2.2.7.2 Classification - ADR 2017

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 descriptiona
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	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-exceptedb,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-exceptedb
UN 3321	RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), non fissile or fissile-exceptedb
UN 3322	RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III), non fissile or fissile-exceptedb
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-exceptedb
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- exceptedb
UN 3327	RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE, non-special form
UN 3332	RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, non fissile or fissile- exceptedb
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-exceptedb
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-exceptedb
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-exceptedb
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-exceptedb
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-exceptedb
UN 3507	URANIUM HEXAFLUORIDE, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE less than 0.1 kg per package, non-fissile or fissile-exceptedb,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.

The following basic values for individual radionuclides are given in Table 2.2.7.2.2.1:

(a) A1 and A2 in 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 for an exempt consignment (Bq)
Actinium (89)
Ac-225 (a)	8 × 10-1	6 × 10-3	1 × 101	1 × 104
Ac-227 (a)	9 × 10-1	9 × 10-5	1 × 10-1	1 × 103
Ac-228	6 × 10-1	5 × 10-1	1 × 101	1 × 106
Silver (47)
Ag-105	2 × 100	2 × 100	1 × 102	1 × 106
Ag-108m (a)	7 × 10-1	7 ×10-1	1 ×101 (b)	1 × 106 (b)
Ag-110m (a)	4 × 10-1	4 × 10-1	1 × 101	1 × 106
Ag-111	2 × 100	6 × 10-1	1 × 103	1 × 106
Aluminium (13)
Al-26	1 × 10-1	1 × 10-1	1 × 101	1 × 105
Americium (95)	1 × 10-1	1 × 10-1	1 × 101	1 × 105
Am-241	1 × 101	1 × 10-3	1 × 100	1 × 104
Am-242m (a)	1 × 101	1 × 10-3	1 × 100 (b)	1 × 104 (b)
Am-243 (a)	5 × 100	1 × 10-3	1 × 100 (b)	1 × 103 (b)
Argon (18)
Ar-37	4 × 101	4 × 101	1 × 106	1 × 108
Ar-39	4 × 101	2 × 101	1 × 107	1 × 104
Ar-41	3 × 10-1	3 × 10-1	1 × 102	1 × 109
Arsenic (33)
As-72	3 × 10-1	3 × 10-1	1 × 101	1 × 105
As-73	4 × 101	4 × 101	1 × 103	1 × 107
As-74	1 × 100	9 × 10-1	1 × 101	1 × 106
As-76	3 × 10-1	3 × 10-1	1 × 102	1 × 105
As-77	2 × 101	7 × 10-1	1 × 103	1 × 106
Astatine (85)
At-211 (a)	2 × 101	5 × 10-1	1 × 103	1 × 107

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Gold (79)
Au-193	7 × 100	2 × 100	1 × 102	1 × 107
Au-194	1 × 100	1 × 100	1 × 101	1 × 106
Au-195	1 × 101	6 × 100	1 × 102	1 × 107
Au-198	1 × 100	6 × 10-1	1 × 102	1 × 106
Au-199	1 × 101	6 × 10-1	1 × 102	1 × 106
Barium (56)
Ba-131 (a)	2 × 100	2 × 100	1 × 102	1 × 106
Ba-133	3 × 100	3 × 100	1 × 102	1 × 106
Ba-133m	2 × 101	6 × 10-1	1 × 102	1 × 106
Ba-140 (a)	5 × 10-1	3 × 10-1	1 × 101 (b)	1 × 105 (b)
Beryllium (4)
Be-7	2 × 101	2 × 101	1 × 103	1 × 107
Be-10	4 × 101	6 × 10-1	1 × 104	1 × 106
Bismuth (83)
Bi-205	7 × 10-1	7 × 10-1	1 × 101	1 × 106
Bi-206	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Bi-207	7 × 10-1	7 × 10-1	1 × 101	1 × 106
Bi-210	1 × 100	6 × 10-1	1 × 103	1 × 106
Bi-210m (a)	6 × 10-1	2 × 10-2	1 × 101	1 × 105
Bi-212 (a)	7 × 10-1	6 × 10-1	1 × 101 (b)	1 × 105 (b)
Berkelium (97)
Bk-247	8 × 100	8 × 10-4	1 × 100	1 × 104
Bk-249 (a)	4 × 101	3 × 10-1	1 × 103	1 × 106
Bromine (35)
Br-76	4 × 10-1	4 × 10-1	1 × 101	1 × 105
Br-77	3 × 100	3 × 100	1 × 102	1 × 106
Br-82	4 × 10-1	4 × 10-1	1 × 101	1 × 106
Carbon (6)
C-11	1 × 100	6 × 10-1	1 × 101	1 × 106
C-14	4 × 101	3 × 100	1 × 104	1 × 107

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Calcium (20)
Ca-41	Unlimited	Unlimited	1 × 105	1 × 107
Ca-45	4 × 101	1 × 100	1 × 104	1 × 107
Ca-47 (a)	3 × 100	3 × 10-1	1 × 101	1 × 106
Cadmium (48)
Cd-109	3 × 101	2 × 100	1 × 104	1 × 106
Cd-113m	4 × 101	5 × 10-1	1 × 103	1 × 106
Cd-115 (a)	3 × 100	4 × 10-1	1 × 102	1 × 106
Cd-115m	5 × 10-1	5 × 10-1	1 × 103	1 × 106
Cerium (58)
Ce-139	7 × 100	2 × 100	1 × 102	1 × 106
Ce-141	2 × 101	6 × 10-1	1 × 102	1 × 107
Ce-143	9 × 10-1	6 × 10-1	1 × 102	1 × 106
Ce-144 (a)	2 × 10-1	2 × 10-1	1 × 102 (b)	1 × 105 (b)
Californium (98)
Cf-248	4 × 101	6 × 10-3	1 × 101	1 × 104
Cf-249	3 × 100	8 × 10-4	1 × 100	1 × 103
Cf-250	2 × 101	2 × 10-3	1 × 101	1 × 104
Cf-251	7 × 100	7 × 10-4	1 × 100	1 × 103
Cf-252	1 × 10-1	3 × 10-3	1 × 101	1 × 104
Cf-253 (a)	4 × 101	4 × 10-2	1 × 102	1 × 105
Cf-254	1 × 10-3	1 × 10-3	1 × 100	1 × 103
Chlorine (17)
Cl-36	1 × 101	6 × 10-1	1 × 104	1 × 106
Cl-38	2 × 10-1	2 × 10-1	1 × 101	1 × 105
Curium (96)
Cm-240	4 × 101	2 × 10-2	1 × 102	1 × 105
Cm-241	2 × 100	1 × 100	1 × 102	1 × 106
Cm-242	4 × 101	1 × 10-2	1 × 102	1 × 105
Cm-243	9 × 100	1 × 10-3	1 × 100	1 × 104
Cm-244	2 × 101	2 × 10-3	1 × 101	1 × 104
Cm-245	9 × 100	9 × 10-4	1 × 100	1 × 103
Cm-246	9 × 100	9 × 10-4	1 × 100	1 × 103

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Cm-247 (a)	3 × 100	1 × 10-3	1 × 100	1 × 104
Cm-248	2 × 10-2	3 × 10-4	1 × 100	1 × 103
Cobalt (27)
Co-55	5 × 10-1	5 × 10-1	1 × 101	1 × 106
Co-56	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Co-57	1 × 101	1 × 101	1 × 102	1 × 106
Co-58	1 × 100	1 × 100	1 × 101	1 × 106
Co-58m	4 × 101	4 × 101	1 × 104	1 × 107
Co-60	4 × 10-1	4 × 10-1	1 × 101	1 × 105
Chromium (24)
Cr-51	3 × 101	3 × 101	1 × 103	1 × 107
Caesium (55)
Cs-129	4 × 100	4 × 100	1 × 102	1 × 105
Cs-131	3 × 101	3 × 101	1 × 103	1 × 106
Cs-132	1 × 100	1 × 100	1 × 101	1 × 105
Cs-134	7 × 10-1	7 × 10-1	1 × 101	1 × 104
Cs-134m	4 × 101	6 × 10-1	1 × 103	1 × 105
Cs-135	4 × 101	1 × 100	1 × 104	1 × 107
Cs-136	5 × 10-1	5 × 10-1	1 × 101	1 × 105
Cs-137 (a)	2 × 100	6 × 10-1	1 × 101 (b)	1 × 104 (b)
Copper (29)
Cu-64	6 × 100	1 × 100	1 × 102	1 × 106
Cu-67	1 × 101	7 × 10-1	1 × 102	1 × 106
Dysprosium (66)
Dy-159	2 × 101	2 × 101	1 × 103	1 × 107
Dy-165	9 × 10-1	6 × 10-1	1 × 103	1 × 106
Dy-166 (a)	9 × 10-1	3 × 10-1	1 × 103	1 × 106
Erbium (68)
Er-169	4 × 101	1 × 100	1 × 104	1 × 107
Er-171	8 × 10-1	5 × 10-1	1 × 102	1 × 106
Europium (63)
Eu-147	2 × 100	2 × 100	1 × 102	1 × 106
Eu-148	5 × 10-1	5 × 10-1	1 × 101	1 × 106

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Eu-149	2 × 101	2 × 101	1 × 102	1 × 107
Eu-150(short lived)	2 × 100	7 × 10-1	1 × 103	1 × 106
Eu-150(long lived)	7 × 10-1	7 × 10-1	1 × 101	1 × 106
Eu-152	1 × 100	1 × 100	1 × 101	1 × 106
Eu-152m	8 × 10-1	8 × 10-1	1 × 102	1 × 106
Eu-154	9 × 10-1	6 × 10-1	1 × 101	1 × 106
Eu-155	2 × 101	3 × 100	1 × 102	1 × 107
Eu-156	7 × 10-1	7 × 10-1	1 × 101	1 × 106
Fluorine (9)
F-18	1 × 100	6 × 10-1	1 × 101	1 × 106
Iron (26)
Fe-52 (a)	3 × 10-1	3 × 10-1	1 × 101	1 × 106
Fe-55	4 × 101	4 × 101	1 × 104	1 × 106
Fe-59	9 × 10-1	9 × 10-1	1 × 101	1 × 106
Fe-60 (a)	4 × 101	2 × 10-1	1 × 102	1 × 105
Gallium (31)
Ga-67	7 × 100	3 × 100	1 × 102	1 × 106
Ga-68	5 × 10-1	5 × 10-1	1 × 101	1 × 105
Ga-72	4 × 10-1	4 × 10-1	1 × 101	1 × 105
Gadolinium (64)
Gd-146 (a)	5 × 10-1	5 × 10-1	1 × 101	1 × 106
Gd-148	2 × 101	2 × 10-3	1 × 101	1 × 104
Gd-153	1 × 101	9 × 100	1 × 102	1 × 107
Gd-159	3 × 100	6 × 10-1	1 × 103	1 × 106
Germanium (32)
Ge-68 (a)	5 × 10-1	5 × 10-1	1 × 101	1 × 105
Ge-71	4 × 101	4 × 101	1 × 104	1 × 108
Ge-77	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Hafnium (72)
Hf-172 (a)	6 × 10-1	6 × 10-1	1 × 101	1 × 106
Hf-175	3 × 100	3 × 100	1 × 102	1 × 106
Hf-181	2 × 100	5 × 10-1	1 × 101	1 × 106
Hf-182	Unlimited	Unlimited	1 × 102	1 × 106

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Mercury (80)
Hg-194 (a)	1 × 100	1 × 100	1 × 101	1 × 106
Hg-195m (a)	3 × 100	7 × 10-1	1 × 102	1 × 106
Hg-197	2 × 101	1 × 101	1 × 102	1 × 107
Hg-197m	1 × 101	4 × 10-1	1 × 102	1 × 106
Hg-203	5 × 100	1 × 100	1 × 102	1 × 105
Holmium (67)
Ho-166	4 × 10-1	4 × 10-1	1 × 103	1 × 105
Ho-166m	6 × 10-1	5 × 10-1	1 × 101	1 × 106
Iodine (53)
I-123	6 × 100	3 × 100	1 × 102	1 × 107
I-124	1 × 100	1 × 100	1 × 101	1 × 106
I-125	2 × 101	3 × 100	1 × 103	1 × 106
I-126	2 × 100	1 × 100	1 × 102	1 × 106
I-129	Unlimited	Unlimited	1 ×102	1 × 105
I-131	3 × 100	7 × 10-1	1 × 102	1 × 106
I-132	4 × 10-1	4 × 10-1	1 × 101	1 × 105
I-133	7 × 10-1	6 × 10-1	1 × 101	1 × 106
I-134	3 × 10-1	3 × 10-1	1 × 101	1 × 105
I-135 (a)	6 × 10-1	6 × 10-1	1 × 101	1 × 106
Indium (49)
In-111	3 × 100	3 × 100	1 × 102	1 × 106
In-113m	4 × 100	2 × 100	1 × 102	1 × 106
In-114m (a)	1 × 101	5 × 10-1	1 × 102	1 × 106
In-115m	7 × 100	1 × 100	1 × 102	1 × 106
Iridium (77)
Ir-189 (a)	1 × 101	1 × 101	1 × 102	1 × 107
Ir-190	7 × 10-1	7 × 10-1	1 × 101	1 × 106
Ir-192	1 × 100(c)	6 × 10-1	1 × 101	1 × 104
Ir-194	3 × 10-1	3 × 10-1	1 × 102	1 × 105
Potassium (19)
K-40	9 × 10-1	9 × 10-1	1 × 102	1 × 106
K-42	2 × 10-1	2 × 10-1	1 × 102	1 × 106

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
K-43	7 × 10-1	6 × 10-1	1 × 101	1 × 106
Krypton (36)
Kr-79	4 × 100	2 × 100	1 × 103	1 × 105
Kr-81	4 × 101	4 × 101	1 × 104	1 × 107
Kr-85	1 × 101	1 × 101	1 × 105	1 × 104
Kr-85m	8 × 100	3 × 100	1 × 103	1 × 1010
Kr-87	2 × 10-1	2 × 10-1	1 × 102	1 × 109
Lanthanum (57)
La-137	3 × 101	6 × 100	1 × 103	1 × 107
La-140	4 × 10-1	4 × 10-1	1 × 101	1 × 105
Lutetium (71)
Lu-172	6 × 10-1	6 × 10-1	1 × 101	1 × 106
Lu-173	8 × 100	8 × 100	1 × 102	1 × 107
Lu-174	9 × 100	9 × 100	1 × 102	1 × 107
Lu-174m	2 × 101	1 × 101	1 × 102	1 × 107
Lu-177	3 × 101	7 × 10-1	1 × 103	1 × 107
Magnesium (12)
Mg-28 (a)	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Manganese (25)
Mn-52	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Mn-53	Unlimited	Unlimited	1 × 104	1 × 109
Mn-54	1 × 100	1 × 100	1 × 101	1 × 106
Mn-56	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Molybdenum (42)
Mo-93	4 × 101	2 × 101	1 × 103	1 × 108
Mo-99 (a)	1 × 100	6 × 10-1	1 × 102	1 × 106
Nitrogen (7)
N-13	9 × 10-1	6 × 10-1	1 × 102	1 × 109
Sodium (11)
Na-22	5 × 10-1	5 × 10-1	1 × 101	1 × 106
Na-24	2 × 10-1	2 × 10-1	1 × 101	1 × 105
Niobium (41)
Nb-93m	4 × 101	3 × 101	1 × 104	1 × 107

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Nb-94	7 × 10-1	7 × 10-1	1 × 101	1 × 106
Nb-95	1 × 100	1 × 100	1 × 101	1 × 106
Nb-97	9 × 10-1	6 × 10-1	1 × 101	1 × 106
Neodymium (60)
Nd-147	6 × 100	6 × 10-1	1 × 102	1 × 106
Nd-149	6 × 10-1	5 × 10-1	1 × 102	1 × 106
Nickel (28)
Ni-59	Unlimited	Unlimited	1 × 104	1 × 108
Ni-63	4 × 101	3 × 101	1 × 105	1 × 108
Ni-65	4 × 10-1	4 × 10-1	1 × 101	1 × 106
Neptunium (93)
Np-235	4 × 101	4 × 101	1 × 103	1 × 107
Np-236(short-lived)	2 × 101	2 × 100	1 × 103	1 × 107
Np-236(long-lived)	9 × 100	2 × 10-2	1 × 102	1 × 105
Np-237	2 × 101	2 × 10-3	1 × 100 (b)	1 × 103 (b)
Np-239	7 × 100	4 × 10-1	1 × 102	1 × 107
Osmium (76)
Os-185	1 × 100	1 × 100	1 × 101	1 × 106
Os-191	1 × 101	2 × 100	1 × 102	1 × 107
Os-191m	4 × 101	3 × 101	1 × 103	1 × 107
Os-193	2 × 100	6 × 10-1	1 × 102	1 × 106
Os-194 (a)	3 × 10-1	3 × 10-1	1 × 102	1 × 105
Phosphorus (15)
P-32	5 × 10-1	5 × 10-1	1 × 103	1 × 105
P-33	4 × 101	1 × 100	1 × 105	1 × 108
Protactinium (91)
Pa-230 (a)	2 × 100	7 × 10-2	1 × 101	1 × 106
Pa-231	4 × 100	4 × 10-4	1 × 100	1 × 103
Pa-233	5 × 100	7 × 10-1	1 × 102	1 × 107
Lead (82)
Pb-201	1 × 100	1 × 100	1 × 101	1 × 106
Pb-202	4 × 101	2 × 101	1 × 103	1 × 106
Pb-203	4 × 100	3 × 100	1 × 102	1 × 106

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Pb-205	Unlimited	Unlimited	1 × 104	1 × 107
Pb-210 (a)	1 × 100	5 × 10-2	1 × 101 (b)	1 × 104 (b)
Pb-212 (a)	7 × 10-1	2 × 10-1	1 × 101 (b)	1 × 105 (b)
Palladium (46)
Pd-103 (a)	4 × 101	4 × 101	1 × 103	1 × 108
Pd-107	Unlimited	Unlimited	1 × 105	1 × 108
Pd-109	2 × 100	5 × 10-1	1 × 103	1 × 106
Promethium (61)
Pm-143	3 × 100	3 × 100	1 × 102	1 × 106
Pm-144	7 × 10-1	7 × 10-1	1 × 101	1 × 106
Pm-145	3 × 101	1 × 101	1 × 103	1 × 107
Pm-147	4 × 101	2 × 100	1 × 104	1 × 107
Pm-148m (a)	8 × 10-1	7 × 10-1	1 × 101	1 × 106
Pm-149	2 × 100	6 × 10-1	1 × 103	1 × 106
Pm-151	2 × 100	6 × 10-1	1 × 102	1 × 106
Polonium (84)
Po-210	4 × 101	2 × 10-2	1 × 101	1 × 104
Praseodymium (59)
Pr-142	4 × 10-1	4 × 10-1	1 × 102	1 × 105
Pr-143	3 × 100	6 × 10-1	1 × 104	1 × 106
Platinum (78)
Pt-188 (a)	1 × 100	8 × 10-1	1 × 101	1 × 106
Pt-191	4 × 100	3 × 100	1 × 102	1 × 106
Pt-193	4 × 101	4 × 101	1 × 104	1 × 107
Pt-193m	4 × 101	5 × 10-1	1 × 103	1 × 107
Pt-195m	1 × 101	5 × 10-1	1 × 102	1 × 106
Pt-197	2 × 101	6 × 10-1	1 × 103	1 × 106
Pt-197m	1 × 101	6 × 10-1	1 × 102	1 × 106
Plutonium (94)
Pu-236	3 × 101	3 × 10-3	1 × 101	1 × 104
Pu-237	2 × 101	2 × 101	1 × 103	1 × 107
Pu-238	1 × 101	1 × 10-3	1 × 100	1 × 104
Pu-239	1 × 101	1 × 10-3	1 × 100	1 × 104

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Pu-240	1 × 101	1 × 10-3	1 × 100	1 × 103
Pu-241 (a)	4 × 101	6 × 10-2	1 × 102	1 × 105
Pu-242	1 × 101	1 × 10-3	1 × 100	1 × 104
Pu-244 (a)	4 × 10-1	1 × 10-3	1 × 100	1 × 104
Radium (88)
Ra-223 (a)	4 × 10-1	7 × 10-3	1 × 102 (b)	1 × 105 (b)
Ra-224 (a)	4 × 10-1	2 × 10-2	1 × 101 (b)	1 × 105 (b)
Ra-225 (a)	2 × 10-1	4 × 10-3	1 × 102	1 × 105
Ra-226 (a)	2 × 10-1	3 × 10-3	1 × 101 (b)	1 × 104 (b)
Ra-228 (a)	6 × 10-1	2 × 10-2	1 × 101 (b)	1 × 105 (b)
Rubidium (37)
Rb-81	2 × 100	8 × 10-1	1 × 101	1 × 106
Rb-83 (a)	2 × 100	2 × 100	1 × 102	1 × 106
Rb-84	1 × 100	1 × 100	1 × 101	1 × 106
Rb-86	5 × 10-1	5 × 10-1	1 × 102	1 × 105
Rb-87	Unlimited	Unlimited	1 × 104	1 × 107
Rb(nat)	Unlimited	Unlimited	1 × 104	1 × 107
Rhenium (75)
Re-184	1 × 100	1 × 100	1 × 101	1 × 106
Re-184m	3 × 100	1 × 100	1 × 102	1 × 106
Re-186	2 × 100	6 × 10-1	1 × 103	1 × 106
Re-187	Unlimited	Unlimited	1 × 106	1 × 109
Re-188	4 × 10-1	4 × 10-1	1 × 102	1 × 105
Re-189 (a)	3 × 100	6 × 10-1	1 × 102	1 × 106
Re(nat)	Unlimited	Unlimited	1 × 106	1 × 109
Rhodium (45)
Rh-99	2 × 100	2 × 100	1 × 101	1 × 106
Rh-101	4 × 100	3 × 100	1 × 102	1 × 107
Rh-102	5 × 10-1	5 × 10-1	1 × 101	1 × 106
Rh-102m	2 × 100	2 × 100	1 × 102	1 × 106
Rh-103m	4 × 101	4 × 101	1 × 104	1 × 108
Rh-105	1 × 101	8 × 10-1	1 × 102	1 × 107
Radon (86)

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Rn-222 (a)	3 × 10-1	4 × 10-3	1 × 101 (b)	1 × 108 (b)
Ruthenium (44)
Ru-97	5 × 100	5 × 100	1 × 102	1 × 107
Ru-103 (a)	2 × 100	2 × 100	1 × 102	1 × 106
Ru-105	1 × 100	6 × 10-1	1 × 101	1 × 106
Ru-106 (a)	2 × 10-1	2 × 10-1	1 × 102 (b)	1 × 105 (b)
Sulphur (16)
S-35	4 × 101	3 × 100	1 × 105	1 × 108
Antimony (51)
Sb-122	4 × 10-1	4 × 10-1	1 × 102	1 × 104
Sb-124	6 × 10-1	6 × 10-1	1 × 101	1 × 106
Sb-125	2 × 100	1 × 100	1 × 102	1 × 106
Sb-126	4 × 10-1	4 × 10-1	1 × 101	1 × 105
Scandium (21)
Sc-44	5 × 10-1	5 × 10-1	1 × 101	1 × 105
Sc-46	5 × 10-1	5 × 10-1	1 × 101	1 × 106
Sc-47	1 × 101	7 × 10-1	1 × 102	1 × 106
Sc-48	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Selenium (34)
Se-75	3 × 100	3 × 100	1 × 102	1 × 106
Se-79	4 × 101	2 × 100	1 × 104	1 × 107
Silicon (14)
Si-31	6 × 10-1	6 × 10-1	1 × 103	1 × 106
Si-32	4 × 101	5 × 10-1	1 × 103	1 × 106
Samarium (62)
Sm-145	1 × 101	1 × 101	1 × 102	1 × 107
Sm-147	Unlimited	Unlimited	1 × 101	1 × 104
Sm-151	4 × 101	1 × 101	1 × 104	1 × 108
Sm-153	9 × 100	6 × 10-1	1 × 102	1 × 106
Tin (50)
Sn-113 (a)	4 × 100	2 × 100	1 × 103	1 × 107
Sn-117m	7 × 100	4 × 10-1	1 × 102	1 × 106
Sn-119m	4 × 101	3 × 101	1 × 103	1 × 107

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Sn-121m (a)	4 × 101	9 × 10-1	1 × 103	1 × 107
Sn-123	8 × 10-1	6 × 10-1	1 × 103	1 × 106
Sn-125	4 × 10-1	4 × 10-1	1 × 102	1 × 105
Sn-126 (a)	6 × 10-1	4 × 10-1	1 × 101	1 × 105
Strontium (38)
Sr-82 (a)	2 × 10-1	2 × 10-1	1 × 101	1 × 105
Sr-85	2 × 100	2 × 100	1 × 102	1 × 106
Sr-85m	5 × 100	5 × 100	1 × 102	1 × 107
Sr-87m	3 × 100	3 × 100	1 × 102	1 × 106
Sr-89	6 × 10-1	6 × 10-1	1 × 103	1 × 106
Sr-90 (a)	3 × 10-1	3 × 10-1	1 × 102 (b)	1 × 104 (b)
Sr-91 (a)	3 × 10-1	3 × 10-1	1 × 101	1 × 105
Sr-92 (a)	1 × 100	3 × 10-1	1 × 101	1 × 106
Tritium (1)
T(H-3)	4 × 101	4 × 101	1 × 106	1 × 109
Tantalum (73)
Ta-178(long-lived)	1 × 100	8 × 10-1	1 × 101	1 × 106
Ta-179	3 × 101	3 × 101	1 × 103	1 × 107
Ta-182	9 × 10-1	5 × 10-1	1 × 101	1 × 104
Terbium (65)
Tb-157	4 × 101	4 × 101	1 × 104	1 × 107
Tb-158	1 × 100	1 × 100	1 × 101	1 × 106
Tb-160	1 × 100	6 × 10-1	1 × 101	1 × 106
Technetium (43)
Tc-95m (a)	2 × 100	2 × 100	1 × 101	1 × 106
Tc-96	4 × 10-1	4 × 10-1	1 × 101	1 × 106
Tc-96m (a)	4 × 10-1	4 × 10-1	1 × 103	1 × 107
Tc-97	Unlimited	Unlimited	1 × 103	1 × 108
Tc-97m	4 × 101	1 × 100	1 × 103	1 × 107
Tc-98	8 × 10-1	7 × 10-1	1 × 101	1 × 106
Tc-99	4 × 101	9 × 10-1	1 × 104	1 × 107
Tc-99m	1 × 101	4 × 100	1 × 102	1 × 107
Tellurium (52)

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Te-121	2 × 100	2 × 100	1 × 101	1 × 106
Te-121m	5 × 100	3 × 100	1 × 102	1 × 106
Te-123m	8 × 100	1 × 100	1 × 102	1 × 107
Te-125m	2 × 101	9 × 10-1	1 × 103	1 × 107
Te-127	2 × 101	7 × 10-1	1 × 103	1 × 106
Te-127m (a)	2 × 101	5 × 10-1	1 × 103	1 × 107
Te-129	7 × 10-1	6 × 10-1	1 × 102	1 × 106
Te-129m (a)	8 × 10-1	4 × 10-1	1 × 103	1 × 106
Te-131m (a)	7 × 10-1	5 × 10-1	1 × 101	1 × 106
Te-132 (a)	5 × 10-1	4 × 10-1	1 × 102	1 × 107
Thorium (90)
Th-227	1 × 101	5 × 10-3	1 × 101	1 × 104
Th-228 (a)	5 × 10-1	1 × 10-3	1 × 100 (b)	1 × 104 (b)
Th-229	5 × 100	5 × 10-4	1 × 100 (b)	1 × 103 (b)
Th-230	1 × 101	1 × 10-3	1 × 100	1 × 104
Th-231	4 × 101	2 × 10-2	1 × 103	1 × 107
Th-232	Unlimited	Unlimited	1 × 101	1 × 104
Th-234 (a)	3 × 10-1	3 × 10-1	1 × 103 (b)	1 × 105 (b)
Th(nat)	Unlimited	Unlimited	1 × 100 (b)	1 × 103 (b)
Titanium (22)
Ti-44 (a)	5 × 10-1	4 × 10-1	1 × 101	1 × 105
Thallium (81)
Tl-200	9 × 10-1	9 × 10-1	1 × 101	1 × 106
Tl-201	1 × 101	4 × 100	1 × 102	1 × 106
Tl-202	2 × 100	2 × 100	1 × 102	1 × 106
Tl-204	1 × 101	7 × 10-1	1 × 104	1 × 104
Thulium (69)
Tm-167	7 × 100	8 × 10-1	1 × 102	1 × 106
Tm-170	3 × 100	6 × 10-1	1 × 103	1 × 106
Tm-171	4 × 101	4 × 101	1 × 104	1 × 108
Uranium (92)
U-230 (fast lung absorption) (a)(d)	4 × 101	1 × 10-1	1 × 101 (b)	1 × 105 (b)
U-230 (medium lung absorption) (a)(e)	4 × 101	4 × 10-3	1 × 101	1 × 104

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
U-230 (slow lung absorption) (a)(f)	3 × 101	3 × 10-3	1 × 101	1 × 104
U-232 (fast lung absorption) (d)	4 × 101	1 × 10-2	1 × 100 (b)	1 × 103 (b)
U-232 (medium lung absorption) (e)	4 × 101	7 × 10-3	1 × 101	1 × 104
U-232 (slow lung absorption) (f)	1 × 101	1 × 10-3	1 × 101	1 × 104
U-233 (fast lung absorption) (d)	4 × 101	9 × 10-2	1 × 101	1 × 104
U-233 (medium lung absorption) (e)	4 × 101	2 × 10-2	1 × 102	1 × 105
U-233 (slow lung absorption) (f)	4 × 101	6 × 10-3	1 × 101	1 × 105
U-234 (fast lung absorption) (d)	4 × 101	9 × 10-2	1 × 101	1 × 104
U-234 (medium lung absorption) (e)	4 × 101	2 × 10-2	1 × 102	1 × 105
U-234 (slow lung absorption) (f)	4 × 101	6 × 10-3	1 × 101	1 × 105
U-235 (all lung absorption types) (a)(d)(e)(f)	Unlimited	Unlimited	1 × 101 (b)	1 × 104 (b)
U-236 (fast lung absorption) (d)	Unlimited	Unlimited	1 × 101	1 × 104
U-236 (medium lung absorption) (e)	4 × 101	2 × 10-2	1 × 102	1 × 105
U-236 (slow lung absorption) (f)	4 × 101	6 × 10-3	1 × 101	1 × 104
U-238 (all lung absorption types) (d)(e)(f)	Unlimited	Unlimited	1 × 101 (b)	1 × 104 (b)
U (nat)	Unlimited	Unlimited	1 × 100 (b)	1 × 103 (b)
U (enriched to 20% or less) (g)	Unlimited	Unlimited	1 × 100	1 × 103
U (dep)	Unlimited	Unlimited	1 × 100	1 × 103
Vanadium (23)
V-48	4 × 10-1	4 × 10-1	1 × 101	1 × 105
V-49	4 × 101	4 × 101	1 × 104	1 × 107
Tungsten (74)
W-178 (a)	9 × 100	5 × 100	1 × 101	1 × 106
W-181	3 × 101	3 × 101	1 × 103	1 × 107
W-185	4 × 101	8 × 10-1	1 × 104	1 × 107
W-187	2 × 100	6 × 10-1	1 × 102	1 × 106
W-188 (a)	4 × 10-1	3 × 10-1	1 × 102	1 × 105
Xenon (54)
Xe-122 (a)	4 × 10-1	4 × 10-1	1 × 102	1 × 109
Xe-123	2 × 100	7 × 10-1	1 × 102	1 × 109
Xe-127	4 × 100	2 × 100	1 × 103	1 × 105
Xe-131m	4 × 101	4 × 101	1 × 104	1 × 104
Xe-133	2 × 101	1 × 101	1 × 103	1 × 104

Radionuclide (atomic number)	A1 (TBq)	A2 (TBq)	Activity concentration limit for exempt material (Bq/g)	Activity limit for an exempt consignment (Bq)
Xe-135	3 × 100	2 × 100	1 × 103	1 × 1010
Yttrium (39)
Y-87 (a)	1 × 100	1 × 100	1 × 101	1 × 106
Y-88	4 × 10-1	4 × 10-1	1 × 101	1 × 106
Y-90	3 × 10-1	3 × 10-1	1 × 103	1 × 105
Y-91	6 × 10-1	6 × 10-1	1 × 103	1 × 106
Y-91m	2 × 100	2 × 100	1 × 102	1 × 106
Y-92	2 × 10-1	2 × 10-1	1 × 102	1 × 105
Y-93	3 × 10-1	3 × 10-1	1 × 102	1 × 105
Ytterbium (70)
Yb-169	4 × 100	1 × 100	1 × 102	1 × 107
Yb-175	3 × 101	9 × 10-1	1 × 103	1 × 107
Zinc (30)
Zn-65	2 × 100	2 × 100	1 × 101	1 × 106
Zn-69	3 × 100	6 × 10-1	1 × 104	1 × 106
Zn-69m (a)	3 × 100	6 × 10-1	1 × 102	1 × 106
Zirconium (40)
Zr-88	3 × 100	3 × 100	1 × 102	1 × 106
Zr-93	Unlimited	Unlimited	1 × 103 (b)	1 × 107 (b)
Zr-95 (a)	2 × 100	8 × 10-1	1 × 101	1 × 106
Zr-97 (a)	4 × 10-1	4 × 10-1	1 × 101 (b)	1 × 105 (b)

(a) A1 and/or A2 values for these parent radionuclides include contributions from their progeny

with half-lives less than 10 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 of

the 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, UO2F2

and UO2(NO3)2 in both normal and accident conditions of carriage.

(e) These values apply only to compounds of uranium that take the chemical form of UO3, UF4,

UCl4 and 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 values

referred to in 2.2.7.2.2.1 shall require multilateral approval. For these radionuclides, activity

concentration limits for exempt material and activity limits for exempt consignments shall be

calculated in accordance with the principles established in the International Basic Safety

Standards 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 A2 value calculated

using a dose coefficient for the appropriate lung absorption type as recommended by the

International Commission on Radiological Protection, if the chemical forms of each

radionuclide under both normal and accident conditions of carriage are taken into

consideration. Alternatively, the radionuclide values in Table 2.2.7.2.2.2 may be used without

obtaining competent authority approval;

(b) In instruments or articles in which the radioactive material is enclosed or is included as a

component part of the instrument or other manufactured article and which meet 2.2.7.2.4.1.3

(c), alternative basic radionuclide values to those in Table 2.2.7.2.2.1 for the activity limit for

an exempt consignment are permitted and shall require multilateral approval. Such alternative

activity limits for an exempt consignment shall be calculated in accordance with the principles

set out in the International Basic Safety Standards for Protection against Ionizing Radiation and

for 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 concentration limit for exempt material	Activity limit for exempt consignments
	(TBq)	(TBq)	(Bq/g)	(Bq)
Only beta or gamma emitting nuclides are known to be present	0.1	0.02	1  101	1  104
Alpha emitting nuclides but no neutron emitters are known to be present	0.2	9  10-5	1  10-1	1  103
Neutron emitting nuclides are known to be present or no relevant data are available	0.001	9  10-5	1  10-1	1  103

In the calculations of A1 and A2 for a radionuclide not in Table 2.2.7.2.2.1, 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 A1 or A2

value 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 in 2.2.7.2.2.1 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 A1 or A2, or the activity concentration limit for exempt material or

the activity limit for an exempt consignment as appropriate for the radionuclide i; and

Xm is the derived value of A1 or A2, or the activity concentration limit for 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.

(Reserved)

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 containing

naturally occurring radionuclides;

(ii) natural uranium, depleted uranium, natural thorium or their compounds or mixtures, that

are unirradiated and in solid or liquid form;

(iii) radioactive material for which the A2 value is unlimited. Fissile material may be

included only if excepted under 2.2.7.2.3.5;

(iv) other radioactive material in which the activity is distributed throughout and the

estimated average specific activity does not exceed 30 times the values for activity

concentration specified in 2.2.7.2.2.1 to 2.2.7.2.2.6. Fissile material may be included

only 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 average

specific activity does not exceed 10-4 A2/g for solids and gases, and 10-5 A2/g for

liquids;

(c) LSA-III - Solids (e.g. consolidated wastes, activated materials), excluding powders, that meet

the requirements of 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 as

concrete, bitumen and ceramic);

(ii) the radioactive material is relatively insoluble, or it is intrinsically contained in a

relatively insoluble matrix, so that, even under loss of packaging, the loss of radioactive

material per package by leaching when placed in water for seven days would not exceed

0.1 A2; and

(iii) the estimated average specific activity of the solid, excluding any shielding material,

does not exceed 2 × 10-3 A2/g.

LSA-III material shall be a solid of such a nature that if the entire contents of a package were

subjected to the test specified in 2.2.7.2.3.1.4 the activity in the water would not exceed 0.1 A2.

2.2.7.2

Classification

2.2.7.2.1

General provisions

2.2.7.2.1.1

2.2.7.2.2

Determination of basic radionuclide values

2.2.7.2.2.1

2.2.7.2.2.2

2.2.7.2.2.3

2.2.7.2.2.4

2.2.7.2.2.5

2.2.7.2.2.6

2.2.7.2.3

Determination of other material characteristics

2.2.7.2.3.1

Low specific activity (LSA) material

2.2.7.2.3.1.1

2.2.7.2.3.1.2

2.2.7.2.3.1.3