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Small-group matrix of neutron diffusion coefficients in reactor lattices

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Literature Cited

  1. 1.

    N. I. Laletin and V. F. Boyarinov, “Effective single-group diffusion coefficient of neutrons in reactor lattices,” At. Énerg.,59, No. 2, 91–96 (1985)

  2. 2.

    N. I. Laletin, “Equations of a heterogeneous reactor. A review,” VANT, Ser. Fiz. Tekh. Yad. Reakt., No. 5 (18), 31–46 (1981).

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    N. I. Laletin, “Equations of heterogeneous reactor (basic principles of construction),” in: Homogenization Method in Reactor Physics, IAEA-TECDOC-231, Vienna (1978), pp. 499–520.

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    V. F. Boyarinov, “Method of surface pseudosources for calculating the antisymmetric single-group neutron distribution in a cylindrical reactor cell,” At. Énerg.,59, No. 2, 104–108 (1985).

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Translated from Atomnaya Énergiya, Vol. 62, No. 5, pp. 351–352, May, 1987.

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Laletin, N.I., Boyarinov, V.F. Small-group matrix of neutron diffusion coefficients in reactor lattices. At Energy 62, 409–412 (1987). https://doi.org/10.1007/BF01125200

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  • Diffusion Coefficient
  • Reactor Lattice
  • Neutron Diffusion