Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor
文献类型：期刊论文
| 作者 | Zhang, ZH; Xia, XB; Cai, J; Wang, JH; Li, CY; Ge, LQ; Zhang, QX |
| 刊名 | NUCLEAR SCIENCE AND TECHNIQUES
 |
| 出版日期 | 2015 |
| 卷号 | 26期号:4页码:— |
| 关键词 | MODEL UDF |
| ISSN号 | 1001-8042 |
| 通讯作者 | Xia, XB (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China. |
| 英文摘要 | The Chinese Academy of Science has launched a thorium-based molten-salt reactor (TMSR) research project with a mission to research and develop a fission energy system of the fourth generation. The TMSR project intends to construct a liquid fuel molten-salt reactor (TMSR-LF), which uses fluoride salt as both the fuel and coolant, and a solid fuel molten-salt reactor (TMSR-SF), which uses fluoride salt as coolant and TRISO fuel. An optimized 2 MWth TMSR-LF has been designed to solve major technological challenges in the Th-U fuel cycle. Preliminary conceptual shielding design has also been performed to develop bulk shielding. In this study, the radiation dose and temperature distribution of the shielding bulk due to the core were simulated and analyzed by performing Monte Carlo simulations and computational fluid dynamics (CFD) analysis. The MCNP calculated dose rate and neutron and gamma spectra indicate that the total dose rate due to the core at the external surface of the concrete wall was 1.91 mu Sv/h in the radial direction, 1.16 mu Sv/h above and 1.33 mu Sv/h below the bulk shielding. All the radiation dose rates due to the core were below the design criteria. Thermal analysis results show that the temperature at the outermost surface of the bulk shielding was 333.86 K, which was below the required limit value. The results indicate that the designed bulk shielding satisfies the radiation shielding requirements for the 2 MWth TMSR-LF. |
| 语种 | 英语 |
| WOS记录号 | WOS:000361645000019 |
| 公开日期 | 2016-03-08 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/25042]  |
| 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 | Zhang, ZH,Xia, XB,Cai, J,et al. Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor[J]. NUCLEAR SCIENCE AND TECHNIQUES,2015,26(4):—. |
| APA | Zhang, ZH.,Xia, XB.,Cai, J.,Wang, JH.,Li, CY.,...&Zhang, QX.(2015).Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor.NUCLEAR SCIENCE AND TECHNIQUES,26(4),—. |
| MLA | Zhang, ZH,et al."Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor".NUCLEAR SCIENCE AND TECHNIQUES 26.4(2015):—. |
入库方式： OAI收割
来源：上海应用物理研究所
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