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Review of Molten Salt Reactor Physics Calculations [Disc 2]

Review of Molten Salt Reactor Physics Calculations [Disc 2]

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10<br />

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

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