The Fluoride-salt-cooled High temperature Reactor (FHR) is new reactor concept-about a decade old which is mainly on going in China and U.S. The preliminary thermal-hydraulic studies of the Fluoride salt cooled High temperature Test Reactor (FHTR) is necessary for the development of the FHR technology. In this paper, the thermal-hydraulics of FHTR (also called TMSR-SF) designed by Shanghai Instituted of Applied Physics (SINAP) is studied in different power modes. The temperature distributions of the coolant and the fuel pebble are obtained using a steady-state thermal-hydraulic analysis code for FHR. The comprehensive local flow and heat transfer are investigated by computational fluid dynamics (CFD) for the locations where may have the maximum pebble temperature based on the results from single channel analysis. The profiles of temperature, velocity, pressure and Nu of the coolant on the surface of the pebble as well as the temperature distribution of a fuel pebble are obtained and analyzed. Numerical results showed that the results of 3-D simulation are in reasonable agreement with that of single channel model and also illustrated safety operation of the preliminary designed TMSR-SF in different power mode.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4595-0
PROCEEDINGS PAPER
Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods
Chenglong Wang,
Chenglong Wang
Xi’an Jiaotong University, Xi’an, China
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Yao Xiao,
Yao Xiao
Xi’an Jiaotong University, Xi’an, China
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Jianjun Zhou,
Jianjun Zhou
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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Suizheng Qiu,
Suizheng Qiu
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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Chenglong Wang
Xi’an Jiaotong University, Xi’an, China
Yao Xiao
Xi’an Jiaotong University, Xi’an, China
Jianjun Zhou
Xi’an Jiaotong University, Xi’an, China
Dalin Zhang
Xi’an Jiaotong University, Xi’an, China
Suizheng Qiu
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:
ICONE22-30219, V005T17A029; 10 pages
Published Online:
November 17, 2014
Citation
Wang, C, Xiao, Y, Zhou, J, Zhang, D, Qiu, S, Tian, W, & Su, G. "Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. Prague, Czech Republic. July 7–11, 2014. V005T17A029. ASME. https://doi.org/10.1115/ICONE22-30219
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