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.
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.
LSA-III material shall be tested as follows:
A solid material sample representing the entire contents of the package shall be immersed for 7days in water at ambient temperature. The volume of water to be used in the test shall be sufficient to ensure that at the end of the7 day test period the free volume of the unabsorbed and unreacted water remaining shall be at least 10% of the volume of the solid test sample itself. The water shall have an initial pH of 6-8 and a maximum conductivity of 1mS/m at 20°C. The total activity of the free volume of water shall be measured following the 7 day immersion of the test sample.
Demonstration of compliance with the performance standards in2.2.7.2.3.1.4 shallbe in accordance with6.4.12.1 and 6.4.12.2.
Surface contaminated object (SCO)
SCO is classified in one of two groups:
(a)SCO-I: A solid object on which:
(i)the non-fixed contamination on the accessible surface averaged over 300cm2(or thearea of the surface if less than 300 cm2) does not exceed 4Bq/cm2for beta and gammaemitters and low toxicity alpha emitters, or 0.4 Bq/cm2for all other alpha emitters; and
(ii)the fixed contamination on the accessible surface averaged over 300cm2(or the area ofthe surface if less than 300 cm2) does not exceed 4 ×104Bq/cm2for beta and gammaemitters and low toxicity alpha emitters, or 4 ×103Bq/cm2for all other alpha emitters;and
(iii)the non-fixed contamination plus the fixed contamination on the inaccessible surfaceaveraged over 300 cm2(or the area of the surface if less than 300 cm2) does not exceed4 ×104Bq/cm2for beta and gamma emitters and low toxicity alpha emitters, or4 ×103Bq/cm2for all other alpha emitters;
(b)SCO-II: A solid object on which either the fixed or non-fixed contamination on the surfaceexceeds the applicable limits specified for SCO-I in (a) above and on which:
(i)the non-fixed contamination on the accessible surface averaged over 300cm2(or thearea of the surface if less than 300 cm2) does not exceed 400Bq/cm2for beta andgamma emitters and low toxicity alpha emitters, or 40 Bq/cm2for all other alphaemitters; and
(ii)the fixed contamination on the accessible surface, averaged over 300cm2(or the area ofthe surface if less than 300 cm2) does not exceed 8 ×105Bq/cm2for beta and gammaemitters and low toxicity alpha emitters, or 8×104Bq/cm2for all other alpha emitters;and
(iii)the non-fixed contamination plus the fixed contamination on the inaccessible surfaceaveraged over 300 cm2(or the area of the surface if less than 300 cm2) does not exceed8 ×105Bq/cm2for beta and gamma emitters and low toxicity alpha emitters, or8 ×104Bq/cm2for all other alpha emitters.
Special form radioactive material
Special form radioactive material shall have at least one dimension not less than 5mm. When a sealed capsule constitutes part of the special form radioactive material, the capsule shall be so manufactured that it can be opened only by destroying it.The design for special form radioactive material requires unilateral approval.
Special form radioactive material shall be of such a nature or shall be so designed that if it is subjected to the tests specified in 2.2.7.2.3.3.4 to 2.2.7.2.3.3.8, it shall meet the following requirements:
(a)It would not break or shatter under the impact, percussion and bending tests2.2.7.2.3.3.5(a),(b),(c) and 2.2.7.2.3.3.6(a) as applicable;
(b)It would not melt or disperse in the applicable heat test 2.2.7.2.3.3.5(d) or 2.2.7.2.3.3.6(b) asapplicable; and
(c)The activity in the water from the leaching tests specified in 2.2.7.2.3.3.7 and 2.2.7.2.3.3.8would not exceed 2 kBq; or alternatively for sealed sources, the leakage rate for the volumetricleakage assessment test specified inISO9978:1992 "Radiation Protection - Sealed RadioactiveSources - Leakage Test Methods", would not exceed the applicable acceptance thresholdacceptable to the competent authority.
Demonstration of compliance with the performance standards in2.2.7.2.3.3.2 shall be in accordance with6.4.12.1 and 6.4.12.2.
Specimens that comprise or simulate special form radioactive material shall be subjected to the impact test, the percussion test, the bending test, and the heat test specified in2.2.7.2.3.3.5 or alternative tests as authorized in2.2.7.2.3.3.6. A different specimen may be used for each of the tests. Following each test, a leaching assessment or volumetric leakage test shall be performed on the specimen by a method no less sensitive than the methods given in 2.2.7.2.3.3.7 for indispersible solid material or 2.2.7.2.3.3.8 for encapsulated material.