Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor
文献类型:期刊论文
作者 | Zou, CY; Cai, XZ; Jiang, DZ; Yu, CG; Li, XX; Ma, YW; Han, JL; Chen, JG |
刊名 | NUCLEAR ENGINEERING AND DESIGN
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出版日期 | 2015 |
卷号 | 281页码:114—120 |
英文摘要 | Molten salt reactor (MSR) has fascinating features: inherent safety, no fuel fabrication, online fuel reprocessing, etc. However, the graphite moderated MSR may present positive feedback coefficient which has severe implications for the transient behavior during operation. In this paper, the feedback coefficient and the breeding ratio are optimized based on the fuel-to-graphite ratio variation for a thorium based MSR (TMSR). A certain thermal core with negative feedback coefficient and relative high initial breeding ratio is chosen for the reprocessing scheme analysis. The breeding performances for the TMSR under different online fuel reprocessing efficiencies and frequencies are evaluated and compared with other MSR concepts. The results indicate that the thermal TMSR can get a breeding ratio greater than 1.0 with appropriate reprocessing scheme. The low fissile inventory in thermal TMSR leads to a short doubling time and low transuranic (TRU) inventory. The lifetime of graphite used for the TMSR is also discussed. (C) 2014 Elsevier B.V. All rights reserved. |
收录类别 | SCI |
语种 | 英语 |
公开日期 | 2015-12-24 |
源URL | [http://ir.sinap.ac.cn/handle/331007/24520] ![]() |
专题 | 上海应用物理研究所_中科院上海应用物理研究所2011-2017年 |
推荐引用方式 GB/T 7714 | Zou, CY,Cai, XZ,Jiang, DZ,et al. Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor[J]. NUCLEAR ENGINEERING AND DESIGN,2015,281:114—120. |
APA | Zou, CY.,Cai, XZ.,Jiang, DZ.,Yu, CG.,Li, XX.,...&Chen, JG.(2015).Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor.NUCLEAR ENGINEERING AND DESIGN,281,114—120. |
MLA | Zou, CY,et al."Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor".NUCLEAR ENGINEERING AND DESIGN 281(2015):114—120. |
入库方式: OAI收割
来源:上海应用物理研究所
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