High temperature heat pipes are effective devices for heat transfer, which are characterized by remarkable advantages in conductivity, isothermality and passivity. It is of significance to apply heat pipes on new concept passive residual heat removal system (PRHRS) of molten salt reactor (MSR). In this paper, the transient performance of high temperature sodium heat pipe is simulated with numerical method in the case of MSR accident. The model of the heat pipe is composed of three conjugate heat transfers, i.e. the vapor space, wick structure and wall. Based on finite element method, the governing equations and boundary conditions are solved by using FORTRAN code to acquire the profiles of the temperature, velocity and pressure for the heat pipe transient operation. The results indicated that high temperature sodium heat pipe had a good operating characteristic and removed the residual heat of fuel salt rapidly under the accident of MSR.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor 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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Wenxi Tian,
Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
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Yingwei Wu,
Yingwei Wu
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
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
Yingwei Wu
Xi’an Jiaotong University, Xi’an, China
Guanghui Su
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE21-15029, V004T09A003; 10 pages
Published Online:
February 7, 2014
Citation
Wang, C, Qiu, S, Tian, W, Wu, Y, & Su, G. "Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A003. ASME. https://doi.org/10.1115/ICONE21-15029
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