m |
In-114 |
|
Sn-113 |
In-113m |
|
Sn-121m |
Sn-121 |
|
Sn-126 |
Sb-126m |
|
Te-118 |
Sb-118 |
|
Te-127m |
Te-127 |
|
Te-129m |
Te-129 |
|
Te-131m |
Te-131 |
|
Te-132 |
I-132 |
|
I-135 |
Xe-135m |
|
Xe-122 |
I-122 |
|
Cs-137 |
Ba-137m |
|
Ba-131 |
Cs-131 |
|
Ba-140 |
La-140 |
|
Ce-144 |
Pr-144m, Pr-144 |
|
Pm-148m |
Pm-148 |
|
Gd-146 |
Eu-146 |
|
Dy-166 |
Ho-166 |
|
Hf-172 |
Lu-172 |
|
W-178 |
Ta-178 |
|
W-188 |
Re-188 |
|
Re-189 |
Os-189m |
|
Os-194 |
Ir-194 |
|
Ir-189 |
Os-189m |
|
Pt-188 |
Ir-188 |
|
Hg-194 |
Au-194 |
|
Hg-195m |
Hg-195 |
|
Pb-210 |
Bi-210 |
|
Pb-212 |
Bi-212, Tl-208, Po-212 |
|
Bi-210m |
Tl-206 |
|
Bi-212 |
Tl-208, Po-212 |
|
At-211 |
Po-211 |
|
Rn-222 |
Po-218, Pb-214, At-218, Bi-214, Po-214 |
|
Ra-223 |
Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207 |
|
Ra-224 |
Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 |
|
Ra-225 |
Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209 |
|
Ra-226 |
Rn-222, Po-218, Pb-214, At-218, Bi-214, Po-214 |
|
Ra-228 |
Ac-228 |
|
Ac-225 |
Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209 |
|
Ac-227 |
Fr-223 |
|
Th-228 |
Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 |
|
Th-234 |
Pa-234m, Pa-234 |
|
Pa-230 |
Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214 |
|
U-230 |
Th-226, Ra-222, Rn-218, Po-214 |
|
U-235 |
Th-231 |
|
Pu-241 |
U-237 |
|
Pu-244 |
U-240, Np-240m |
|
Am-242m |
Am-242, Np-238 |
|
Am-243 |
Np-239 |
|
Cm-247 |
Pu-243 |
|
Bk-249 |
Am-245 |
|
Cf-253 |
Cm-249 |
(b)Parent nuclides and their progeny included in secular equilibrium are listed in the following:
|
Sr-90 |
Y-90 |
|
Zr-93 |
Nb-93m |
|
Zr-97 |
Nb-97 |
|
Ru-106 |
Rh-106 |
|
Ag-108m |
Ag-108 |
|
Cs-137 |
Ba-137m |
|
Ce-144 |
Pr-144 |
|
Ba-140 |
La-140 |
|
Bi-212 |
Tl-208 (0,36), Po-212 (0,64) |
|
Pb-210 |
Bi-210, Po-210 |
|
Pb-212 |
Bi-212, Tl-208 (0,36), Po-212 (0,64) |
|
Rn-222 |
Po-218, Pb-214, Bi-214, Po-214 |
|
Ra-223 |
Rn-219, Po-215, Pb-211, Bi-211, Tl-207 |
|
Ra-224 |
Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0,36), Po-212 (0,64) |
|
Ra-226 |
Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 |
|
Ra-228 |
Ac-228 |
|
Th-228 |
Ra-224, Rn-220, Po-216, Pb212, Bi-212, Tl208 (0,36), Po-212 (0,64) |
|
Th-229 |
Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209 |
|
Th-nat |
Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, l208 (0,36), Po-212 (0,64) |
|
Th-234 |
Pa-234m |
|
U-230 |
Th-226, Ra-222, Rn-218, Po-214 |
|
U-232 |
Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0,36), Po-212 (0,64) |
|
U-235 |
Th-231 |
|
U-238 |
Th-234, Pa-234m |
|
U-nat |
Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 |
|
Np-237 |
Pa-233 |
|
Am-242m |
Am-242 |
|
Am-243 |
Np-239 |
(c) The quantity may be determined from a measurement of the rate of decay or a measurement ofthe radiation level at a prescribed distance from the source.
(d)These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2and UO2(NO3)2in both normal and accident conditions of carriage.
(e)These values apply only to compounds of uranium that take the chemical form of UO3, UF4,UCl4and hexavalent compounds in both normal and accident conditions of carriage.
(f)These values apply to all compounds of uranium other than those specified in (d) and (e)above.
(g)These values apply to unirradiated uranium only.
For individual radionuclides:
(a) Which are not listed in Table 2.2.7.2.2.1 the determination of the basic radionuclide valuesreferred to in 2.2.7.2.2.1 shall require multilateral approval. For these radionuclides, activityconcentration limits for exempt material and activity limits for exempt consignments shall becalculated in accordance with the principles established in the International Basic SafetyStandards for Protection against Ionizing Radiation and for the Safety of Radiation Sources,Safety Series No.115, IAEA, Vienna (1996). It is permissible to use an A2value calculatedusing a dose coefficient for the appropriate lung absorption type as recommended by theInternational Commission on Radiological Protection, if the chemical forms of eachradionuclide under both normal and accident conditions of carriage are taken intoconsideration. Alternatively, the radionuclide values in Table2.2.7.2.2.2 may be used withoutobtaining competent authority approval;
(b) In instruments or articles in which the radioactive material is enclosed or is included as acomponent part of the instrument or other manufactured article and which meet 2.2.7.2.4.1.3(c), alternative basicradionuclide values to those in Table 2.2.7.2.2.1 for the activity limit foran exempt consignment are permitted and shall require multilateral approval. Such alternativeactivity limits for an exempt consignment shall be calculated in accordance with theprinciplesset out in the International Basic Safety Standards for Protection against Ionizing Radiation andfor the Safety of Radiation Sources, Safety Series No.115, IAEA, Vienna (1996).
Table 2.2.7.2.2.2: Basic radionuclide values for unknown radionuclides or mixtures
|
Radioactive contents |
A1 |
A2 |
Activity |
Activity |
|
(TBq) |
(TBq) |
(Bq/g) |
(Bq) |
|
|
Only beta or gamma emitting nuclides are known to be present |
0,1 |
0,02 |
1 x 101 |
1 x 104 |
|
Alpha emitting nuclides but no neutron emitters are known to be present |
0,2 |
9 x 10-5 |
1 x 10-1 |
1 x 103 |
|
Neutron emitting nuclides are known to be present or no relevant data are available |
0,001 |
9 x 10-5 |
1 x 10-1 |
1 x 103 |
In the calculations of A1and A2for a radionuclide not in Table2.2.7.2.2.1, a single radioactive decay chain in which the radionuclides are present in their naturally occurring proportions, and in which no daughter nuclide has a half-life either longer than 10 days or longer than that of the parent nuclide, shall be considered as a single radionuclide; and the activity to be taken into account and the A1or A2value to be applied shall be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than 10 days or greater than that of the parent nuclide, the parent and such daughter nuclides shall be considered as mixtures of different nuclides.
For mixtures of radionuclides, the basic radionuclide values referred to in2.2.7.2.2.1 may be determined as follows:
where, 
f(i) is the fraction of activity or activity concentration of radionuclide i in the mixture;
X(i) is the appropriate value of A1or A2, or the activity concentration limitfor exempt material or the activity limit for an exempt consignment as appropriate for the radionuclide i; and
Xm is the derived value of A1or A2, or the activity concentration limitfor exempt material or the activity limit for an exempt consignment in the case of a mixture.
When the identity of each radionuclide is known but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest radionuclide value, as appropriate, for the radionuclides in each group may be used in applying the formulas in 2.2.7.2.2.4 and 2.2.7.2.4.4. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest radionuclide values for the alpha emitters or beta/gamma emitters, respectively.
For individual radionuclides or for mixtures of radionuclides for which relevant data are not available, the values shown in Table 2.2.7.2.2.2 shall be used.
Determination of other material characteristics
Low specific activity (LSA) material
LSA material shall be in one of three groups:
(a)LSA-I
(i)uranium and thorium ores and concentrates of such ores, and other ores containingnaturally occurring radionuclides;
(ii)natural uranium, depleted uranium, natural thorium or their compounds or mixtures, thatare unirradiated and in solid or liquid form;
(iii)radioactive material for which the A2value is unlimited. Fissile material may beincluded only if excepted under 2.2.7.2.3.5;
(iv)other radioactive material in which the activity is distributed throughout and theestimated average specific activity does not exceed 30 times the values for activityconcentration specified in 2.2.7.2.2.1 to2.2.7.2.2.6.Fissile material may be includedonly if excepted under 2.2.7.2.3.5;
(b)LSA-II
(i)water with tritium concentration up to 0.8 TBq/l;
(ii)other material in which the activity is distributed throughout and the estimated averagespecific activity does not exceed 10-4 A2/g for solids and gases, and 10-5 A2/g forliquids;
(c)LSA-III- Solids (e.g. consolidated wastes, activated materials), excluding powders, that meetthe requirementsof 2.2.7.2.3.1.3,in which:
(i)the radioactive material is distributed throughout a solid or a collection of solid objects,or is essentially uniformly distributed in a solid compact binding agent (such asconcrete, bitumen and ceramic);
(ii)the radioactive material is relatively insoluble, or it is intrinsically contained in arelatively insoluble matrix, so that, even under loss of packaging, the loss of radioactivematerial per package by leaching when placed in water for seven days would not exceed0.1 A2; and
(iii)the estimated average specific activity of the solid, excluding any shielding material,does not exceed 2×10-3 A2/g.