Numerical solution of the neutron diffusion equations as eigenvalue problem in the nuclear reactors using GDQ method

Gholam Reza Ansarifar; Saeed Mohammadi Alavijeh

doi:10.1504/ijnest.2016.10002887

Numerical solution of the neutron diffusion equations as eigenvalue problem in the nuclear reactors using GDQ method

International Journal of Nuclear Energy Science and Technology ◽

10.1504/ijnest.2016.10002887 ◽

2016 ◽

Vol 10 (4) ◽

pp. 302

Author(s):

Gholam Reza Ansarifar ◽

Saeed Mohammadi Alavijeh

Keyword(s):

Eigenvalue Problem ◽

Numerical Solution ◽

Nuclear Reactors ◽

Diffusion Equations ◽

Neutron Diffusion

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Numerical solution of the neutron diffusion equations as eigenvalue problem in the nuclear reactors using GDQ method

International Journal of Nuclear Energy Science and Technology ◽

10.1504/ijnest.2016.081992 ◽

2016 ◽

Vol 10 (4) ◽

pp. 302

Author(s):

Gholam Reza Ansarifar ◽

Saeed Mohammadi Alavijeh

Keyword(s):

Eigenvalue Problem ◽

Numerical Solution ◽

Nuclear Reactors ◽

Diffusion Equations ◽

Neutron Diffusion

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Numerical solution of the 2D-neutron diffusion equations of a non-rectangular computational area with the wave digital concept

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2009.03.016 ◽

2009 ◽

Vol 239 (7) ◽

pp. 1275-1284

Author(s):

Thomas Lutter

Keyword(s):

Numerical Solution ◽

Diffusion Equations ◽

Neutron Diffusion

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Numerical Solution of Neutron Diffusion Equations in Multiconnected Regions Using Compound Boundary-Fitted Coordinate Systems

Nuclear Science and Engineering ◽

10.13182/nse86-a17863 ◽

1986 ◽

Vol 92 (1) ◽

pp. 42-50 ◽

Cited By ~ 2

Author(s):

Motoo Aoyama ◽

Sadao Uchikawa

Keyword(s):

Numerical Solution ◽

Diffusion Equations ◽

Neutron Diffusion ◽

Coordinate Systems

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Numerical Solution of the Time- and Space-Dependent Multigroup Neutron Diffusion Equations

Nuclear Science and Engineering ◽

10.13182/nse70-a18881 ◽

1970 ◽

Vol 40 (1) ◽

pp. 91-100

Author(s):

W. R. Rhyne ◽

A. C. Lapsley

Keyword(s):

Numerical Solution ◽

Diffusion Equations ◽

Neutron Diffusion ◽

Time And Space ◽

Multigroup Neutron

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THE TWENTY GRAND PROGRAM FOR THE NUMERICAL SOLUTION OF FEW-GROUP NEUTRON DIFFUSION EQUATIONS IN TWO DIMENSIONS

10.2172/4792907 ◽

1962 ◽

Cited By ~ 2

Author(s):

M.L. Tobias ◽

T.B. Fowler

Keyword(s):

Numerical Solution ◽

Two Dimensions ◽

Diffusion Equations ◽

Neutron Diffusion

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Polynomial nodal method for solving neutron diffusion equations in hexagonal-z geometry

Annals of Nuclear Energy ◽

10.1016/s0306-4549(01)00083-4 ◽

2002 ◽

Vol 29 (9) ◽

pp. 1105-1117 ◽

Cited By ~ 11

Author(s):

Vyacheslav G. Zimin ◽

Denis M. Baturin

Keyword(s):

Diffusion Equations ◽

Neutron Diffusion ◽

Nodal Method

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A Hierarchical Domain Decomposition Boundary Element Method Applied to the Multiregion Problems of Neutron Diffusion Equations

Nuclear Science and Engineering ◽

10.13182/nse98-a1966 ◽

1998 ◽

Vol 129 (1) ◽

pp. 88-96 ◽

Cited By ~ 14

Author(s):

M. Dhandhang Purwadi ◽

M. Tsuji ◽

M. Narita ◽

M. Itagaki

Keyword(s):

Boundary Element Method ◽

Domain Decomposition ◽

Boundary Element ◽

Diffusion Equations ◽

Neutron Diffusion ◽

Element Method

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Numerical Solution of the Inverse Eigenvalue Problem for Real Symmetric Toeplitz Matrices

SIAM Journal on Scientific Computing ◽

10.1137/s1064827595280673 ◽

1997 ◽

Vol 18 (6) ◽

pp. 1722-1736 ◽

Cited By ~ 32

Author(s):

William F. Trench

Keyword(s):

Eigenvalue Problem ◽

Numerical Solution ◽

Toeplitz Matrices ◽

Inverse Eigenvalue Problem ◽

Inverse Eigenvalue

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An error analysis for a numerical solution of the eigenvalue problem for compact positive operators

Numerical Treatment of Integral Equations / Numerische Behandlung von Integralgleichungen ◽

10.1007/978-3-0348-6314-8_10 ◽

1980 ◽

pp. 151-156

Author(s):

D. Kershaw

Keyword(s):

Eigenvalue Problem ◽

Error Analysis ◽

Numerical Solution ◽

Positive Operators

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The numerical analysis of eigenvalue problem solutions in the multigroup neutron diffusion theory

Progress in Nuclear Energy ◽

10.1016/s0149-1970(96)00026-1 ◽

1998 ◽

Vol 33 (3) ◽

pp. 301-391 ◽

Cited By ~ 4

Author(s):

Zbigniew I. Woźnicki

Keyword(s):

Numerical Analysis ◽

Eigenvalue Problem ◽

Diffusion Theory ◽

Neutron Diffusion ◽

Multigroup Neutron

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