GENERATION OF TIME-DEPENDENT NEUTRON TRANSPORT SOLUTIONS IN INFINITE MEDIA.

B. D. Ganapol, P. W. McKenty, K. L. Peddicord

Research output: Contribution to journalArticle

27 Scopus citations

Abstract

The multiple collision technique as applied to the monoenergetic time-dependent neutron transport equation for pulsed plan source emission in an infinite medium is used to obtain the flux due to a pulsed point source in the same medium. This result is then integrated to determine the flux due to the corresponding pulsed line source problem. The semi-infinite albedo problem is also shown to be solvable using the multiple collision approach. A generalization to include delayed neutrons follows directly from the multiple collision treatment, as does an equivalence between a monoenergetic time-dependent problem and a particular stationary slowing down problem in infinite geometry. Results are tabulated and comparisons are made to provide benchmark solutions to the fundamental time-dependent transport problems considered and thus bridge the gap between theory and practice.

Original languageEnglish (US)
Pages (from-to)317-331
Number of pages15
JournalNuclear Science and Engineering
Volume64
Issue number2
DOIs
StatePublished - Jan 1 1977
Externally publishedYes

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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