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

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E 400<br />

7.17<br />

DCASE 5<br />

S/ CASE 4<br />

S300<br />

z 200 S2000 REPOSITORY<br />

o STARTUP<br />

:-<br />

0<br />

100<br />

S2020 REPOSITORY<br />

_- STARTUP<br />

2000 2010 2020 2030 2040 2050 2070<br />

YEAR<br />

FIGURE 7.3.7. Repository High-Level <strong>Waste</strong> Inventory Accumulation for<br />

Cases 4 and 5 with Reprocessing<br />

TABLE 7.3.la. Number <strong>of</strong> Spent Fuel Canisters Sent to Disposal in the Once-Through Cycle<br />

Thousands <strong>of</strong> Containers<br />

Proposed Program Alternative Program<br />

Nuclear Power (Geologic Disposal (Disposal Starting No-Action<br />

Case Growth Assumption Starting 1990 - 2010) 2010 - 2030) Alternative<br />

1 Present Inventory<br />

Only 35.6 35.6 0<br />

2 Present Capacity and<br />

Normal Life 165 165 0<br />

3 250 GWe System by<br />

Year 2000 and Normal<br />

Life 808 808 0<br />

4 250 GWe system by<br />

Year 2000 and<br />

Steady State 1,070 1,070 NA(a)<br />

5 500 GWe system by<br />

Year 2040 1,440 1,440 NA<br />

(a) NA = not applicable.<br />

alternative program and since we assumed that each fuel assembly would be encapsulated indi-<br />

vidually for this analysis, the number <strong>of</strong> canisters is the same for both major alternatives.<br />

The total number <strong>of</strong> waste containers sent to disposal with the reprocessing cycle is<br />

shown in Table 7.3.1b (see Sections 4.3.2 and 4.3.3 for container descriptions). The range<br />

<strong>of</strong> numbers <strong>of</strong> high-level waste containers results from variations in the allowable heat

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