ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
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