Development and benchmarking of a point detector in OpenMC

Itay Horin; Or Alon; Arik Kreisel; Tsviki Y. Hirsh; Tamar Dayan; Hallel Fuks

doi:10.1016/j.anucene.2025.111497

Development and benchmarking of a point detector in OpenMC

Itay Horin, Or Alon, Arik Kreisel, Tsviki Y. Hirsh, Tamar Dayan, Hallel Fuks

Department of Particle Physics and Astrophysics

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

Abstract

This study presents the development and benchmarking of a point detector in the OpenMC framework. The detector efficiently estimates neutron flux at a point, employing a relativistic formulation that is valid across all energy ranges. This is the first implementation of a point detector tally in OpenMC, validated through tests, that demonstrate excellent agreement with conventional methods. By enhancing simulation efficiency in challenging scenarios such as heavy shielding this work broadens OpenMC's applicability to a wide range of geometries and nuclear physics reactions.

Original language	English
Article number	111497
Number of pages	9
Journal	Annals of Nuclear Energy
Volume	220
DOIs	https://doi.org/10.1016/j.anucene.2025.111497
Publication status	Published - 15 Sept 2025

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering

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10.1016/j.anucene.2025.111497Licence: CC BY-NC

Cite this

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abstract = "This study presents the development and benchmarking of a point detector in the OpenMC framework. The detector efficiently estimates neutron flux at a point, employing a relativistic formulation that is valid across all energy ranges. This is the first implementation of a point detector tally in OpenMC, validated through tests, that demonstrate excellent agreement with conventional methods. By enhancing simulation efficiency in challenging scenarios such as heavy shielding this work broadens OpenMC's applicability to a wide range of geometries and nuclear physics reactions.",

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AU - Alon, Or

AU - Kreisel, Arik

AU - Hirsh, Tsviki Y.

AU - Dayan, Tamar

AU - Fuks, Hallel

PY - 2025/9/15

Y1 - 2025/9/15

N2 - This study presents the development and benchmarking of a point detector in the OpenMC framework. The detector efficiently estimates neutron flux at a point, employing a relativistic formulation that is valid across all energy ranges. This is the first implementation of a point detector tally in OpenMC, validated through tests, that demonstrate excellent agreement with conventional methods. By enhancing simulation efficiency in challenging scenarios such as heavy shielding this work broadens OpenMC's applicability to a wide range of geometries and nuclear physics reactions.

AB - This study presents the development and benchmarking of a point detector in the OpenMC framework. The detector efficiently estimates neutron flux at a point, employing a relativistic formulation that is valid across all energy ranges. This is the first implementation of a point detector tally in OpenMC, validated through tests, that demonstrate excellent agreement with conventional methods. By enhancing simulation efficiency in challenging scenarios such as heavy shielding this work broadens OpenMC's applicability to a wide range of geometries and nuclear physics reactions.

UR - https://www.scopus.com/pages/publications/105003371493

U2 - 10.1016/j.anucene.2025.111497

DO - 10.1016/j.anucene.2025.111497

M3 - Article

SN - 0306-4549

VL - 220

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

M1 - 111497

ER -

Development and benchmarking of a point detector in OpenMC

Abstract

All Science Journal Classification (ASJC) codes

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