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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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6-27<br />

The effect of applying <strong>the</strong> improving tails strategy to a nuclear system based on <strong>the</strong><br />

throwaway cycle is to increase <strong>the</strong> maximum installed nuclear capacity by approximately 60 GWe<br />

and to delay <strong>the</strong> maximum by approximately five years (see Fig. 6.2-9). Mining <strong>the</strong> tails<br />

stockpile accumulated prior to 2010 does not significantly change <strong>the</strong> result. The reason<br />

that mining <strong>the</strong> past tails stockpile does not produce a significantly larger nuclear contri-<br />

bution is explained by Fig. 6.2-11, which shows <strong>the</strong> cumulative amount of U308 processed<br />

through <strong>the</strong> enrichment plants as a function of time. The amount is considerably less than<br />

<strong>the</strong> amount of U,Ob committed at any given time, as shown in Fig. 6.2-6. It i s important to<br />

note that <strong>the</strong> amount of U308 actually processed through <strong>the</strong> enrichment plants prior to 1990<br />

is relatively small, and at this time <strong>the</strong> tails composition for <strong>the</strong> improving tails strategy<br />

has been decreasing linearly for 10 yr. Thus, most of <strong>the</strong> U308 in <strong>the</strong> improving tails case<br />

is processed at lower tails compositions, and mining <strong>the</strong> past stockpile does not produce a<br />

significant improvement.<br />

The most dramatic effect associated with <strong>the</strong> improving tails option<br />

is <strong>the</strong> increase in <strong>the</strong> maximum annual enrichment requirement. As indicated in Fig. 6.2-9,<br />

<strong>the</strong> maximum annual U308 requirement for this option is 67,000 ST/yr, while <strong>the</strong> maximum<br />

annual enrichment requirement is 92 million SWU/yr. Thus, <strong>the</strong> principal limitation in this<br />

case would be <strong>the</strong> availability of enrichment capacity.<br />

The utilization and movement of fissile material per GWe of installed capacity in<br />

<strong>the</strong> year 2035 for each of <strong>the</strong> converter options is shown in Fig. 6.2-12a-d, assuming <strong>the</strong><br />

high-cost U308 supply. These figures represent a snapshot of <strong>the</strong> system in time and include<br />

<strong>the</strong> first core loadings for units starting up in <strong>the</strong> year 2036.<br />

As can be seen, <strong>the</strong> U308 con-<br />

sumption for Case 1L in <strong>the</strong> year 2035 is approximately 142 ST U308/GWe, with <strong>the</strong> LWRs having<br />

an extended discharge exposure comprising 92% of <strong>the</strong> installed capacity. When <strong>the</strong> LWRs are<br />

followed by SSCRs (Case lS), <strong>the</strong> annual U308 consumption is 135 ST U308, with <strong>the</strong> SSCR com-<br />

prising 74% of <strong>the</strong> installed capacity. The fractional installed capacity of <strong>the</strong> SSCR is less<br />

than that of <strong>the</strong> extended-exposure LWR in Case 1L because <strong>the</strong> extended-exposure LWR is intro-<br />

duced'in 1981 while <strong>the</strong> SSCR is not introduced until 1991. In general, <strong>the</strong> fractional installed<br />

capacity of a reactor concept in <strong>the</strong> year 2035 will decrease monotonically as <strong>the</strong> intro-<br />

duction date for <strong>the</strong> concept increases. Similarly, <strong>the</strong> fractional installed nuclear<br />

capacity of a reactor concept will increase monotonically as its U308 requirement decreases.<br />

When <strong>the</strong> LWRs are followed by HTGRs (Case lG.), <strong>the</strong> U308 consumption in <strong>the</strong> year 2035<br />

is 133 ST U308/GWe, with <strong>the</strong> HTGR comprising 54% of <strong>the</strong> installed capacity. The annual U308<br />

consumption is lower than in Case 1s because <strong>the</strong> U308 requirement of <strong>the</strong> HTGR is less than<br />

that of <strong>the</strong> SSCR (see Table 6.1-2 and Fig. 6.2-1). The fractional installed capacity of <strong>the</strong><br />

HTGR is less than that of <strong>the</strong> SSCR in <strong>the</strong> Case 1s because <strong>the</strong> SSCR is introduced in 1991<br />

while <strong>the</strong> HTGR is not introduced until 1995.<br />

When HWRs follow <strong>the</strong> LWRs (Case lH), U3O8 consumption in year 2035 is approximately<br />

106 ST U308/GWe and <strong>the</strong> HWR comprises 79% of <strong>the</strong> installed capacity. The HWR in this case<br />

and <strong>the</strong> HTGR in Case 1G have <strong>the</strong> same introduction date. The HWR, however, has a lower<br />

U308 requirement and hence <strong>the</strong> total installed nuclear capacity is greater with this

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