Review of Molten Salt Reactor Physics Calculations [Disc 2]
Review of Molten Salt Reactor Physics Calculations [Disc 2]
Review of Molten Salt Reactor Physics Calculations [Disc 2]
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2. The average '1 <strong>of</strong> 235U was 1.9n compared with 1.958 in the<br />
previous calculations. We believe that the new cross sections are<br />
likely to be better for this nuclide. The result was an increase in<br />
breeding ratio <strong>of</strong> 0,001.<br />
3. We used a lower cross section for 234U in accordance with the<br />
.recammendations <strong>of</strong> the latest edition <strong>of</strong> 3ML-325, As (1 consequence,<br />
more <strong>of</strong> the 234U<br />
was removed with the excess uranium, and there were<br />
'fewer absorptions in 235U, 236U, and 237Np. The net result kppears<br />
to have been an increase.in breeding ratio <strong>of</strong> less than 0.001.<br />
4. We did not include any 23% production in our calculation<br />
since it did not seem appropriate. Any other trans-uranium isotdpes<br />
beyond 237Ng<br />
should not lead to a net loss since they could probably<br />
be separated and sold if there were any tendency for them to accumulate.<br />
An increase in breeding ratio <strong>of</strong> 0.001 resulted.<br />
5. Parasitic absorptions in carrier salt (other than 6 W) were<br />
lower because <strong>of</strong> the Increased fissile loading In our calculation. An<br />
increase <strong>of</strong> 0.003 in breeding ratio occured.<br />
6. Parasitic absorptions in graphite were lower for the same reason.<br />
An increase <strong>of</strong> 0.004 occured.<br />
7. The previous calculations osnittqd the INOR tubes in the lower<br />
blanket. Although there is a possibility <strong>of</strong> reducing the ef'fect by<br />
redesign, the current design gave a breeding ratio loss <strong>of</strong> 0.005 to<br />
absorptions in the INOR.<br />
8. Our calculations gave an increase in breeding ratio <strong>of</strong> 0.003<br />
from lower fission product absorption. About one-half <strong>of</strong> this difference<br />
came from nuclides which were allowed to recycle in the cPTIMERc calcula-<br />
tion althorn belonging to chemical groups which are actually thought .%o<br />
be removed in reprocessing. It may be that the prevholis calculations<br />
were Justified in introducing a measure <strong>of</strong> conservatism at this point.<br />
The remainder <strong>of</strong> the difference is associated with the higher fissile<br />
inventory in our calculations.<br />
. 9. The previous calculations used a 7 I,% content in the makeup <strong>of</strong><br />
99.997$ together with a cost <strong>of</strong> $120 per kg. In reviewing the basis for<br />
this choice we find that the publtshed AEC price schedule is for 99.996<br />
t