{"title":"非结构化几何反应器的建模和通量重建","authors":"","doi":"10.1016/j.anucene.2024.110815","DOIUrl":null,"url":null,"abstract":"<div><p>Innovative reactors are typically designed with complex geometric structures, which put forward higher requirements for deterministic reactor core calculation. In the complex geometric reactor core calculation, the LAVENDER code in the SARAX code system was used, which is based on the three-dimensional neutron transport nodal method. A modeling method based on constructive solid geometry was applied to generate arbitrary triangular-z meshes. To meet the requirements of coupling core physics calculation with thermal and other physics fields, a flux reconstruction method based on the statistics of biharmonic spline interpolation of Green’s function has been proposed, which was used to reconstruct the flux of specified region. Three reactors with different types were calculated to verify the accuracy of the flux reconstruction method. Numerical results show that the fluxes of specified region calculated by the proposed flux reconstruction method in the SARAX code were in good agreement with the direct full-core Monte-Carlo results.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Modeling and flux reconstruction of unstructured geometric reactor\",\"authors\":\"\",\"doi\":\"10.1016/j.anucene.2024.110815\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>Innovative reactors are typically designed with complex geometric structures, which put forward higher requirements for deterministic reactor core calculation. In the complex geometric reactor core calculation, the LAVENDER code in the SARAX code system was used, which is based on the three-dimensional neutron transport nodal method. A modeling method based on constructive solid geometry was applied to generate arbitrary triangular-z meshes. To meet the requirements of coupling core physics calculation with thermal and other physics fields, a flux reconstruction method based on the statistics of biharmonic spline interpolation of Green’s function has been proposed, which was used to reconstruct the flux of specified region. Three reactors with different types were calculated to verify the accuracy of the flux reconstruction method. Numerical results show that the fluxes of specified region calculated by the proposed flux reconstruction method in the SARAX code were in good agreement with the direct full-core Monte-Carlo results.</p></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-07-30\",\"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/S030645492400478X\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S030645492400478X","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}
Modeling and flux reconstruction of unstructured geometric reactor
Innovative reactors are typically designed with complex geometric structures, which put forward higher requirements for deterministic reactor core calculation. In the complex geometric reactor core calculation, the LAVENDER code in the SARAX code system was used, which is based on the three-dimensional neutron transport nodal method. A modeling method based on constructive solid geometry was applied to generate arbitrary triangular-z meshes. To meet the requirements of coupling core physics calculation with thermal and other physics fields, a flux reconstruction method based on the statistics of biharmonic spline interpolation of Green’s function has been proposed, which was used to reconstruct the flux of specified region. Three reactors with different types were calculated to verify the accuracy of the flux reconstruction method. Numerical results show that the fluxes of specified region calculated by the proposed flux reconstruction method in the SARAX code were in good agreement with the direct full-core Monte-Carlo results.
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.