nureg/cr-6700 - Oak Ridge National Laboratory
nureg/cr-6700 - Oak Ridge National Laboratory
nureg/cr-6700 - Oak Ridge National Laboratory
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Radiation Shielding Section 5<br />
1<br />
Relative Spontaneous Fission Source<br />
0.1<br />
0.01<br />
cm244<br />
cf252<br />
cm246<br />
pu240<br />
pu242<br />
pu238<br />
cm248<br />
cf250<br />
cm242<br />
u238<br />
0.001<br />
0 20 40 60 80<br />
Burnup (GWd/t)<br />
Figure 20 Relative importance of the dominant spontaneous fission actinides for 5-wt % PWR fuel,<br />
5-year cooling<br />
42