Publication: Evaluation of the burnout efficiency of Np-237 and Am-241 in a BN-600 reactor with a modified core
Дата
2020
Авторы
Korobeynikov, V. V.
Ignatev, I. A.
Klimenko, D. S.
Kolesov, V. V.
Vnukov, R. A.
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© Published under licence by IOP Publishing Ltd.From the results of comparing the fission and capture cross sections, it follows that a reactor with fuel in the form of Am-241 or Np-237 can only be on fast neutrons, because in the thermal and intermediate spectra, the capture cross section significantly exceeds the fission cross section. Therefore, this paper analyzes the possibility of achieving criticality when loading the BN-600 reactor core with fuel from Am-241 or Np-237 alone, as well as the efficiency of their burning out in various modifications and variants of core loading. The calculation results show that when the reactor is fully loaded with fuel consisting of minor actinides of interest, we have a huge reactivity reserve, which does not decrease, and in some cases increases, during 450 days of reactor operation at rated power. Also, when calculating the modified core with fuel from minor actinides and uranium dioxide, it was possible to achieve high burnout rates of Am-241 and Np-237.
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Evaluation of the burnout efficiency of Np-237 and Am-241 in a BN-600 reactor with a modified core / Korobeynikov, V.V. [et al.] // Journal of Physics: Conference Series. - 2020. - 1689. - № 1. - 10.1088/1742-6596/1689/1/012047