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

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xxx 11<br />

TABLES (contd)<br />

7.3.1a Number <strong>of</strong> Spent Fuel Canisters Sent to Disposal in the<br />

Once-Through Cycle . . . . . . . . . . . . 7.17<br />

7.3.1b Number <strong>of</strong> <strong>Waste</strong> Containers Sent to Disposal in Reprocessing<br />

Cycle . . . . . . . . . . . . . . . 7.18<br />

7.3.2 Comparison <strong>of</strong> Away-From-Reactor Spent Fuel Storage Requirements<br />

for the Program Alternative Using the Once-Through Cycle . . . . . 7.19<br />

7.3.3 Comparison <strong>of</strong> Away-From-Reactor Spent Fuel Storage Requirements<br />

for the Program Alternative Using the Reprocessing Cycle . . . . . 7.19<br />

7.3.4 Interim <strong>Waste</strong> Storage Requirements for the Program Alternatives Using<br />

the Reprocessing Cycle . . . . . . . . . . . 7.21<br />

7.3.5 Comparison <strong>of</strong> Transportation Requirements for the Program Alternative<br />

Using the Once-Through Fuel Cycle . . . . . . . . . 7.22<br />

7.3.6 Comparison <strong>of</strong> Total Transportation Requirements for the Program<br />

Alternative Using the Reprocessing Fuel Cycle . . . . . . . 7.23<br />

7.3.7 Maximum (and Minimum) Age <strong>of</strong> Spent Fuel Entering the Repository<br />

Using the Once-Through Cycle, Years . . . . . . . . . 7.24<br />

7.3.8 Maximum (and minimum) Age <strong>of</strong> High-Level <strong>Waste</strong> Entering the<br />

Repository using the Reprocessing Cycle, Years . . . . . . . 7.25<br />

7.3.9 Fuel Reprocessing and MOX Fuel Fabrication Plant Requirements . . . . 7.28<br />

7.3.10 Number <strong>of</strong> 800-hectare Repositories Required . . . . . . . 7.29<br />

7.3.11 Equilibrium Requirements for Case 4 (250 GWe Steady State) . . . . 7.29<br />

7.3.12 Plutonium Disposition Within the Timeframe <strong>of</strong> the Analysis . . . . 7.31<br />

7.3.13 Total Radioactivity Inventory <strong>of</strong> All Fission and Activation Products<br />

in All Repositories . . . . . . . . . . . . 7.33<br />

7.3.14 Total Radioactivity Inventory <strong>of</strong> All Actinide and Daughter Nuclides<br />

in All Repositories . . . . . . . . . . . . 7.33<br />

7.3.15 Heat Output <strong>of</strong> Total Inventory <strong>of</strong> all Fission and Activation Products<br />

in All Repositories . . . . . . . . . . . . 7.34<br />

7.3.16 Heat Output <strong>of</strong> Total Inventory <strong>of</strong> All Actinide and Daughter Nuclides<br />

in All Repositories . . . . . . . . . . . . 7.34<br />

7.3.17 Hazard Index <strong>of</strong> Repository <strong>Waste</strong> Inventory Relative to<br />

0.2% Uranium Ore. . . . . . . . . . . . . 7.36<br />

7.3.18 Principal Contributors to the Hazard Index . . . . . . . 7.37<br />

7.4.1 Comparison <strong>of</strong> 70-Year Whole-Body Dose Accumulations from Normal<br />

Operations for the Program Alternatives Using the Once-Through<br />

Cycle, man-rem . . . . . . . . . . . . . 7.38

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