Development, verification, and validation of the parallel transport code AZTRAN

Julian Duran-Gonzalez; Edmundo del Valle-Gallegos; Melisa Reyes-Fuentes; Armando Gomez-Torres; Vicente Xolocostli-Munguia

doi:10.1016/j.pnucene.2021.103792

Development, verification, and validation of the parallel transport code AZTRAN

Julian Duran-Gonzalez, Edmundo del Valle-Gallegos, Melisa Reyes-Fuentes, Armando Gomez-Torres, Vicente Xolocostli-Munguia

Escuela Superior de Física y Matemáticas (ESFM)

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

AZTRAN is a 3D parallel S_N 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.

Translated title of the contribution	Desarrollo, verificación y validación del código de transporte paralelo AZTRAN
Original language	English
Article number	103792
Journal	Progress in Nuclear Energy
Volume	137
DOIs	https://doi.org/10.1016/j.pnucene.2021.103792
State	Published - Jul 2021

Keywords

C5G7 benchmarks
Discrete-ordinates code
Neutron transport code
Parallel code with domain decomposition

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10.1016/j.pnucene.2021.103792

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title = "Development, verification, and validation of the parallel transport code AZTRAN",

abstract = "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.",

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AU - Duran-Gonzalez, Julian

AU - del Valle-Gallegos, Edmundo

AU - Reyes-Fuentes, Melisa

AU - Gomez-Torres, Armando

AU - Xolocostli-Munguia, Vicente

PY - 2021/7

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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.

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KW - Discrete-ordinates code

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JO - Progress in Nuclear Energy

JF - Progress in Nuclear Energy

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Development, verification, and validation of the parallel transport code AZTRAN

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Keywords

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