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