Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor
文献类型:期刊论文
作者 | Zeng, YSS; Wu, SW; Liu, W; Wang, GH; Qian, N; Wu, XL; Liu, WG; Huang, Y; Qian, Y |
刊名 | NUCLEAR TECHNOLOGY |
出版日期 | 2018 |
卷号 | 203期号:1页码:48-57 |
ISSN号 | 0029-5450 |
DOI | 10.1080/00295450.2018.1433408 |
文献子类 | 期刊论文 |
英文摘要 | The Thorium-Based Molten Salt Reactor (TMSR) has been highlighted for its safety, economy, and nuclear nonproliferation. A program for developing the TMSR system has been launched in Shanghai Institute of Applied Physics, Chinese Academy of Sciences. In the TMSR system, mixtures of LiF and BeF2, termed FLiBe, are proposed and used as the primary coolant salt, in which tritium is produced mainly by the neutron reactions of lithium. In the TMSR system, at high temperatures, tritium can permeate through metal walls to the surroundings, leading to a potential radiological hazard. Thus, tritium control becomes a major problem hindering the development of the TMSR system. Evaluation of the tritium distribution is necessary for tritium control in the TMSR system. In this study, the Tritium Transport Analysis Code (TTAC) has been developed for simulating the tritium behaviors in the TMSR system (hence, the code TMSR-TTAC), such as tritium chemical forms in coolant salts, tritium transport behaviors, and tritium distribution in the system. The model code is developed by the MATLAB/SIMULINK package, and it is based on the mass balance equations of the tritium-containing species and hydrogen. TMSR-TTAC is benchmarked with the molten salt reactor model, which is based on Molten Salt Reactor Experiment designs. The results show that TMSR-TTAC has the ability to calculate the tritium distribution in the TMSR system. |
语种 | 英语 |
WOS记录号 | WOS:000435422500004 |
源URL | [http://ir.sinap.ac.cn/handle/331007/28968] |
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.Zeng, YSS 2.Wu, SW 3.Liu, W 4.Wang, GH 5.Qian, N 6.Wu, XL 7.Liu, WG 8.Huang, Y 9.Qian, Y |
推荐引用方式 GB/T 7714 | Zeng, YSS,Wu, SW,Liu, W,et al. Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor[J]. NUCLEAR TECHNOLOGY,2018,203(1):48-57. |
APA | Zeng, YSS.,Wu, SW.,Liu, W.,Wang, GH.,Qian, N.,...&Qian, Y.(2018).Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor.NUCLEAR TECHNOLOGY,203(1),48-57. |
MLA | Zeng, YSS,et al."Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor".NUCLEAR TECHNOLOGY 203.1(2018):48-57. |
入库方式: OAI收割
来源:上海应用物理研究所
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