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ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

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32<br />

"spent" fuel. If credit were allowed for <strong>the</strong> residual fissile uranium<br />

in <strong>the</strong> salt (plutonium presumably would not be recovered), <strong>the</strong> net U308<br />

requirement would be reduced by almost one-half,<br />

The temporal distribution of fuel requirements in a DMSR is also<br />

significant. The data in Table 17 show that only about 36% of <strong>the</strong> makeup<br />

fuel is required during <strong>the</strong> first 15 years of <strong>the</strong> cycle; <strong>the</strong> major demand<br />

occurs toward <strong>the</strong> end-of-life. Thus, if <strong>the</strong> reactor were operated at a<br />

lower capacitv factor in later years, <strong>the</strong> U308 requirement could be re-<br />

duced fur<strong>the</strong>r or <strong>the</strong> plant calendar lifetime could be extended. The ad-<br />

vantage associated with <strong>the</strong> time distribution of <strong>the</strong> makeup fuel require-<br />

ment is partly offset by <strong>the</strong> large initial fuel loading and <strong>the</strong> high in-<br />

plant fissile inventory. Therefore, an optimum fuel cycle might coneeiv-<br />

ably balance a Power initial loading (and inventory) having a lower net<br />

conversion ratio against a higher requirement for makeup fuel.<br />

pears to be some latitude for optimization of <strong>the</strong> fuel cycle in this area.<br />

3.1.6.2 Potential for imDrsvement<br />

*<br />

There ap-<br />

mile <strong>the</strong> fuel utilization of this conceptual system compares favor-<br />

ably with that of o<strong>the</strong>r reactor systems, some fur<strong>the</strong>r improvements may be<br />

possible. Only a limited range of fuel volume fractions and core zone<br />

sizes has been conside~edl for this core, and o<strong>the</strong>r values could lead to<br />

higher performance. However, <strong>the</strong>re appears to be little potential benefit<br />

in using more than two core zones.<br />

The actinide content of <strong>the</strong> salt is thought to be near optimum for<br />

long-term, high-performance conversion, but, as implied previously, an-<br />

o<strong>the</strong>r concentration might be better for <strong>the</strong> 30-year cycle. Certainly,<br />

some improvement in fuel utilization would come from relaxing <strong>the</strong> re-<br />

quirement for 2 3 8 ~ content ei<strong>the</strong>r of <strong>the</strong> system in operation or of <strong>the</strong><br />

makeup material being added. Table 18 shows <strong>the</strong> approximate effect of<br />

<strong>the</strong>se constraints on 2 3 5 ~ requirements.<br />

fully denature <strong>the</strong> makeup feed material has only a small effect on <strong>the</strong><br />

fuel requirement.<br />

Removing <strong>the</strong> requirement to<br />

Similarly, increasing <strong>the</strong> allowed enrichment of 234U<br />

This is frequently done in electric power stations as newer and<br />

dk<br />

cheaper plants are built.

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