Management of Commercially Generated Radioactive Waste - U.S. ...

4.12
BWR fuel models that account for all radionuclides in the fuel and take into account differ-
ences in fuel exposures for PWR and BWR fuel assemblies and the effects of reduced exposure
for startup and shutdown cores.
The amounts of some selected radionuclides present in the example fuel composition are
listed in Table 4.2.2. These radionuclides were selected based on several factors, among
which are 1) potential for release, 2) potential effect of release, 3) quantity present, and
4) public interest. These nuclides and their radioactive daughter nuclides provide most of
TABLE 4.2.2. Selected Radionuclide Content in Example Once-Through Cycle Spent Fuel
Ci/GWe-yr for Various Decay Periods
Fission Products(a) 1.5 yr 5 yr (b ) 10 yr 50 yr 100 yr
3 H (1.2 x 101) 1.6 x 104 1.3 x 10 4 9.5 x 10 3 1.0 x 10 3 6.1 x 101
8 5 Kr (1.1 x 101) 3.4 x 10 5 2.7 x 105 1.9 x 105 1.5 x 10 4 6.1 x 102
90Sr (2.9 x 101) 2.5 x 10 6 2.2 x 106 2.0 x 106 7.4 x 105 2.2 x 10 5
1 0 6 Ru (1.0) 6.5 x 106 3.8 x 105 1.3 x 104
1291 (1.6 x 107) 1.3 1.3 1.3 1.3 1.3
1 34 Cs (2.1) 4.6 x 106 1.2 x 106 2.2 x 105 2.9 x 10 - 1
1 3 7 Cs (3.0 x 101) 3.5 x 106 3.2 x 10 6 2.9 x 10 6 1.1 x 10 6 3.6 x 10 5
1 4 4 Ce (7.8 x 10 - 1 ) 9.5 x 10 6 2.7 x 105 3.1 x 103
Total all Fis- 7 7 7 6 6
sion Products 5.3 x 10 1.6 x 10 1.0 x 10 3.7 x 10 1.1 x 10
Actinides a)
238U (4.5 x 109) 2 x 10 101 2 10 x 10 1 x 101 1.2 1.2 x 101 1.2 x 101
23 8 Pu (8.9 x 101) 8.0 x 104 7.9 x 10 4 7.6 x 10 4 5.6 x 10 4 3.8 x 104
2 3 9 Pu (2.4 x 104) 1.1 x 104 1.1 x 10 4 1.1 x 10 4 1.1 x 10 4 1.1 x 104
240Pu (6.8 x 103) 1.7 x 104 1.7 x 104 4 1.7 x 1 1.7 x 10 4 1.7 x 104
2 4 1 Pu (1.3 x 101) 4.2 x 106 3.4 x 106 2.6 x 106 4.1 x 105 3.8 x 103
241Am (4.6 x 102) 1.4 x 104 3.5 x 104 6.1 x 104 1.3 x 105 1.3 x 105
242Cm (4.5 x 10 - 1 ) 1.4 x 105 6.0 x 10 2 3.2 x 102 2.7 x 10 2 2.1 x 10 2
2 4 4 Cm (1.8 x 101) 4.9 x 104 4.2 x 10 4 3.4 x 104 7 x 10 3 1.1 x 103
Total All Actinides 4.5 x 106 3.6 x 10 6 2.9 x 10 6 6.3 x 105 2.4 x 105
Activation Products(a)
14 C (5.7 x 103) 2.8 x 101 2.8 x 101 2.8 x 101 2.8 x 101 2.8 x 101
5 5 1 - 7
Fe (2.4) 1.6 x 105 3.8 x 104 1.3 x 104 2.7 x 10- 4.5 x 10
6 0 4
Co (5.3) 1.6 x 105 1.1 x 105 4.0 x 10 2.6 x 103 2.8 x 10-1
6 3 4
Ni (9.2 x 101) 1.5 x 104 1.5 1.5 x 1 .5 x 10 1.3 x 10 4 7.7 x 103
Total All Activa- 5 4 4 3
tion Products 3.5 x 105 2.1 x 10 7.2 x 10 1.6 x 10 7.7 x 10
(a) Numbers in parentheses are the half-lives (in years).
(b) A minimum age of 5 yr is assumed here for shipment of spent fuel from the reactors
in the once-through cycle.