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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educe <strong>the</strong> average demand for mined uranium. O<strong>the</strong>r performance improve-<br />
ments (short of break-even breeding) could be achieved by combining <strong>the</strong><br />
on-line fuel processing with periodic removal or reenrichment of part of<br />
<strong>the</strong> active uranium inventory. In all <strong>the</strong>se options, <strong>the</strong> net consumption<br />
of natural uranium would become a minor factor in <strong>the</strong> application of<br />
BMSHPs. Some consideration was given to fuel processing concepts that<br />
Would reBIOVe Only part of <strong>the</strong> SOlklbPe fission products. such prQC@SseS<br />
appear to offer few (if any) advantages over ei<strong>the</strong>r <strong>the</strong> unprocessed or<br />
<strong>the</strong> fuhky plrOCeSsed apprQaCheS,<br />
6,3 Commercialization Considerations<br />
Since <strong>the</strong> MSW concept was under study and deVelQpmWIt for nearly a0<br />
years, most of <strong>the</strong> relevant areas of <strong>the</strong> required technology have received<br />
at least some attention. After <strong>the</strong> successful operation of <strong>the</strong> EISRE, a<br />
Pimjitecf amount of design effort was expended on a commercial-size MSBB;<br />
that effort was discontinued in 1993, The technology development work<br />
proceeded in parallel with <strong>the</strong> design studies up to that time. A small<br />
development effort (without design support) was resumed in I974 and can-<br />
celled again in l976, This WQI-~, despite its limited scope, provided an<br />
engineering-scale demonstration of tritium management in <strong>the</strong> secondary<br />
salt and significant progress toward <strong>the</strong> definition of an acceptable<br />
structural alloy for molten-salt service. Work was under way toward dem-<br />
onstration of some of <strong>the</strong> chemical processing operations when <strong>the</strong> program<br />
was ended<br />
Aside from <strong>the</strong> technical progress, <strong>the</strong> last development activity<br />
produced a comprehensive plan ~ S S <strong>the</strong> fur<strong>the</strong>r development of MSRs, which<br />
served as <strong>the</strong> basis for <strong>the</strong> proposed DMSR development plan and schedule.<br />
This plan suggests that <strong>the</strong> commercialization of DMSRs could proceed via<br />
three reactor projects: (a> a moderate-sized (100- to 2BO-PIWe) molten-<br />
salt test reactor that could be authorfzed in 1985 and become operational<br />
in 1995, (2) an intermediate-sized commercial prototype plant authorized<br />
in 1995 and operating in 2005, and (3) a first standard-design DMSR to<br />
operate in 2011. A preliminary estimate for <strong>the</strong> cost of this programrp<br />
Y