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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6-6<br />
6.1.2. Reactor Options<br />
The reactor designs included in this study have not been optimized to cover every con-<br />
ceivable nuclear policy option. Such a task is clearly impossible until <strong>the</strong> options have<br />
been reduced to a more manageable number.<br />
by using detailed design procedures and <strong>the</strong>y are more than adequate for a reactor strategy<br />
study such as is described here.<br />
However, <strong>the</strong> designs selected have been developed<br />
Table 6.1-1. Estimates of Us08 Supply Available in U.S.A.a<br />
Resources (lo3 ST)<br />
Forward<br />
cost<br />
($71 b) Known Probable Possible Speculative To tal<br />
aFrom ref. 1.<br />
~<br />
15 360 560 485 165 1,570<br />
30 690 1,065 1,120 41 5 3,290<br />
50b 875 1,450 1,470 5 70 4 , 365<br />
bAt $50/lb, <strong>the</strong> known reserves of 875 x lo3 ST plus <strong>the</strong> probable reserves of 1,450 x 103<br />
ST plus 140 x 103 ST from byproducts (phosphates and copper) total 2,465 x 103 ST (or %<br />
2.5 million ST). If <strong>the</strong> possible and speculative resources are included, <strong>the</strong> total is<br />
increased to 4,505 x lo3 ST (or % 4.5 million ST).<br />
Four general types of reactors are included:<br />
LWRs, represented by Pressurized Water<br />
Reactors (PWRs) ; HWRs, represented by Canadian Deuterium Uranium Reactors (CANDUS) ; High<br />
Temperature Gas Cooled Reactors (HTGRs); and Fast Breeder Reactors (FBRs). The data for <strong>the</strong><br />
PWRs were provided by Combustion Engineering (CE) and Hanford Engineering Development Lab-<br />
oratory (HEDL); <strong>the</strong> data for <strong>the</strong> CANDUs by Argonne National Laboratory (ANL); <strong>the</strong> data for<br />
<strong>the</strong> HTGRs by General Atomic (GA); and <strong>the</strong> data for <strong>the</strong> FBRs by HEDL.<br />
standard LWRs (PWRs) , spectral-shift-controlled PWRs (SSCRs) are also included in <strong>the</strong> study,<br />
<strong>the</strong> data for <strong>the</strong> SSCRs being provided by CE. Descriptions of <strong>the</strong> individual reactors used<br />
in <strong>the</strong> study are given in Tables 6.1-2 and 6.1-3 (ref. 7), and <strong>the</strong> economic data base for<br />
each is given in Appendix B.<br />
In addition to <strong>the</strong><br />
The LWR designs include reactors fueled with low-enriched and denatured 23511, denatured<br />
233U, and plutonium, <strong>the</strong> diluent for <strong>the</strong> denatured designs consisting of ei<strong>the</strong>r 2381) or<br />
thorium, or both. In addition, a low-enriched LWR design optimized for throwaway has been<br />
studied, and also three SSCRs fueled with low-enriched 23511, denatured 233U, and Pu/Th.<br />
The HWRs are represented by three 235U-fueled reactors (natural , slightly enriched,<br />
and denatured), a denatured 233U reactor, a P U / ~ ~ reactor, ~ U and a Pu/Th reactor. The HTGR<br />
designs consist of low-enriched, denatured, and highly enriched z35U reactors; denatured*<br />
and highly enriched 233U reactors; and a Pu/Th reactor.<br />
The FBR designs consist of two PU/*~~U core designs (one with a 238U blanket and one<br />
with a thorium blanket) and one Pu/Th core design (with a thorium blanket). In addition, a<br />
233U/238U core design with a thorium blan\et has been studied. The 233U enrichment is less<br />
than 12%, and thus this FBR is a denatured design.<br />
*In contrast to <strong>the</strong> o<strong>the</strong>r reactor types, <strong>the</strong> denatured 233U HTGR design is assumed to contain<br />
15% 233U in 238U instead of 12%.<br />
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