Jinchao Zhang , Qian Zhang , Shuai Qin , Wei Cao , Shifu Wu , Qiang Zhao , Kun Zhuang
{"title":"A novel method to estimate the high-order flux moment under the isotropic source assumption","authors":"Jinchao Zhang , Qian Zhang , Shuai Qin , Wei Cao , Shifu Wu , Qiang Zhao , Kun Zhuang","doi":"10.1016/j.anucene.2025.111840","DOIUrl":null,"url":null,"abstract":"<div><div>Collapsing coarse-group high-order scattering matrix using the accurate flux moment is important for the fast reactor calculations. However, current methods for calculating the flux moment are time-consuming because of the treatment of the anisotropic source and the slow convergence rate. To address this issue, this study proposes a novel method to estimate the high-order flux moment based on the isotropic source assumption. The transport equation is solved using the Method of Characteristics transport method under the time-saving isotropic source assumption. The flux moment is calculated with the angular flux saved during the source iterations and is used to collapse coarse-group high-order scattering matrix as an approximation of the actual flux moment.</div><div>To validate the proposed method, two simplified problems are used to assess its performance and two 2-D fast reactor problems are employed to explore its range of applicability. Numerical results for the simplified problems indicate that the high-order scattering matrix collapsed using the proposed method achieves accuracy comparable to that obtained under the anisotropic source assumption. For the 2-D problems, the results demonstrate the effectiveness of the proposed method, with the eigenvalue error within −200 pcm and the maximum relative error of assembly power within 1%. These findings highlight the accuracy and efficiency of the proposed method in predicting the flux moment.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111840"},"PeriodicalIF":2.3000,"publicationDate":"2025-09-05","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/S0306454925006577","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
Collapsing coarse-group high-order scattering matrix using the accurate flux moment is important for the fast reactor calculations. However, current methods for calculating the flux moment are time-consuming because of the treatment of the anisotropic source and the slow convergence rate. To address this issue, this study proposes a novel method to estimate the high-order flux moment based on the isotropic source assumption. The transport equation is solved using the Method of Characteristics transport method under the time-saving isotropic source assumption. The flux moment is calculated with the angular flux saved during the source iterations and is used to collapse coarse-group high-order scattering matrix as an approximation of the actual flux moment.
To validate the proposed method, two simplified problems are used to assess its performance and two 2-D fast reactor problems are employed to explore its range of applicability. Numerical results for the simplified problems indicate that the high-order scattering matrix collapsed using the proposed method achieves accuracy comparable to that obtained under the anisotropic source assumption. For the 2-D problems, the results demonstrate the effectiveness of the proposed method, with the eigenvalue error within −200 pcm and the maximum relative error of assembly power within 1%. These findings highlight the accuracy and efficiency of the proposed method in predicting the flux moment.
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.