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

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7.32<br />

fuel, 4) the long time for spent recycle fuel to work its way through the inventory to<br />

reprocessing, and 5) the year 2040 cut<strong>of</strong>f date for this analysis. No third-recycle fuel is<br />

irradiated in the Year 2010 reprocessing case. The same effect is noted in Case 4 and<br />

Case 5. We calculate that at equilibrium, 4 MT <strong>of</strong> third-recycle plutonium would be dis-<br />

charged for each 1,000 MT <strong>of</strong> equilibrium plus recycle reload fuel charged (equilibrium<br />

reload fuel accounts for approximately 80% <strong>of</strong> the total fuel). Thus, for Case 3 for<br />

example, where 239,000 MT <strong>of</strong> fuel are charged, the eventual implied commitment for third-<br />

recycle plutonium disposal is approximately 780 MT.<br />

7.3.8 Radioactivity Inventory in Disposal Repositories<br />

The total radioactivity and the total heat output from the entire inventory <strong>of</strong> all<br />

wastes sent to disposal from the entire system are summarized in Tables 7.3.13 through<br />

7.3.16. These tables show the activity and heat output from year 2070 at periodic intervals<br />

for the next 1 million years for each <strong>of</strong> the nuclear growth cases. By the year 2070, all<br />

wastes have been placed in the repositories and much <strong>of</strong> the shorter life activities have<br />

decayed to low levels. Detailed tables showing the breakdown <strong>of</strong> radioactivity and heat out-<br />

put by individual nuclides are included in Appendix A.2 and A.3.<br />

Table 7.3.13 shows the radioactivity inventory for all the fission and activation pro-<br />

ducts. The radioactivity here is roughly proportional to the total energy produced in each<br />

case (see Table 7.1.1). The fission and activation product inventory for the reprocessing<br />

cases is closely similar to the fission and activation product inventory for the once-<br />

through cases.<br />

Table 7.3.14 summarizes the total radioactivity inventory for all <strong>of</strong> the actinides and<br />

their daughter nuclides. The activity inventories in the once-through cases are roughly<br />

proportional to the energy generated in each case. This is also true for the reprocessing<br />

cases. However, the actinide inventories for comparable reprocessing and once-through cases<br />

are substantially different. The actinide activity initially is much higher with the once-<br />

through cycle wastes. This is because these wastes contain all <strong>of</strong> the plutonium present in<br />

the spent fuel. However, the recycle wastes contain a much higher level <strong>of</strong> the higher<br />

actinides--americum, curium, etc. Thus, the difference in total actinide activity inven-<br />

tories is not as large as one might expect based just on the plutonium content, and the dif-<br />

ferences become smaller in later years. Reprocessing Case 3 shows that the reprocessing<br />

date significantly effects the total actinide activity inventory in the wastes.<br />

Table 7.3.15 shows total heat output for the fission and activation products and<br />

Table 7.3.16 shows heat output for the actinides and their daughter nuclides. These tables<br />

show that in all cases, the heat output is dominated by the actinides after the first<br />

500 years.<br />

Comparisons <strong>of</strong> the toxicity <strong>of</strong> radioactive wastes on the basis <strong>of</strong> hazard indices is<br />

discussed in Section 3.4. The relative toxicities <strong>of</strong> the once-through cycle and

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