Vectorization of a 2D–1D Iterative Algorithm for the 3D Neutron Transport Problem in Prismatic Geometries

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo ◽

10.1051/snamc/201404102 ◽

2014 ◽

Author(s):

Salli Moustafa ◽

François Févotte ◽

Bruno Lathuilière ◽

Laurent Plagne

Keyword(s):

Iterative Algorithm ◽

Neutron Transport ◽

Transport Problem

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Positive solution of a time and energy dependent neutron transport problem

Journal of Mathematical Physics ◽

10.1063/1.522451 ◽

1975 ◽

Vol 16 (10) ◽

pp. 2166-2171 ◽

Author(s):

C. V. Pao

Keyword(s):

Positive Solution ◽

Neutron Transport ◽

Transport Problem ◽

Energy Dependent ◽

Time And Energy

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Nonmonotonic behavior of the ‘C’ eigenvalue of the one-speed neutron transport problem in two-dimensional cylindrical (R,Z) geometry

Transport Theory and Statistical Physics ◽

10.1080/00411459408203931 ◽

1994 ◽

Vol 23 (6) ◽

pp. 893-906 ◽

Author(s):

A. K. Kulkarni ◽

S. D. Paranjape ◽

V. Kumar ◽

D. C. Sahni

Keyword(s):

Neutron Transport ◽

Transport Problem ◽

Two Dimensional ◽

The One ◽

Nonmonotonic Behavior

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An analytical approach for a nodal formulation of a two-dimensional fixed-source neutron transport problem in heterogeneous medium

Kerntechnik ◽

10.3139/124.110468 ◽

2015 ◽

Vol 80 (2) ◽

pp. 167-173 ◽

Author(s):

L. B. Barichello ◽

R. D. da Cunha ◽

C. B. Picoloto ◽

A. Tres

Keyword(s):

Analytical Approach ◽

Heterogeneous Medium ◽

Neutron Transport ◽

Transport Problem ◽

Two Dimensional ◽

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Transmission probability method based on triangle meshes for solving unstructured geometry neutron transport problem

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2006.04.031 ◽

2007 ◽

Vol 237 (1) ◽

pp. 28-37 ◽

Author(s):

Wu Hongchun ◽

Liu Pingping ◽

Zhou Yongqiang ◽

Cao Liangzhi

Keyword(s):

Neutron Transport ◽

Transmission Probability ◽

Transport Problem ◽

Probability Method ◽

Triangle Meshes

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Implementation and performance study of lpCMFD acceleration method for multi-energy group k-eigenvalue neutron transport problem in hexagonal geometry

Annals of Nuclear Energy ◽

10.1016/j.anucene.2019.107220 ◽

2020 ◽

Vol 139 ◽

pp. 107220 ◽

Author(s):

Yimeng Chan ◽

Sicong Xiao

Keyword(s):

Neutron Transport ◽

Transport Problem ◽

Performance Study ◽

Energy Group ◽

Acceleration Method ◽

And Performance

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Existence Result for the Kinetic Neutron Transport Problem in the Presence of Delayed Neutrons

Transport Theory and Statistical Physics ◽

10.1080/00411450600901748 ◽

2006 ◽

Vol 35 (3-4) ◽

pp. 137-156 ◽

Author(s):

Lahbib Bourhrara ◽

Richard Sanchez

Keyword(s):

Existence Result ◽

Neutron Transport ◽

Transport Problem ◽

Delayed Neutrons

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TN approximation on the critical size of time-dependent, one-speed and one-dimensional neutron transport problem with anisotropic scattering

Annals of Nuclear Energy ◽

10.1016/j.anucene.2009.01.012 ◽

2009 ◽

Vol 36 (5) ◽

pp. 575-582 ◽

Author(s):

Hakan Öztürk ◽

Süleyman Güngör

Keyword(s):

Critical Size ◽

Neutron Transport ◽

Anisotropic Scattering ◽

Transport Problem ◽

Time Dependent ◽

One Dimensional

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Solution of the Initial‐Value Neutron‐Transport Problem for a Slab with Infinite Reflectors

Journal of Mathematical Physics ◽

10.1063/1.1665409 ◽

1970 ◽

Vol 11 (8) ◽

pp. 2445-2458 ◽

Author(s):

Perry A. Newman ◽

Robert L. Bowden

Keyword(s):

Neutron Transport ◽

Transport Problem ◽

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Time-dependentX- andY-functions for an isotropically scattering neutron transport problem in a finite slab

Astrophysics and Space Science ◽

10.1007/bf00644428 ◽

1991 ◽

Vol 175 (1) ◽

pp. 107-118

Author(s):

S. Karanjai ◽

G. Biswas

Keyword(s):

Neutron Transport ◽

Transport Problem ◽

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A three‐dimensional neutron transport problem

Journal of Mathematical Physics ◽

10.1063/1.522760 ◽

1975 ◽

Vol 16 (9) ◽

pp. 1840-1843

Author(s):

Luigi Mangiarotti

Keyword(s):

Neutron Transport ◽

Three Dimensional ◽

Transport Problem

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