Multigroup Methods for Neutron Diffusion Problems

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Description

Abstract: "The age-diffusion is adequate to describe the neutron behavior of a very large class of nonthermal reactors (all except those whose dimensions are comparable to the neutron mean free path). Thus, a convenient means of obtaining an accurate solution to this equation is very useful for general reactor calculations. Methods for reducing the age-diffusion equation to a finite set of coupled ordinary differential equations, called multigroup equations, are described. The relative merits of several alternate schemes are discussed. The multigroup equations may be solved by iterative procedures based on an assumed spatial distribution of the fission source neutrons. In … continued below

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[46] p. : ill. ; 28 cm.

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Hurwitz, H., Jr. & Ehrlich, R. August 20, 1953.

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  • Main Title: Multigroup Methods for Neutron Diffusion Problems
  • Series Title: Atomic Energy Commission Reports
  • Added Title: Atomic Energy Commission Report AECD-3595

Description

Abstract: "The age-diffusion is adequate to describe the neutron behavior of a very large class of nonthermal reactors (all except those whose dimensions are comparable to the neutron mean free path). Thus, a convenient means of obtaining an accurate solution to this equation is very useful for general reactor calculations. Methods for reducing the age-diffusion equation to a finite set of coupled ordinary differential equations, called multigroup equations, are described. The relative merits of several alternate schemes are discussed. The multigroup equations may be solved by iterative procedures based on an assumed spatial distribution of the fission source neutrons. In practice the initially assumed source shape is accurate enough so that additional iterations are unnecessary. Analytical and numerical methods for solving the multigroup equations with the assumed source are discussed. The adjoint equations are also reduced to multigroup form, and examples of the adjoint function in obtaining improved reactivity values are given."

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[46] p. : ill. ; 28 cm.

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  • OCLC: 911182890
  • SuDoc Number: Y 3.AT 7:22/AECD-3595
  • Report No.: AECD-3595
  • Grant Number: W-31-109-Eng-52
  • Archival Resource Key: ark:/67531/metadc172808

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  • August 20, 1953

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  • Feb. 12, 2018, 7:42 a.m.

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  • April 23, 2019, 3:20 p.m.

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Hurwitz, H., Jr. & Ehrlich, R. Multigroup Methods for Neutron Diffusion Problems, report, August 20, 1953; [Oak Ridge, Tennessee]. (https://digital.library.unt.edu/ark:/67531/metadc172808/: accessed November 14, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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