TWO-DIMENSIONAL FINITE ELEMENT METHOD FOR INTEGRAL NEUTRON TRANSPORT CALCULATIONS.

E. E. Lewis; W. F. Miller; T. P. Henry

doi:10.13182/NSE75-A28223

TWO-DIMENSIONAL FINITE ELEMENT METHOD FOR INTEGRAL NEUTRON TRANSPORT CALCULATIONS.

E. E. Lewis^*, W. F. Miller, T. P. Henry

^*Corresponding author for this work

Mechanical Engineering

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

8 Scopus citations

Abstract

A spatial finite element method is formulated for neutron transport calculations in two-dimensional reactor lattice cells in x-y geometry. The method is closely related to classical integral transport techniques in that scalar flux equations result that are similar in form to those of collision probability methods. The use of triangular spatial elements permits flexible geometrical representation of material regions, including regions with curved interfaces. On a rectangular domain, a block inversion technique provides for the incorporation of exact-reflected boundary conditions into the transport kernel. The method is implemented in a computer code and illustrated in a series of lattice cell calculations.

Original language	English (US)
Pages (from-to)	203-212
Number of pages	10
Journal	Nuclear Science and Engineering
Volume	58
Issue number	2
DOIs	https://doi.org/10.13182/NSE75-A28223
State	Published - Jan 1 1975

ASJC Scopus subject areas

Nuclear Energy and Engineering

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title = "TWO-DIMENSIONAL FINITE ELEMENT METHOD FOR INTEGRAL NEUTRON TRANSPORT CALCULATIONS.",

abstract = "A spatial finite element method is formulated for neutron transport calculations in two-dimensional reactor lattice cells in x-y geometry. The method is closely related to classical integral transport techniques in that scalar flux equations result that are similar in form to those of collision probability methods. The use of triangular spatial elements permits flexible geometrical representation of material regions, including regions with curved interfaces. On a rectangular domain, a block inversion technique provides for the incorporation of exact-reflected boundary conditions into the transport kernel. The method is implemented in a computer code and illustrated in a series of lattice cell calculations.",

author = "Lewis, {E. E.} and Miller, {W. F.} and Henry, {T. P.}",

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AU - Miller, W. F.

AU - Henry, T. P.

PY - 1975/1/1

Y1 - 1975/1/1

N2 - A spatial finite element method is formulated for neutron transport calculations in two-dimensional reactor lattice cells in x-y geometry. The method is closely related to classical integral transport techniques in that scalar flux equations result that are similar in form to those of collision probability methods. The use of triangular spatial elements permits flexible geometrical representation of material regions, including regions with curved interfaces. On a rectangular domain, a block inversion technique provides for the incorporation of exact-reflected boundary conditions into the transport kernel. The method is implemented in a computer code and illustrated in a series of lattice cell calculations.

AB - A spatial finite element method is formulated for neutron transport calculations in two-dimensional reactor lattice cells in x-y geometry. The method is closely related to classical integral transport techniques in that scalar flux equations result that are similar in form to those of collision probability methods. The use of triangular spatial elements permits flexible geometrical representation of material regions, including regions with curved interfaces. On a rectangular domain, a block inversion technique provides for the incorporation of exact-reflected boundary conditions into the transport kernel. The method is implemented in a computer code and illustrated in a series of lattice cell calculations.

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TWO-DIMENSIONAL FINITE ELEMENT METHOD FOR INTEGRAL NEUTRON TRANSPORT CALCULATIONS.

Abstract

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