CAS OpenIR  > 中科院上海应用物理研究所2011-2019年
Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor
Zeng, YSS; Wu, SW; Liu, W; Wang, GH; Qian, N; Wu, XL; Liu, WG; Huang, Y; Qian, Y
2018
Source PublicationNUCLEAR TECHNOLOGY
ISSN0029-5450
Volume203Issue:1Pages:48-57
Subtype期刊论文
AbstractThe 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.
DOI10.1080/00295450.2018.1433408
Indexed BySCI
Language英语
WOS IDWOS:000435422500004
Citation statistics
Cited Times:1[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.sinap.ac.cn/handle/331007/28968
Collection中科院上海应用物理研究所2011-2019年
Affiliation1.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
Recommended Citation
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.
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