L. Qiu, G. S. Luan, Q. Xu, Z. Guo, X. Gao, P. Duan, X.Q. Zhang, Y.Y. Li, W. Xu, Y. Wu, W.Y. Wu, C. Xia, Q. Huang, Y. Chen, N. Xiang, W.G. Zhang Yina, Y. Wu, Y. Chen, C. Qian
{"title":"Hefei tokamak Experimental Hybrid Reactor conceptual design","authors":"L. Qiu, G. S. Luan, Q. Xu, Z. Guo, X. Gao, P. Duan, X.Q. Zhang, Y.Y. Li, W. Xu, Y. Wu, W.Y. Wu, C. Xia, Q. Huang, Y. Chen, N. Xiang, W.G. Zhang Yina, Y. Wu, Y. Chen, C. Qian","doi":"10.1109/FUSION.1991.218764","DOIUrl":null,"url":null,"abstract":"The authors present a new concept of a hybrid reactor: using a Joint-European-Torus-like device which works in the sub-breakeven condition as a source of high-energy neutrons makes it possible to induce a blanket fission of depleted-uranium, solid breeding material, and helium cooling so that one can produce 100 kg of nuclear fuel (/sup 239/Pu) per year. High temperature will be maintained by external ICRF and ECRF heating. A steady-state plasma current will be driven by LHCD. The plasma density will be maintained by pellet injection ICRF can produce a high-energy tail in the ion distribution function and lead to significant enhancement of D-T reaction rate by 2-5 times so that one can obtain a neutron source strength of 1*10/sup 19/ n/s, enough for the requirement of the hybrid reactor.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"7 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/FUSION.1991.218764","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1
Abstract
The authors present a new concept of a hybrid reactor: using a Joint-European-Torus-like device which works in the sub-breakeven condition as a source of high-energy neutrons makes it possible to induce a blanket fission of depleted-uranium, solid breeding material, and helium cooling so that one can produce 100 kg of nuclear fuel (/sup 239/Pu) per year. High temperature will be maintained by external ICRF and ECRF heating. A steady-state plasma current will be driven by LHCD. The plasma density will be maintained by pellet injection ICRF can produce a high-energy tail in the ion distribution function and lead to significant enhancement of D-T reaction rate by 2-5 times so that one can obtain a neutron source strength of 1*10/sup 19/ n/s, enough for the requirement of the hybrid reactor.<>
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