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Volume 44 Issue S2
Dec.  2023
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Du Zhengyu, Ma Yugao, Zhong Ruicheng, Ding Shuhua, He Xiaoqiang, Deng Jian, Liu Yu. Analysis of Start-up Characteristics of Heat Pipe Reactor[J]. Nuclear Power Engineering, 2023, 44(S2): 67-73. doi: 10.13832/j.jnpe.2023.S2.0067
Citation: Du Zhengyu, Ma Yugao, Zhong Ruicheng, Ding Shuhua, He Xiaoqiang, Deng Jian, Liu Yu. Analysis of Start-up Characteristics of Heat Pipe Reactor[J]. Nuclear Power Engineering, 2023, 44(S2): 67-73. doi: 10.13832/j.jnpe.2023.S2.0067

Analysis of Start-up Characteristics of Heat Pipe Reactor

doi: 10.13832/j.jnpe.2023.S2.0067
  • Received Date: 2023-07-11
  • Rev Recd Date: 2023-08-28
  • Publish Date: 2023-12-30
  • The heat pipe reactor differs significantly from the pressurized water reactor in terms of neutron energy spectrum, fuel and core structure, temperature feedback coefficient, reactivity control method, and coolant, which may lead to a large power peak in the core and temperature difference at both ends of the heat pipe during startup. In response to these issues, this paper focuses on the land-based heat pipe reactor and proposes a “leapfrog” startup control strategy. The control set values of the strategy are determined through theoretical analysis. In terms of system design improvement, a scheme is proposed to add an air preheater for preheating the condensation section of the heat pipe before the heat pipe is completely started. The application effect of the aforementioned scheme is analyzed and verified using numerical calculations. The results show that the startup control strategy and system design improvement proposed in this paper reduce the fluctuation amplitude of core power during startup, decrease the temperature difference between the evaporation and condensation sections of the of heat pipe during startup, and correspondingly reduce the thermal stress of the heat pipe, thereby improving the reliability of heat pipe operation. The research findings of this paper provide input for drum control design and serve as a reference for setting monitoring parameters related to reactor protection and control systems. The relevant research findings of this paper can also provide reference for the design of gas-cooled systems in heat pipe reactors.

     

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