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Multigroup integral equation system for the description of neutron transfer

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Literature Cited

  1. D. V. Shirkov, in: The Physics and Thermal Technique of Reactors [in Russian], Atomizdat, Moscow (1958), p. 57.

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  2. A. D. Galanin, The Theory of Thermal Neutron Atomic Reactors [in Russian], Atomizdat, Moscow (1959).

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  3. J. Butler, The Status of Theoretical Methods for Reactor Shield Design, AEEW-R361 (1964).

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  5. I. V. Gordeev and others, Nuclear Physics Constants [in Russian], Gosatomizdat, Moscow (1963).

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Authors
  1. B. R. Bergel'son
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  2. I. A. Rumyantsev
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  3. B. Z. Torlin
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Additional information

Translated from Atomnaya Énergiya, Vol. 24, No. 1, pp. 28–32, January, 1968.

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Bergel'son, B.R., Rumyantsev, I.A. & Torlin, B.Z. Multigroup integral equation system for the description of neutron transfer. At Energy 24, 27–31 (1968). https://doi.org/10.1007/BF01133463

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  • DOI: https://doi.org/10.1007/BF01133463

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