nureg/cr-6700 - Oak Ridge National Laboratory

LIST OF FIGURES
Figure Page
1 Historical and projected LWR spent fuel discharge burnup .................................................................... 4
2 Absorption fractions for 5-wt % PWR fuel as a function of burnup...................................................... 10
3 Fraction of total neutron absorptions from actinides for 5-wt % PWR fuel,
5-year cooling ........................................................................................................................................ 12
4 Fraction of total neutron absorptions from actinides for 5-wt % PWR fuel,
100-year cooling .................................................................................................................................... 13
5 Fraction of total neutron absorptions from fission products for 5-wt % PWR fuel,
5-year cooling ........................................................................................................................................ 14
6 Fraction of total neutron absorptions from fission products for 5-wt % PWR fuel,
100-year cooling..................................................................................................................................... 15
7 Decay-heat-rate profiles for 5-wt % 235 U PWR fuel, 5-year cooling ..................................................... 24
8 Decay-heat-rate profiles for 5-wt % 235 U PWR fuel, 100-year cooling ................................................. 25
9 Fraction of decay-heat generation for 5-wt % 235 U PWR fuel, 5-year cooling...................................... 27
10 Fraction of decay-heat generation for 5-wt % 235 U PWR fuel, 100-year cooling.................................. 28
11 Neutron dose rates for steel cask with 5-wt % PWR fuel ......................................................................32
12 Gamma dose rates for steel cask with 5-wt % PWR fuel....................................................................... 33
13 Relative contribution of neutrons to the total dose rate for 5-wt % PWR fuel,
concrete storage cask.............................................................................................................................. 34
14 Relative contribution of neutrons to the total dose rate for 5-wt % PWR fuel,
steel transport cask................................................................................................................................. 35
15 Relative contribution of neutrons to the total dose rate for 5-wt % PWR fuel,
lead cask................................................................................................................................................. 36
16 Contribution of (α,n) and spontaneous fission neutron sources for 5-wt % PWR fuel,
5-year cooling......................................................................................................................................... 37
17 Contribution of (α,n) and spontaneous fission neutron sources for 5-wt % PWR fuel,
100-year cooling..................................................................................................................................... 38
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