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Estimated results of measuring the average neutron cross section ratios for fuel nuclides in a BN-350 reactor

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Literature Cited

  1. A. S. Seregin, “Annotating the TRIGEX program for few-group neutron physics reactor calculations in three-dimensional hexagonal geometry,” Vopr. At. Nauki Tekhniki, Ser. Fiz. Tekh. Yad. Reaktorov, No. 4 (33) (1982).

  2. R. K. Goncharov, A. V. Zvonarev, V. I. Ivanov, et al., “Comparing the235U and239Pu alpha values determined from analyzing irradiated BN-350 reactor fuel with calculated values,” At. Énerg.,61, No. 6, 456–457 (1986).

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  3. R. K. Goncharov, A. V. Zvonarev, V. A. Kolyzhenkov, et al., “Ratio of average cross sections for a number of fuel nuclides in a low-enrichment zone and a uranium-plutonium module of a BN-350 reactor,” ibid.66 No. 5, 353–354 (1989).

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Authors
  1. R. K. Goncharov
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  2. A. V. Zvonarev
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  3. V. A. Kolyzhenkov
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  4. M. N. Nikolaev
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  5. M. Yu. Semenov
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  6. A. M. Tsibulya
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Additional information

Physices-Power Institute. Translated from Atomnaya Énergiya, Vol. 70, No. 2, pp. 123–125, February, 1991.

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Goncharov, R.K., Zvonarev, A.V., Kolyzhenkov, V.A. et al. Estimated results of measuring the average neutron cross section ratios for fuel nuclides in a BN-350 reactor. At Energy 70, 160–163 (1991). https://doi.org/10.1007/BF01121863

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  • DOI: https://doi.org/10.1007/BF01121863

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