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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96<br />
233U production capability would be less than 3 kgfyear, which seems im-<br />
practically low.<br />
AI%hough <strong>the</strong> removal of fissile material from a DMSR may be awkward,<br />
if it could be ascomplfshed without removing large quantities of salt,<br />
<strong>the</strong>n <strong>the</strong> removal could be easily ~~ncesled by additions of denatured 235U<br />
to <strong>the</strong> fuel salt. The change in total uranium concentration would not<br />
become significant until after <strong>the</strong> exchange of a few tens of kilograms of<br />
fissile fuel<br />
Although a much more detailed, quantitative analysis that considered<br />
<strong>the</strong> relative values of various foms of SSMM would be required to permit<br />
a comprehensive ~SS~SSTIER~ of <strong>the</strong> proliferation sensitivity of <strong>the</strong> once-<br />
through DNSR, this general treatment suggests that this concept may corn-<br />
pare favorably with o<strong>the</strong>r alternatives in terns of resistance to prolif-<br />
eration of nuclear explosives.<br />
. ...<br />
. . . . . . . .<br />
v.3