VARIATIONAL NODAL METHODS FOR NEUTRON TRANSPORT.

I. Dilber*, Elmer E Lewis

*Corresponding author for this work

Research output: Contribution to journalArticle

27 Scopus citations

Abstract

Nodal diffusion and transport methods are formulated variationally in terms of the even-parity form of the neutron transport equation and applied to problems in X-Y geometry. The resulting functional guarantees the satisfaction of nodal balance, regardless of the form of the space-angle trial function within the node or on its boundaries. Code vectorization and generalization to three dimensions are discussed.

Original languageEnglish (US)
Pages (from-to)132-142
Number of pages11
JournalNuclear Science and Engineering
Volume91
Issue number2
DOIs
StatePublished - Jan 1 1985

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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