Mesh-free method for numerical solution of the multi-group discrete ordinate neutron transport equation

Annals of Nuclear Energy ◽

10.1016/j.anucene.2017.03.034 ◽

2017 ◽

Vol 106 ◽

pp. 51-63 ◽

Author(s):

S. Kashi ◽

A. Minuchehr ◽

A. Zolfaghari ◽

B. Rokrok

Keyword(s):

Numerical Solution ◽

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Discrete Ordinate ◽

Mesh Free ◽

Mesh Free Method

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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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Analytical Tests for Ray Effect Errors in Discrete Ordinate Methods for Solving the Neutron Transport Equation

10.2172/15014046 ◽

2004 ◽

Author(s):

B Chang

Keyword(s):

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Discrete Ordinate

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A geometry conforming isogeometric method for the self-adjoint angular flux (SAAF) form of the neutron transport equation with a discrete ordinate (SN) angular discretisation

Annals of Nuclear Energy ◽

10.1016/j.anucene.2019.107049 ◽

2020 ◽

Vol 136 ◽

pp. 107049 ◽

Author(s):

C. Latimer ◽

J. Kópházi ◽

M.D. Eaton ◽

R.G. McClarren

Keyword(s):

Transport Equation ◽

Neutron Transport ◽

The Self ◽

Neutron Transport Equation ◽

Discrete Ordinate

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Numerical Solution Using Two- Dimensional Haar Wavelet Collocation Method for Stationary Neutron Transport Equation in Homogeneous Isotropic Medium

Fractional Calculus with Applications for Nuclear Reactor Dynamics ◽

10.1201/b18684-13 ◽

2015 ◽

pp. 196-223

Keyword(s):

Numerical Solution ◽

Transport Equation ◽

Collocation Method ◽

Isotropic Medium ◽

Neutron Transport ◽

Haar Wavelet ◽

Two Dimensional ◽

Neutron Transport Equation ◽

Wavelet Collocation Method

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Application of preconditioned GMRES to the numerical solution of the neutron transport equation

Annals of Nuclear Energy ◽

10.1016/s0306-4549(01)00034-2 ◽

2002 ◽

Vol 29 (2) ◽

pp. 109-136 ◽

Author(s):

Bruce W. Patton ◽

James Paul Holloway

Keyword(s):

Numerical Solution ◽

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Preconditioned Gmres

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Numerical solution of the neutron transport equation using cellular neural networks

Annals of Nuclear Energy ◽

10.1016/j.anucene.2008.11.003 ◽

2009 ◽

Vol 36 (1) ◽

pp. 15-27 ◽

Author(s):

Mehrdad Boroushaki

Keyword(s):

Neural Networks ◽

Numerical Solution ◽

Transport Equation ◽

Neutron Transport ◽

Cellular Neural Networks ◽

Neutron Transport Equation

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Application of Richardson Extrapolation to Numerical Solution of the Neutron Transport Equation

Nuclear Science and Engineering ◽

10.13182/nse88-a23553 ◽

1988 ◽

Vol 99 (2) ◽

pp. 123-132 ◽

Author(s):

E. J. Allen

Keyword(s):

Numerical Solution ◽

Transport Equation ◽

Neutron Transport ◽

Richardson Extrapolation ◽

Neutron Transport Equation

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Numerical solution of the time dependent neutron transport equation by the method of the characteristics

Journal of Computational Physics ◽

10.1016/j.jcp.2012.12.020 ◽

2013 ◽

Vol 240 ◽

pp. 248-267 ◽

Author(s):

Alberto Talamo

Keyword(s):

Numerical Solution ◽

Transport Equation ◽

Neutron Transport ◽

Time Dependent ◽

Neutron Transport Equation

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Discontinuous isogeometric analysis methods for the first-order form of the neutron transport equation with discrete ordinate (S) angular discretisation

Journal of Computational Physics ◽

10.1016/j.jcp.2016.03.060 ◽

2016 ◽

Vol 315 ◽

pp. 501-535 ◽

Author(s):

A.R. Owens ◽

J.A. Welch ◽

J. Kópházi ◽

M.D. Eaton

Keyword(s):

Transport Equation ◽

Isogeometric Analysis ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Discrete Ordinate ◽

First Order ◽

Analysis Methods

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A mesh-free treatment for even parity neutron transport equation

Annals of Nuclear Energy ◽

10.1016/j.anucene.2021.108292 ◽

2021 ◽

Vol 158 ◽

pp. 108292

Author(s):

A. Alizadeh ◽

M. Abbasi ◽

A. Minuchehr ◽

A. Zolfaghari

Keyword(s):

Transport Equation ◽

Neutron Transport ◽

Neutron Transport Equation ◽

Mesh Free ◽

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