{"title":"改进的一对多方法在 CFETR 中子建模中的应用和验证","authors":"Miao Yin, Qixiang Cao, Xiaoyu Wang, Xinghua Wu, Shen Qu","doi":"10.1007/s10894-024-00397-9","DOIUrl":null,"url":null,"abstract":"<div><p>China fusion engineering test reactor (CFETR) is a magnetic confinement device which will fill the gap between the fusion experimental reactor and the demonstration reactor. To efficiently conduct neutronics modeling for the multiple identical and similar structures present in CFETR’s modular design, an improved one-to-many method is developed and implemented in this study. This method involves using a basic model in conjunction with a 3D transformed coordinate system. However, the absence of a clear solution method for the transformed coordinate system in MCNP presents a challenge. To address this issue, a solution method based on the axis attributes of the surfaces in MCNP and the composite nature of the 3D transformed coordinate system is developed. The improved one-to-many method has been applied to the neutron modeling of CFETR, and its reliability has been verified. In the neutron calculation model corresponding to the one-to-many and one-to-one methods, relative differences of the total TBR and nuclear heating are 0.25%, 0.07% respectively. The contribution of blanket modules to tritium breeding ratio (TBR) and nuclear heating has a relative difference within the range of − 0.25–0.55%. The relative differences of neutron flux and nuclear heating distribution for individual blanket modules #3–1 and #6–1 are within the range of − 0.60–0.40%. The results indicate that the improved one-to-many method can be employed for neutronics modeling in the preliminary design of CFETR.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 1","pages":""},"PeriodicalIF":1.9000,"publicationDate":"2024-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Application and Validation of an Improved One-to-Many Method to CFETR Neutronics Modeling\",\"authors\":\"Miao Yin, Qixiang Cao, Xiaoyu Wang, Xinghua Wu, Shen Qu\",\"doi\":\"10.1007/s10894-024-00397-9\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>China fusion engineering test reactor (CFETR) is a magnetic confinement device which will fill the gap between the fusion experimental reactor and the demonstration reactor. To efficiently conduct neutronics modeling for the multiple identical and similar structures present in CFETR’s modular design, an improved one-to-many method is developed and implemented in this study. This method involves using a basic model in conjunction with a 3D transformed coordinate system. However, the absence of a clear solution method for the transformed coordinate system in MCNP presents a challenge. To address this issue, a solution method based on the axis attributes of the surfaces in MCNP and the composite nature of the 3D transformed coordinate system is developed. The improved one-to-many method has been applied to the neutron modeling of CFETR, and its reliability has been verified. In the neutron calculation model corresponding to the one-to-many and one-to-one methods, relative differences of the total TBR and nuclear heating are 0.25%, 0.07% respectively. The contribution of blanket modules to tritium breeding ratio (TBR) and nuclear heating has a relative difference within the range of − 0.25–0.55%. The relative differences of neutron flux and nuclear heating distribution for individual blanket modules #3–1 and #6–1 are within the range of − 0.60–0.40%. The results indicate that the improved one-to-many method can be employed for neutronics modeling in the preliminary design of CFETR.</p></div>\",\"PeriodicalId\":634,\"journal\":{\"name\":\"Journal of Fusion Energy\",\"volume\":\"43 1\",\"pages\":\"\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-03-19\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Fusion Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://link.springer.com/article/10.1007/s10894-024-00397-9\",\"RegionNum\":4,\"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":"Journal of Fusion Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10894-024-00397-9","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Application and Validation of an Improved One-to-Many Method to CFETR Neutronics Modeling
China fusion engineering test reactor (CFETR) is a magnetic confinement device which will fill the gap between the fusion experimental reactor and the demonstration reactor. To efficiently conduct neutronics modeling for the multiple identical and similar structures present in CFETR’s modular design, an improved one-to-many method is developed and implemented in this study. This method involves using a basic model in conjunction with a 3D transformed coordinate system. However, the absence of a clear solution method for the transformed coordinate system in MCNP presents a challenge. To address this issue, a solution method based on the axis attributes of the surfaces in MCNP and the composite nature of the 3D transformed coordinate system is developed. The improved one-to-many method has been applied to the neutron modeling of CFETR, and its reliability has been verified. In the neutron calculation model corresponding to the one-to-many and one-to-one methods, relative differences of the total TBR and nuclear heating are 0.25%, 0.07% respectively. The contribution of blanket modules to tritium breeding ratio (TBR) and nuclear heating has a relative difference within the range of − 0.25–0.55%. The relative differences of neutron flux and nuclear heating distribution for individual blanket modules #3–1 and #6–1 are within the range of − 0.60–0.40%. The results indicate that the improved one-to-many method can be employed for neutronics modeling in the preliminary design of CFETR.
期刊介绍:
The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews.
This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.