Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor

The multigroup Monte Carlo (MC) neutron transport method with a regionwise even-parity discontinuity factor (REPDF), i.e. the discontinuity factor (DF)–MC method, is developed with the aim to provide a reference solution for deterministic transport calculations with DF. Applying the analogy with optics, neutrons are transmitted or reflected at a region surface during random walks. The probability of transmission or reflection is determined by REPDFs in adjacent regions. The DF is traditionally used in deterministic neutron transport methods to reduce the discretization error due to spatial homogenization and energy condensation. The DF-MC method can treat DF in the framework of the multigroup MC method.

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Publication Details

Journal
Nuclear Science and Engineering
Published
2024-08-26
DOI
https://doi.org/10.1080/00295639.2024.2383102
Citations
1
Primary Topic
Nuclear Physics and Applications
Type
article
Field-Weighted Citation Impact
0.61
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Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor

Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto
1 citations
Nuclear Science and Engineering
Nuclear Physics and Applications
0.61
article

Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor

Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto
article en
1 citations

Abstract

The multigroup Monte Carlo (MC) neutron transport method with a regionwise even-parity discontinuity factor (REPDF), i.e. the discontinuity factor (DF)–MC method, is developed with the aim to provide a reference solution for deterministic transport calculations with DF. Applying the analogy with optics, neutrons are transmitted or reflected at a region surface during random walks. The probability of transmission or reflection is determined by REPDFs in adjacent regions. The DF is traditionally used in deterministic neutron transport methods to reduce the discretization error due to spatial homogenization and energy condensation. The DF-MC method can treat DF in the framework of the multigroup MC method.

Nuclear Science and EngineeringVol. 199(4)
Nagoya University (JP)
Openalex Percentile: Top 32%
Nuclear Physics and Applications
0.61
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