Modeling and Code Development of HP-PRHRS for Molten Salt Reactor

被引:0
|
作者
Liu M. [1 ]
Zhang Y. [1 ]
Wang C. [2 ]
Zhang D. [2 ]
Qiu S. [2 ]
Li Y. [1 ]
Yin S. [1 ]
Liu H. [1 ]
Yang H. [1 ]
机构
[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu
[2] School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an
关键词
High temperature heat pipe; Molten salt reactor; Passive residual heat removal system; System modeling;
D O I
10.7538/yzk.2020.youxian.0099
中图分类号
学科分类号
摘要
The conceptual design of heat pipe cooled passive residual heat removal system (HP-PRHRS) was proposed to improve passive safety performance of molten salt reactor (MSR). Based on the structure of HP-PRHRS and the operation performance of MSR, a set of reasonable mathematical physical models were built, mainly including reactor core physical thermal model, high temperature heat pipe model and HP-PRHRS model. Analysis code PRAC for HP-PRHRS was developed for MSR adopting those models. The verification of the code was conducted using MSRE benchmark and the transient experimental data. The results show that the calculated value of PRAC code is in good agreement with the benchmark and experimental results, which proves the accuracy of the model and code. HP-PRHRS model and PRAC code can support and provide foundation for the future research on MSR. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:2353 / 2361
页数:8
相关论文
共 15 条
  • [1] CAI Xiangzhou, DAI Zhimin, XU Hongjie, Thorium molten salt reactor nuclear energy system, Physics, 45, 9, pp. 578-590, (2016)
  • [2] LEBLANC D., Molten salt reactors: A new beginning for an old idea, Nuclear Engineering and Design, 240, 6, pp. 1644-1656, (2010)
  • [3] JIANG Mianheng, XU Hongjie, DAI Zhimin, Advanced fission energy program-TMSR nuclear energy system, Bulletin of Chinese Academy of Sciences, 27, 3, pp. 366-374, (2012)
  • [4] WANG C, ZHANG D, QIU S, Et al., Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor, Nuclear Engineering and Design, 265, pp. 691-700, (2013)
  • [5] WANG C, GUO Z, ZHANG D, Et al., Transient behavior of the sodium-potassium alloy heat pipe in passive residual heat removal system of molten salt reactor, Progress in Nuclear Energy, 68, pp. 142-152, (2013)
  • [6] LIU Minghao, ZHANG Dalin, WANG Cheng-long, Et al., Experimental study on the heat transfer characteristics of fluoride salt in the new conceptual passive heat removal system of molten salt reactor[J], International Journal of Energy Research, 42, 4, pp. 1635-1648, (2018)
  • [7] LIU Minghao, ZHANG Dalin, WANG Cheng-long, Et al., Experimental study on heat transfer performance between fluoride salt and heat pipes in the new conceptual passive residual heat removal system of molten salt reactor, Nuclear Engineering and Design, 339, pp. 215-224, (2018)
  • [8] WANG C L, LIU M H, ZHANG D L, Et al., Experimantal study on transient performance of heat pipe-cooled passive residual heat removal system fo a molten salt reactor, Progress in Nuclear Energy, 118, pp. 103-113, (2020)
  • [9] RICHTER R, GOTTSCHLICH J., Thermodynamic aspects of heat pipe operation, Journal of Thermophysics and Heat transfer, 8, 2, pp. 334-340, (1994)
  • [10] (2000)