Temperature analysis of the HTR-10 after full load rejection

  • Xiang-Cheng Zhang
  • Ding She
  • Fu-Bing ChenEmail author
  • Lei Shi
  • Yu-Jie Dong
  • Zuo-Yi Zhang


The HTR-10 is a small modular high-temperature reactor located in Tsinghua University, in China. After the reactor ran continuously for 72 h at full power in the commissioning stage, a full load rejection test was conducted by manually disconnecting the generator from the grid. In this study, reactor transients were analyzed using the THERMIX model. Some of the important thermal–fluid phenomena that occurred after the test initiation are discussed here, including the natural convection of helium in the core and the temperature redistribution in the reactor. Temperatures reproduced for the measuring points arranged in the internals were in agreement with the test data. This demonstrated that the code and calculation model are suitable for posttest analysis applications. Regarding the safety features of the reactor, there was a large margin between the predicted maximum fuel temperature of 997 °C and the safety limit of 1620 °C.


HTR-10 Load rejection THERMIX Code validation 


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Copyright information

© China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, Chinese Nuclear Society and Springer Nature Singapore Pte Ltd. 2019

Authors and Affiliations

  • Xiang-Cheng Zhang
    • 1
  • Ding She
    • 1
  • Fu-Bing Chen
    • 1
    Email author
  • Lei Shi
    • 1
  • Yu-Jie Dong
    • 1
  • Zuo-Yi Zhang
    • 1
  1. 1.Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of EducationTsinghua UniversityBeijingChina

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