The finite element response matrix method for the solution of the neutron transport equation

Progress in Nuclear Energy ◽

10.1016/0149-1970(86)90030-2 ◽

1986 ◽

Vol 18 (1-2) ◽

pp. 237-250 ◽

Author(s):

James A. Rathkopf ◽

William R. Martin

Keyword(s):

Finite Element ◽

Transport Equation ◽

Matrix Method ◽

Neutron Transport ◽

Response Matrix ◽

Neutron Transport Equation

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A finite element approach for treating the energy variable in the numerical solution of the neutron transport equation

Transport Theory and Statistical Physics ◽

10.1080/00411458608212681 ◽

1986 ◽

Vol 15 (4) ◽

pp. 449-478 ◽

Author(s):

E. J. Allen

Keyword(s):

Finite Element ◽

Numerical Solution ◽

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Finite Element Approach ◽

Element Approach ◽

Energy Variable

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A multi group finite-element solution of the neutron transport equation—II

Annals of Nuclear Energy ◽

10.1016/0306-4549(85)90105-7 ◽

1985 ◽

Vol 12 (5) ◽

pp. 217-231 ◽

Author(s):

J. Wood

Keyword(s):

Finite Element ◽

Transport Equation ◽

Neutron Transport ◽

Finite Element Solution ◽

Element Solution ◽

Neutron Transport Equation

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Discontinuous finite element discretizations for the SN neutron transport equation in problems with spatially varying cross sections

Annals of Nuclear Energy ◽

10.1016/j.anucene.2014.06.050 ◽

2014 ◽

Vol 73 ◽

pp. 506-526 ◽

Author(s):

Peter G. Maginot ◽

Jean C. Ragusa ◽

Jim E. Morel

Keyword(s):

Finite Element ◽

Transport Equation ◽

Cross Sections ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Finite Element Discretizations ◽

Discontinuous Finite Element ◽

Spatially Varying ◽

Element Discretizations

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Least-Squares Finite Element Discretization of the Neutron Transport Equation in Spherical Geometry

SIAM Journal on Scientific Computing ◽

10.1137/140975152 ◽

2015 ◽

Vol 37 (5) ◽

pp. S71-S89 ◽

Author(s):

C. Ketelsen ◽

T. Manteuffel ◽

J. B. Schroder

Keyword(s):

Finite Element ◽

Transport Equation ◽

Least Squares ◽

Neutron Transport ◽

Spherical Geometry ◽

Neutron Transport Equation ◽

Finite Element Discretization ◽

Element Discretization

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Nodal finite element approximations for the neutron transport equation

Mathematics and Computers in Simulation ◽

10.1016/j.matcom.2010.04.010 ◽

2010 ◽

Vol 80 (11) ◽

pp. 2168-2176 ◽

Author(s):

Jean-Pierre Hennart ◽

Edmundo del Valle

Keyword(s):

Finite Element ◽

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Finite Element Approximations

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SOLUTION OF THE TWO‐DIMENSIONAL NEUTRON TRANSPORT EQUATION BY A HIERARCHICAL FINITE ELEMENT METHOD

International Journal of Numerical Methods for Heat &amp Fluid Flow ◽

10.1108/eb017514 ◽

1993 ◽

Vol 3 (1) ◽

pp. 35-47 ◽

Author(s):

AWONO ONANA ◽

S. YUNKAP KWANKAM ◽

MVOGO NGONO JOSEPH

Keyword(s):

Finite Element Method ◽

Finite Element ◽

Transport Equation ◽

Neutron Transport ◽

Two Dimensional ◽

Neutron Transport Equation ◽

Hierarchical Finite Element Method ◽

Element Method ◽

Hierarchical Finite Element

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A Unified Form of Stabilized Finite Element Methods for Solving the First-order Neutron Transport Equation

10.13182/t31927 ◽

2020 ◽

Author(s):

L. Cao ◽

C. Fang ◽

H. Wu

Keyword(s):

Finite Element ◽

Transport Equation ◽

Finite Element Methods ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Stabilized Finite Element Methods ◽

Stabilized Finite Element ◽

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Solution of Multi-Dimensional Neutron Transport Equation by Finite Element Method

Journal of Nuclear Science and Technology ◽

10.1080/18811248.1972.9734860 ◽

1972 ◽

Vol 9 (6) ◽

pp. 366-373 ◽

Author(s):

Seiji UKAI

Keyword(s):

Finite Element Method ◽

Finite Element ◽

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

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An arbitrary geometry finite element method for the adjoint neutron transport equation

Annals of Nuclear Energy ◽

10.1016/j.anucene.2017.06.038 ◽

2017 ◽

Vol 110 ◽

pp. 511-525 ◽

Author(s):

Mostafa Yousefi ◽

A. Zolfaghari ◽

A. Minuchehr ◽

M.R. Abbassi

Keyword(s):

Finite Element Method ◽

Finite Element ◽

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Arbitrary Geometry ◽

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Discontinuous Finite Element Method for Solving the Two-Dimesional Neutron Transport Equation on Lagrangian Meshes

Nuclear Science and Engineering ◽

10.13182/nse86-a18166 ◽

1986 ◽

Vol 92 (2) ◽

pp. 197-203 ◽

Author(s):

G. Samba

Keyword(s):

Finite Element Method ◽

Finite Element ◽

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Discontinuous Finite Element ◽

Discontinuous Finite Element Method ◽

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