Itay Horin , Or Alon , Arik Kreisel , Tsviki Y. Hirsh , Tamar Dayan , Hallel Fuks
{"title":"Development and benchmarking of a point detector in OpenMC","authors":"Itay Horin , Or Alon , Arik Kreisel , Tsviki Y. Hirsh , Tamar Dayan , Hallel Fuks","doi":"10.1016/j.anucene.2025.111497","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111497"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925003147","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
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.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.