PROGRESS IN MULTIDIMENSIONAL NEUTRON TRANSPORT COMPUTATION.

E. E. Lewis*

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

7 Scopus citations

Abstract

The methods available for solution of the time-independent neutron transport problems arising in the analysis of nuclear systems are examined. The merits of deterministic and Monte Carlo methods are briefly compared. The capabilities of deterministic computational methods derived from the first-order form of the transport equation, from the second-order even-parity form of this equation, and from integral transport formulations are discussed in some detail. Emphasis is placed on the approaches for dealing with the related problems of computer memory requirements, computational cost, and achievable accuracy. Attention is directed to some areas where problems exist currently and where the need for further work appears to be particularly warranted.

Original languageEnglish (US)
Pages (from-to)279-293
Number of pages15
JournalNuclear Science and Engineering
Volume64
Issue number2
DOIs
StatePublished - Jan 1 1977

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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