Tritium control is one of the most critical issues for the development of Molten Salt Reactor (MSR). The point kinetic model has been added into the TAPAS (Tritium trAnsPort chAracteristicS code) to research the dynamic responses of tritium transport characteristics during transients. Two typical transient accident conditions for Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) are simulated, including unprotected reactivity insertion (URIA) and unprotected overcooling (UOC). The distributions of the key variables in the primary loop and variations with time are obtained including TF, T2 and Cr2+. Numerical results show that during transients, tritium has quite different transport characteristics compared with steady state, ranging from tritium production and speciation, absorption by graphite, Cr corrosion and deposition to tritium permeation. The results are discussed in comparison with earlier findings in detail. This study may provide a valuable reference for the tritium control in MSR.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5146-3
PROCEEDINGS PAPER
Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions Available to Purchase
Chenglong Wang,
Chenglong Wang
Xi'an Jiaotong University, Xi'an, China
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Suizheng Qiu,
Suizheng Qiu
Xi'an Jiaotong University, Xi'an, China
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Dalin Zhang,
Dalin Zhang
Xi'an Jiaotong University, Xi'an, China
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Wenxi Tian,
Wenxi Tian
Xi'an Jiaotong University, Xi'an, China
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Guanghui Su
Guanghui Su
Xi'an Jiaotong University, Xi'an, China
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Hao Qin
Xi'an Jiaotong University, Xi'an, China
Chenglong Wang
Xi'an Jiaotong University, Xi'an, China
Suizheng Qiu
Xi'an Jiaotong University, Xi'an, China
Dalin Zhang
Xi'an Jiaotong University, Xi'an, China
Wenxi Tian
Xi'an Jiaotong University, Xi'an, China
Guanghui Su
Xi'an Jiaotong University, Xi'an, China
Paper No:
ICONE26-81728, V004T06A023; 6 pages
Published Online:
October 24, 2018
Citation
Qin, H, Wang, C, Qiu, S, Zhang, D, Tian, W, & Su, G. "Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation. London, England. July 22–26, 2018. V004T06A023. ASME. https://doi.org/10.1115/ICONE26-81728
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