Verification of the Parallel Transport Codes Parafish and AZTRAN with the TAKEDA Benchmarks

Julian Duran-Gonzalez, Victor Hugo Sanchez-Espinoza, Luigi Mercatali, Armando Gomez-Torres and Edmundo del Valle-Gallegos
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Julian Duran-Gonzalez: Karlsruhe Institute of Technology (KIT), Institute of Neutron Physics and Reactor Technology (INR), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany
Victor Hugo Sanchez-Espinoza: Karlsruhe Institute of Technology (KIT), Institute of Neutron Physics and Reactor Technology (INR), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany
Luigi Mercatali: Karlsruhe Institute of Technology (KIT), Institute of Neutron Physics and Reactor Technology (INR), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany
Armando Gomez-Torres: Instituto Nacional de Investigaciones Nucleares, Departamento de Sistemas Nucleares, Carretera México-Toluca S/N, Ocoyoacac 52750, Mexico
Edmundo del Valle-Gallegos: Instituto Politécnico Nacional, Escuela Superior de Física y Matemáticas, Av. IPN S/N, Alcaldía Gustavo A, Madero 07738, Mexico

Energies, 2022, vol. 15, issue 7, 1-16

Abstract: With the increase in computational resources, parallel computation in neutron transport codes is inherent since it allows simulations with high spatial-angular resolution. Among the different methodologies available for the solution of the neutron transport equation, spherical harmonics ( P N ) and discrete-ordinates ( S N ) approximations have been widely used, as they are established classical methods for performing nuclear reactor calculations. This work focuses on describing and verifying two parallel deterministic neutron transport codes under development. The first one is the Parafish code that is based on the finite-element method and P N approximation. The second one is the AZTRAN code, based on the RTN-0 nodal method and S N approximation. The capabilities of these two codes have been tested on the TAKEDA benchmarks and the results obtained show good behavior and accuracy compared to the Monte Carlo reference solutions. Additionally, the speedup obtained by each code in the parallel execution is acceptable. In general, the results encourage further improvement in the codes to be comparable to other well-validated deterministic transport codes.

Keywords: Neutron transport equation; Spherical Harmonics ( P N ); Finite Element Method; Discrete Ordinates ( S N ); RTN-0 Nodal method (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2022
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