{"title":"Evaluation of effective kinetic parameters and adjoint flux distribution using iterated fission probability in the iMC Monte Carlo code","authors":"","doi":"10.1016/j.anucene.2024.110878","DOIUrl":null,"url":null,"abstract":"<div><p>The iterated fission probability (IFP) method enables assessment of adjoint flux-weighted kinetic parameters, i.e., effective kinetic parameters, in Monte Carlo (MC) simulation, an essential capability in modern MC codes. This method can be extended to calculate adjoint flux-weighted quantities within a prescribed phase-space, enabling the estimation of adjoint flux distributions. The iMC Monte Carlo code, developed at the Korea Advanced Institute of Science and Technology (KAIST), is proficient in both calculating effective kinetic parameters and adjoint flux distributions. This paper presents benchmark results verifying the code’s capabilities. Critical device configurations are considered for evaluating kinetic parameters, compared with the Serpent2 code results. Both multi-group and continuous-energy benchmarks are solved to assess IFP-based spatial- and energy-wise adjoint flux distributions, and comparison is made against deterministic transport calculations. Results show that effective kinetic parameters can be accurately estimated, and acceptable adjoint flux distributions can be obtained using the iMC code.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-08-30","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/S0306454924005413","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
The iterated fission probability (IFP) method enables assessment of adjoint flux-weighted kinetic parameters, i.e., effective kinetic parameters, in Monte Carlo (MC) simulation, an essential capability in modern MC codes. This method can be extended to calculate adjoint flux-weighted quantities within a prescribed phase-space, enabling the estimation of adjoint flux distributions. The iMC Monte Carlo code, developed at the Korea Advanced Institute of Science and Technology (KAIST), is proficient in both calculating effective kinetic parameters and adjoint flux distributions. This paper presents benchmark results verifying the code’s capabilities. Critical device configurations are considered for evaluating kinetic parameters, compared with the Serpent2 code results. Both multi-group and continuous-energy benchmarks are solved to assess IFP-based spatial- and energy-wise adjoint flux distributions, and comparison is made against deterministic transport calculations. Results show that effective kinetic parameters can be accurately estimated, and acceptable adjoint flux distributions can be obtained using the iMC code.
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.