Influence of U-235 enrichment on the moderator temperature coefficient of reactivity in a graphite-moderated molten salt reactor
文献类型:期刊论文
作者 | Li, XX; Cui, DY; Ma, YW; Cai, XZ; Chen, JG |
刊名 | NUCLEAR SCIENCE AND TECHNIQUES
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出版日期 | 2019 |
卷号 | 30期号:11页码:- |
ISSN号 | 1001-8042 |
DOI | 10.1007/s41365-019-0694-z |
文献子类 | 期刊论文 |
英文摘要 | To optimize the temperature coefficient of reactivity (TCR) for a graphite-moderated and liquid-fueled molten salt reactor, the effects of fuel salt composition on the fuel salt temperature coefficient of reactivity (FSTC) were investigated in our earlier work. In this study, we aim to provide a more comprehensive analysis of the TCR by considering the effects of the graphite-moderator temperature coefficient of reactivity (MTC). The effects of 235U enrichment and heavy metal (HM) proportion in the salt mixture on the MTC are investigated from the perspective of the six-factor formula based on a full-core model. For the MTC (labeled ``aTM''), the temperature coefficient of the fast fission factors (aTMoeTHORN) is positive, while those of the resonance escape probability (aTMopTHORN), the thermal reproduction factor (aTMogTHORN), the thermal utilization factor (aTMof THORN), and the total non-leakage probability (aTM) are negative. The results reveal that the magnitudes of aTMoeTHORN and aTMopTHORN for the MTC are similar. Thus, variations in the MTC with 235U enrichment for different HM proportions are mainly dependent on aTMogTHORN, aTMoKTHORN, and aTMof THORN, but especially on the former two. To obtain a more negative MTC, a lower HM proportion and/or a lower 235U enrichment is recommended. Together with our previous studies on the FSTC, a relatively soft neutron spectrum could strengthen the TCR with a sufficiently negative MTC. |
语种 | 英语 |
源URL | [http://ir.sinap.ac.cn/handle/331007/32096] ![]() |
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 |
作者单位 | 1.Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China; 2.Univ Chinese Acad Sci, Beijing 100049, Peoples R China 3.Chinese Acad Sci, CAS Innovat Acad TMSR Energy Syst, Shanghai 201800, Peoples R China; |
推荐引用方式 GB/T 7714 | Li, XX,Cui, DY,Ma, YW,et al. Influence of U-235 enrichment on the moderator temperature coefficient of reactivity in a graphite-moderated molten salt reactor[J]. NUCLEAR SCIENCE AND TECHNIQUES,2019,30(11):-. |
APA | Li, XX,Cui, DY,Ma, YW,Cai, XZ,&Chen, JG.(2019).Influence of U-235 enrichment on the moderator temperature coefficient of reactivity in a graphite-moderated molten salt reactor.NUCLEAR SCIENCE AND TECHNIQUES,30(11),-. |
MLA | Li, XX,et al."Influence of U-235 enrichment on the moderator temperature coefficient of reactivity in a graphite-moderated molten salt reactor".NUCLEAR SCIENCE AND TECHNIQUES 30.11(2019):-. |
入库方式: OAI收割
来源:上海应用物理研究所
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