Hongchun Wu , Shuaizheng Li , Jun Chen , Guangwen Bi , Zhouyu Liu , Sifan Zhang , Xinyu Zhou , Liangzhi Cao
{"title":"二维/一维和三维SN节点耦合中子输运计算方法","authors":"Hongchun Wu , Shuaizheng Li , Jun Chen , Guangwen Bi , Zhouyu Liu , Sifan Zhang , Xinyu Zhou , Liangzhi Cao","doi":"10.1016/j.anucene.2025.111663","DOIUrl":null,"url":null,"abstract":"<div><div>The 2D/1D neutron transport method is a popular approach for high-fidelity neutron transport calculations. For some research or testing reactors, the reactor core is surrounded by heavy water, and outside the heavy water is light water. To obtain the spectrum in the heavy water and light water outside the core, the heavy water and light water domains must be included in the calculation. This significantly affects the calculation time and convergence when using the 2D/1D method. Therefore, a new neutron transport method based on the 2D/1D method and the 3D SN nodal method is proposed to address these issues. In this method, the reactor core is divided into two calculation domains. The reactor active core is calculated by the 2D/1D method with fine meshes, while the region outside the reactor core is calculated by the 3D SN nodal method. The two calculation domains are coupled by the boundary angular flux. The CMFD and parallel scheme are also implemented to accelerate the calculations. This method is applied to the C5G7 benchmark and JRR-3 reactor core. The numerical tests show that the efficiency and convergence of the coupling method are much better than those of the 2D/1D method while maintaining accuracy.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111663"},"PeriodicalIF":2.3000,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"A neutron transport calculation approach via the coupling of 2D/1D and 3D SN nodal methods\",\"authors\":\"Hongchun Wu , Shuaizheng Li , Jun Chen , Guangwen Bi , Zhouyu Liu , Sifan Zhang , Xinyu Zhou , Liangzhi Cao\",\"doi\":\"10.1016/j.anucene.2025.111663\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The 2D/1D neutron transport method is a popular approach for high-fidelity neutron transport calculations. For some research or testing reactors, the reactor core is surrounded by heavy water, and outside the heavy water is light water. To obtain the spectrum in the heavy water and light water outside the core, the heavy water and light water domains must be included in the calculation. This significantly affects the calculation time and convergence when using the 2D/1D method. Therefore, a new neutron transport method based on the 2D/1D method and the 3D SN nodal method is proposed to address these issues. In this method, the reactor core is divided into two calculation domains. The reactor active core is calculated by the 2D/1D method with fine meshes, while the region outside the reactor core is calculated by the 3D SN nodal method. The two calculation domains are coupled by the boundary angular flux. The CMFD and parallel scheme are also implemented to accelerate the calculations. This method is applied to the C5G7 benchmark and JRR-3 reactor core. The numerical tests show that the efficiency and convergence of the coupling method are much better than those of the 2D/1D method while maintaining accuracy.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"223 \",\"pages\":\"Article 111663\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-06-24\",\"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/S0306454925004803\",\"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/S0306454925004803","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}
A neutron transport calculation approach via the coupling of 2D/1D and 3D SN nodal methods
The 2D/1D neutron transport method is a popular approach for high-fidelity neutron transport calculations. For some research or testing reactors, the reactor core is surrounded by heavy water, and outside the heavy water is light water. To obtain the spectrum in the heavy water and light water outside the core, the heavy water and light water domains must be included in the calculation. This significantly affects the calculation time and convergence when using the 2D/1D method. Therefore, a new neutron transport method based on the 2D/1D method and the 3D SN nodal method is proposed to address these issues. In this method, the reactor core is divided into two calculation domains. The reactor active core is calculated by the 2D/1D method with fine meshes, while the region outside the reactor core is calculated by the 3D SN nodal method. The two calculation domains are coupled by the boundary angular flux. The CMFD and parallel scheme are also implemented to accelerate the calculations. This method is applied to the C5G7 benchmark and JRR-3 reactor core. The numerical tests show that the efficiency and convergence of the coupling method are much better than those of the 2D/1D method while maintaining accuracy.
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.