Neutron excess method for performance assessment of thorium-based fuel in a breed-and-burn reactor with various coolants
文献类型：期刊论文
| 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 |
| ISSN号 | 1001-8042 |
| 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. |
| 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 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/26584]  |
| 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 | Yang, K,Qin, W,Chen, JG,et al. Neutron excess method for performance assessment of thorium-based fuel in a breed-and-burn reactor with various coolants[J]. NUCLEAR SCIENCE AND TECHNIQUES,2016,27(4):-. |
| APA | Yang, K,Qin, W,Chen, JG,&Cai, XZ.(2016).Neutron excess method for performance assessment of thorium-based fuel in a breed-and-burn reactor with various coolants.NUCLEAR SCIENCE AND TECHNIQUES,27(4),-. |
| MLA | Yang, K,et al."Neutron excess method for performance assessment of thorium-based fuel in a breed-and-burn reactor with various coolants".NUCLEAR SCIENCE AND TECHNIQUES 27.4(2016):-. |
入库方式： OAI收割
来源：上海应用物理研究所
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