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题名: Neutron excess method for performance assessment of thorium-based fuel in a breed-and-burn reactor with various coolants
作者: Yang, K; Qin, W; Chen, JG; Cai, XZ
刊名: NUCLEAR SCIENCE AND TECHNIQUES
出版日期: 2016
卷号: 27, 期号:4, 页码:-
关键词: Neutron excess ; Thorium breed-and-burn ; Monte Carlo method
DOI: 10.1007/s41365-016-0096-4
通讯作者: Chen, JG ; Cai, XZ (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China. ; Chen, JG ; Cai, XZ (reprint author), Chinese Acad Sci, CAS Ctr Excellence TMSR Energy Syst, Shanghai 201800, Peoples R China.
文章类型: 期刊论文
英文摘要: Fertile fuel, such as thorium or depleted uranium, can be bred into fissile fuel and burnt in a breed-and-burn (B&B) reactor. Modeling a full core with fertile fuel can assess the performance of a B&B reactor with exact quantitative estimates, but costs too much computation time. For simplicity, performing the recently developed neutron balance method with a zero-dimensional (0-D) model can also provide a reasonable result. Based on the 0-D model, the feasibility of the B&B mode for thorium fuel in a fast reactor cooled by sodium was investigated by considering the (n, 2n) and (n, 3n) reaction rates of fuel and coolant in this work, and compared with that of depleted uranium fuel. Afterward, the performance of the same thorium-based fuel core, but cooled by helium, lead-bismuth, and FLiBe, respectively, is discussed. It is found that the (n, 2n) and (n, 3n) reactions should not be neglected for the neutron balance calculation for thorium-based fuel to sustain the B&B mode of operation.
收录类别: SCI
语种: 英语
WOS记录号: WOS:000385041100023
ISSN号: 1001-8042
Citation statistics:
内容类型: 期刊论文
URI标识: http://ir.sinap.ac.cn/handle/331007/26584
Appears in Collections:中科院上海应用物理研究所2011-2017年_期刊论文

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