TY - GEN
T1 - Tritium transport characteristics analysis in molten salt reactor under transient conditions
AU - Qin, Hao
AU - Zhang, Dalin
AU - Wang, Chenglong
AU - Tian, Wenxi
AU - Qiu, Suizheng
AU - Su, Guanghui
N1 - Publisher Copyright:
Copyright © 2018 ASME
PY - 2018
Y1 - 2018
N2 - 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.
AB - 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.
UR - https://www.scopus.com/pages/publications/85056181352
U2 - 10.1115/ICONE2681728
DO - 10.1115/ICONE2681728
M3 - 会议稿件
AN - SCOPUS:85056181352
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation
PB - American Society of Mechanical Engineers (ASME)
T2 - 2018 26th International Conference on Nuclear Engineering, ICONE 2018
Y2 - 22 July 2018 through 26 July 2018
ER -