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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Section 5<br />
Radiation Shielding<br />
Neutron Source (n/s/arbitrary unit)<br />
3<br />
2.5<br />
2<br />
1.5<br />
1<br />
0.5<br />
Alpha,n<br />
Spontaneous fission<br />
Total neutron<br />
0<br />
0 20 40 60 80<br />
Burnup (GWd/t)<br />
Figure 16 Contribution of (α,n) and spontaneous fission neutron sources for 5-wt % PWR fuel,<br />
5-year cooling<br />
37
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