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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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