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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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23 2 233<br />

Th(n,y)---t Th<br />

23*U(n,y)-239U<br />

4-7<br />

Fig. 4.0-2a. Nuclide Production Chain for 232Th.<br />

239Np(n, y),240Np<br />

0- 123.5111<br />

Fig. 4.0-2b. Nucl ie Production Chain for 23%.<br />

Consideration of many of <strong>the</strong> above factors is inherent in <strong>the</strong> "mass balance" calcula-<br />

tions presented in this chapter for <strong>the</strong> various reactors operating on alternate fuel cycles.<br />

It is emphasized, however, that if a definite decision were made to employ a specific alternate<br />

fuel cycle in a specific reactor, <strong>the</strong> next step would be to optimize <strong>the</strong> reactor design for<br />

that particular cycle, as is discussed in Chapter 5. Optimization of each reactor for <strong>the</strong><br />

many fuels considered was beyond <strong>the</strong> scope of this study, however, and instead <strong>the</strong> design<br />

used for each reactor was <strong>the</strong> design for that reactor's reference fuel, regardless of <strong>the</strong><br />

fuel cycle under consideration.<br />

The reactors analyzed in <strong>the</strong> calculations are light-water <strong>the</strong>rmal reactors; spectral-<br />

shift-controlled <strong>the</strong>rmal reactors; heavy-water <strong>the</strong>rmal reactors; high-temperature gas-<br />

cooled <strong>the</strong>rmal reactors; liquid-metal fast breeder reactors; and fast breeder reactors of<br />

advanced or alternate designs.

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