Error Analysis of the Nodal Integral Method for Solving the Neutron Diffusion Equation in Two-Dimensional Cartesian Geometry

Nodal Integral method for multi-group neutron diffusion equation in three dimensional cylindrical coordinate system

10.1016/j.anucene.2020.107904 ◽

2021 ◽

Vol 151 ◽

pp. 107904

Author(s):

Manish Raj ◽

Suneet Singh

Keyword(s):

Diffusion Equation ◽

Coordinate System ◽

Integral Method ◽

Three Dimensional ◽

Cylindrical Coordinate System ◽

Neutron Diffusion ◽

Cylindrical Coordinate ◽

Nodal Integral Method ◽

Solution of neutron diffusion equation in 2d polar (r,θ) coordinates using Nodal Integral Method

10.1016/j.anucene.2017.02.025 ◽

2017 ◽

Vol 105 ◽

pp. 69-78 ◽

Cited By ~ 1

Author(s):

Manish Raj ◽

Suneet Singh

Keyword(s):

Diffusion Equation ◽

Integral Method ◽

Neutron Diffusion ◽

Nodal Integral Method ◽

Error Analysis of the Nodal Expansion Method for Solving the Neutron Diffusion Equation

Nuclear Science and Engineering ◽

10.13182/nse97-a24275 ◽

1997 ◽

Vol 125 (3) ◽

pp. 284-299 ◽

Cited By ~ 1

Author(s):

R. Christian Penland ◽

Yousry Y. Azmy ◽

Paul J. Turinsky

Keyword(s):

Diffusion Equation ◽

Error Analysis ◽

Expansion Method ◽

Neutron Diffusion ◽

Nodal Expansion Method ◽

Solution of Two-Dimensional Neutron Diffusion Equation for Triangular Region by Finite Fourier Transformation

Journal of Nuclear Science and Technology ◽

10.1080/18811248.1978.9733194 ◽

1978 ◽

Vol 15 (1) ◽

pp. 1-9 ◽

Cited By ~ 3

Author(s):

Keisuke KOBAYASHI ◽

Hideo ISHIBASHI

Keyword(s):

Diffusion Equation ◽

Fourier Transformation ◽

Neutron Diffusion ◽

Two Dimensional ◽

Triangular Region ◽

A New Method for the Numerical Solution of the Two-Dimensional Neutron Diffusion Equation

Nuclear Science and Engineering ◽

10.13182/nse75-a40342 ◽

1975 ◽

Vol 57 (1) ◽

pp. 53-62 ◽

Cited By ~ 2

Author(s):

Katsutada Aoki ◽

Makoto Tsuiki

Keyword(s):

Diffusion Equation ◽

Numerical Solution ◽

New Method ◽

Neutron Diffusion ◽

Two Dimensional ◽

A numerical method for solving the two-dimensional neutron diffusion equation

Journal of Nuclear Energy (1954) ◽

10.1016/0891-3919(55)90044-9 ◽

1956 ◽

Vol 2 (3-4) ◽

pp. 277-285

Author(s):

R.M. Pearce

Keyword(s):

Diffusion Equation ◽

Numerical Method ◽

Neutron Diffusion ◽

Two Dimensional ◽

Solving the static-neutron diffusion equation in 2D-Cartesian geometry with Lagrange interpolation

10.1016/j.anucene.2013.11.013 ◽

2014 ◽

Vol 65 ◽

pp. 370-375 ◽

Cited By ~ 4

Author(s):

Barbaro Quintero-Leyva

Keyword(s):

Diffusion Equation ◽

Lagrange Interpolation ◽

Neutron Diffusion ◽

Cartesian Geometry ◽

A new moving-mesh Finite Volume Method for the efficient solution of two-dimensional neutron diffusion equation using gradient variations of reactor power

Nuclear Engineering and Technology ◽

10.1016/j.net.2019.02.011 ◽

2019 ◽

Vol 51 (5) ◽

pp. 1181-1194

Author(s):

Mehran Vagheian ◽

Dariush Rezaei Ochbelagh ◽

Morteza Gharib

Keyword(s):

Diffusion Equation ◽

Finite Volume Method ◽

Finite Volume ◽

Efficient Solution ◽

Reactor Power ◽

Moving Mesh ◽

Neutron Diffusion ◽

Two Dimensional ◽

Volume Method ◽

On an improved Direct Discrete Method and its application in two dimensional multi-group neutron diffusion equation

10.1016/j.anucene.2012.01.014 ◽

2012 ◽

Vol 44 ◽

pp. 1-7 ◽

Cited By ~ 6

Author(s):

Seyed Mohsen Ayyoubzadeh ◽

Naser Vosoughi ◽

Seyed Mohammad Ayyoubzadeh

Keyword(s):

Diffusion Equation ◽

Neutron Diffusion ◽

Two Dimensional ◽

Discrete Method ◽

PERTURBATIVE ANALYSIS OF THE STEADY STATE MULTI-GROUP MULTI-LAYER NEUTRON DIFFUSION EQUATION IN CARTESIAN GEOMETRY BY FICTITIOUS BORDERS POWER METHOD

10.26678/abcm.encit2016.cit2016-0020 ◽

2016 ◽

Author(s):

Rodrigo Zanette ◽

Claudio Zen Petersen ◽

Welton Menezes

Keyword(s):

Steady State ◽

Diffusion Equation ◽

Power Method ◽

Neutron Diffusion ◽

Cartesian Geometry ◽