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 />
Neutron Source (n/s/arbitrary unit)<br />
0.14<br />
0.12<br />
0.1<br />
0.08<br />
0.06<br />
0.04<br />
Alpha,n<br />
Spontaneous fission<br />
Total neutron<br />
0.02<br />
0<br />
0 20 40 60 80<br />
Burnup (GWd/t)<br />
Figure 17 Contribution of (α,n) and spontaneous fission neutron sources for 5-wt % PWR fuel,<br />
100-year cooling<br />
38