VARIATIONAL NODAL METHODS FOR NEUTRON TRANSPORT.

I. Dilber; E. E. Lewis

doi:10.13182/NSE85-A27436

VARIATIONAL NODAL METHODS FOR NEUTRON TRANSPORT.

I. Dilber^*, E. E. Lewis

^*Corresponding author for this work

Mechanical Engineering

Research output: Contribution to journal › Article › peer-review

40 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 language	English (US)
Pages (from-to)	132-142
Number of pages	11
Journal	Nuclear Science and Engineering
Volume	91
Issue number	2
DOIs	https://doi.org/10.13182/NSE85-A27436
State	Published - 1985

ASJC Scopus subject areas

Nuclear Energy and Engineering

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title = "VARIATIONAL NODAL METHODS FOR NEUTRON TRANSPORT.",

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.",

author = "I. Dilber and Lewis, {E. E.}",

year = "1985",

doi = "10.13182/NSE85-A27436",

language = "English (US)",

volume = "91",

pages = "132--142",

journal = "Nuclear Science and Engineering",

issn = "0029-5639",

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T1 - VARIATIONAL NODAL METHODS FOR NEUTRON TRANSPORT.

AU - Dilber, I.

AU - Lewis, E. E.

PY - 1985

Y1 - 1985

N2 - 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.

AB - 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.

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U2 - 10.13182/NSE85-A27436

DO - 10.13182/NSE85-A27436

M3 - Article

AN - SCOPUS:0022145478

SN - 0029-5639

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SP - 132

EP - 142

JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

IS - 2

ER -

VARIATIONAL NODAL METHODS FOR NEUTRON TRANSPORT.

Abstract

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