{"title":"Neutron Flux in EU DEMO Divertor Cassette Body Using HCPB and WCLL Breeding Blanket Models","authors":"Simona Breidokaite, Gediminas Stankunas","doi":"10.1007/s10894-022-00327-7","DOIUrl":null,"url":null,"abstract":"<div><p>The paper presents results from neutron flux calculations in the divertor cassette body in cases of Helium Cooled Pebble Bed, and Water-Cooled Lithium Lead concepts are used as a breeding blanket. The same divertor model configuration and specified DEMO neutron source were used for both cases studied. MCNP6 code was used for neutron transport calculations and employing the FENDL-3.1 nuclear data library. |In addition, this paper presents the neutron-induced dose rate calculations performed with support by ADVANTG (AutomateD VAriaNce reducTion Generator) tool and MCNP code, which were used for the variance reduction and particle transport accordingly. The application of such a coupled computational method led to the dose rate and neutron flux maps production, which was obtained for the divertor of the DEMO reactor.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2022-06-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-022-00327-7.pdf","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Fusion Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10894-022-00327-7","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}
引用次数: 0
Abstract
The paper presents results from neutron flux calculations in the divertor cassette body in cases of Helium Cooled Pebble Bed, and Water-Cooled Lithium Lead concepts are used as a breeding blanket. The same divertor model configuration and specified DEMO neutron source were used for both cases studied. MCNP6 code was used for neutron transport calculations and employing the FENDL-3.1 nuclear data library. |In addition, this paper presents the neutron-induced dose rate calculations performed with support by ADVANTG (AutomateD VAriaNce reducTion Generator) tool and MCNP code, which were used for the variance reduction and particle transport accordingly. The application of such a coupled computational method led to the dose rate and neutron flux maps production, which was obtained for the divertor of the DEMO reactor.
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.
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