Transition to thorium fuel cycle for TMSR
文献类型：期刊论文
| 作者 | Zou, CY; Cai, CZ; Yu, CG; Wu, JH; Chen, JG |
| 刊名 | NUCLEAR ENGINEERING AND DESIGN
 |
| 出版日期 | 2018 |
| 卷号 | 330页码:420-428 |
| 关键词 | Molten-salt Reactor Optimization System |
| ISSN号 | 0029-5493 |
| DOI | 10.1016/j.nucengdes.2018.01.033 |
| 文献子类 | 期刊论文 |
| 英文摘要 | Molten Salt Reactor (MSR) has been recognized as one of the reference reactors of the Generation IV International Forum (GIF) with the unique potential (inherent safety, no fuel fabrication, online fuel reprocessing, etc). A thermal MSR based on Th-232/U-233 fuel cycle can be designed to be a breeder with low fissile inventory and leads to a short doubling time and low transuranic (TRU) inventory. However, the fissile fuel supply is one of the unresolved problems since there is no available U-233. It is therefore needed to use existing fissile materials such as U-235 or Plutonium to produce U-233. In this paper, two ways for the thorium fuel cycle transition are proposed. One is that the TMSR is started with existing fissile material as starting fuel and thorium as fertile fuel. The bred U-233 from thorium is reinjected into the core for critical operation to achieve the transition to thorium fuel cycle gradually in the core (in-core transition). The other also adopts the same starting fuel as the in-core transition but stores the bred U-233 out of the core for starting a new TMSR which is then operated with Th-232/U-233 fuel cycle (ex-core transition). The transition performances for the two ways are analyzed based on a thermal TMSR configuration with negative coefficient and BR greater than 1.0. The results show that the transition capacity with Pu or TRU fuel is attractive. For the in-core transition mode, the thorium fuel cycle is quickly evoked and the characteristics of the TMSR turn out to be equivalent to the U-233 started TMSR after about 15-year operation. For the ex-core transition mode, the U-233 production is appreciable which needs less than 5 years to restart a new TMSR. Besides, the temperature feedback coefficients for the two ways are all negative during the entire operation. Finally, the preliminary characteristics of the thorium fuel cycle deployment are illustrated, which reveals that a thorium nuclear energy park containing various TMSRs as a TMSR fleet can provide sustainable nuclear energy with low production of long-life nuclear wastes. |
| 语种 | 英语 |
| WOS记录号 | WOS:000428300200039 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/29194]  |
| 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.Zou, CY 2.Cai, CZ 3.Yu, CG 4.Wu, JH 5.Chen, JG |
| 推荐引用方式 GB/T 7714 | Zou, CY,Cai, CZ,Yu, CG,et al. Transition to thorium fuel cycle for TMSR[J]. NUCLEAR ENGINEERING AND DESIGN,2018,330:420-428. |
| APA | Zou, CY,Cai, CZ,Yu, CG,Wu, JH,&Chen, JG.(2018).Transition to thorium fuel cycle for TMSR.NUCLEAR ENGINEERING AND DESIGN,330,420-428. |
| MLA | Zou, CY,et al."Transition to thorium fuel cycle for TMSR".NUCLEAR ENGINEERING AND DESIGN 330(2018):420-428. |
入库方式： OAI收割
来源：上海应用物理研究所
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