Application of material-mesh algebraic collapsing acceleration technique in method of characteristics–based neutron transport code

Neutron Transport ◽

Acceleration Technique ◽

Application of Krylov Acceleration Technique in Method of Characteristics–Based Neutron Transport Code

Nuclear Science and Engineering ◽

10.1080/00295639.2018.1499340 ◽

2018 ◽

Vol 192 (2) ◽

pp. 153-188 ◽

Cited By ~ 3

Author(s):

Tanay Mazumdar ◽

Anurag Gupta

Keyword(s):

Neutron Transport ◽

Acceleration Technique ◽

Transport Code ◽

Krylov Acceleration

Recent validation study of a Method of Characteristics based Neutron Transport Code

Life Cycle Reliability and Safety Engineering ◽

10.1007/s41872-020-00124-1 ◽

2020 ◽

Vol 9 (2) ◽

pp. 171-180

Author(s):

Tanay Mazumdar ◽

Tej Singh

Keyword(s):

Validation Study ◽

Neutron Transport ◽

Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2008.04.014 ◽

2008 ◽

Vol 238 (10) ◽

pp. 2828-2833 ◽

Cited By ~ 30

Author(s):

Qichang Chen ◽

Hongchun Wu ◽

Liangzhi Cao

Keyword(s):

Neutron Transport ◽

Arbitrary Geometry ◽

Gemma: Development of a two-dimensional neutron transport code with the method of characteristics

10.1016/j.anucene.2018.01.043 ◽

2018 ◽

Vol 115 ◽

pp. 367-376

Author(s):

Guillermo Ibarra Reyes ◽

Samuel Vargas Escamilla ◽

Armando Miguel Gómez Torres ◽

Edmundo del Valle Gallegos

Keyword(s):

Neutron Transport ◽

Two Dimensional ◽

DIAMOND – A Method of Characteristics neutron transport code using unstructured meshing

10.1016/j.anucene.2019.107086 ◽

2020 ◽

Vol 137 ◽

pp. 107086

Author(s):

Lakshay Jain ◽

Ramamoorthy Karthikeyan ◽

Umasankari Kannan

Keyword(s):

Neutron Transport ◽

Transport Code ◽

Unstructured Meshing

ANEMONA — a neutron transport code for general geometry reactor assemblies based on the method of characteristics and R-function solid modeler

10.1016/s0306-4549(00)00038-4 ◽

2001 ◽

Vol 28 (2) ◽

pp. 125-152 ◽

Cited By ~ 24

Author(s):

T. Jevremovic ◽

J. Vujic ◽

K. Tsuda

Keyword(s):

Neutron Transport ◽

Transport Code ◽

General Geometry ◽

Solid Modeler

Development of high-fidelity neutron transport code STREAM

Computer Physics Communications ◽

10.1016/j.cpc.2021.107915 ◽

2021 ◽

pp. 107915

Author(s):

Sooyoung Choi ◽

Wonkyeong Kim ◽

Jiwon Choe ◽

Woonghee Lee ◽

Hanjoo Kim ◽

...

Keyword(s):

Neutron Transport ◽

High Fidelity ◽

Generalized Equivalence Theory Used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport

Nuclear Science and Engineering ◽

10.1080/00295639.2020.1765606 ◽

2020 ◽

Vol 194 (11) ◽

pp. 1044-1055 ◽

Cited By ~ 1

Author(s):

Guillaume Giudicelli ◽

Kord Smith ◽

Benoit Forget

Keyword(s):

Neutron Transport ◽

Equivalence Theory

Solution of the neutron transport equation by the Method of Characteristics using a linear representation of the source within a mesh

10.1016/j.anucene.2017.04.011 ◽

2017 ◽

Vol 108 ◽

pp. 132-150 ◽

Cited By ~ 7

Author(s):

Tanay Mazumdar ◽

S.B. Degweker

Keyword(s):

Transport Equation ◽

Neutron Transport ◽

Linear Representation ◽

Neutron Transport Equation ◽

The Method Of Characteristics

Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation

Computer Physics Communications ◽

10.1016/j.cpc.2020.107332 ◽

2021 ◽

Vol 260 ◽

pp. 107332 ◽

Cited By ~ 1

Author(s):

Sooyoung Choi ◽

Deokjung Lee

Keyword(s):

Neutron Transport ◽

Three Dimensional ◽

Analysis Method ◽

Transport Calculation ◽

Transport Analysis