TY - JOUR
T1 - Development, verification, and validation of the parallel transport code AZTRAN
AU - Duran-Gonzalez, Julian
AU - del Valle-Gallegos, Edmundo
AU - Reyes-Fuentes, Melisa
AU - Gomez-Torres, Armando
AU - Xolocostli-Munguia, Vicente
N1 - Publisher Copyright:
© 2021 Elsevier Ltd
PY - 2021/7
Y1 - 2021/7
N2 - AZTRAN is a 3D parallel SN neutron transport code developed for the AZTLAN Platform project, an initiative devoted to developing a Mexican platform for analysis and design of nuclear reactors. AZTRAN solves the multi-group discrete-ordinates form of the neutron transport equation in 3D Cartesian geometry applying the nodal RTN-0 method and the domain decomposition method for its parallelization. To verify and start the validation process, the C5G7 MOX Benchmarks were used. The accuracy of the serial solver was demonstrated by comparing the numerical results of the keff and normalized pin powers with the reference solutions. Excellent agreement and good consistency were obtained, showing errors reduce as the spatial and angular discretizations refine. The parallel implementation is also demonstrated. The speed-up is significant as the number of processors increases without losing quality in the numerical results and reaching efficiencies over 80% in the 2D cases and 85% in the 3D cases.
AB - AZTRAN is a 3D parallel SN neutron transport code developed for the AZTLAN Platform project, an initiative devoted to developing a Mexican platform for analysis and design of nuclear reactors. AZTRAN solves the multi-group discrete-ordinates form of the neutron transport equation in 3D Cartesian geometry applying the nodal RTN-0 method and the domain decomposition method for its parallelization. To verify and start the validation process, the C5G7 MOX Benchmarks were used. The accuracy of the serial solver was demonstrated by comparing the numerical results of the keff and normalized pin powers with the reference solutions. Excellent agreement and good consistency were obtained, showing errors reduce as the spatial and angular discretizations refine. The parallel implementation is also demonstrated. The speed-up is significant as the number of processors increases without losing quality in the numerical results and reaching efficiencies over 80% in the 2D cases and 85% in the 3D cases.
KW - C5G7 benchmarks
KW - Discrete-ordinates code
KW - Neutron transport code
KW - Parallel code with domain decomposition
UR - http://www.scopus.com/inward/record.url?scp=85107064357&partnerID=8YFLogxK
U2 - 10.1016/j.pnucene.2021.103792
DO - 10.1016/j.pnucene.2021.103792
M3 - Artículo
AN - SCOPUS:85107064357
SN - 0149-1970
VL - 137
JO - Progress in Nuclear Energy
JF - Progress in Nuclear Energy
M1 - 103792
ER -