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Simulation on gap bypass flow of the prismatic high temperature gas cooled reactor core
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Simulation on gap bypass flow of the prismatic high temperature gas cooled reactor core

    • “In the field of high-temperature gas cooled reactors, experts used the ANSYS CFX program to conduct three-dimensional numerical simulations of the gap side flow phenomenon in the MHTGR-350 reactor core, and analyzed the influence of gap size on the thermal fluid performance of the core, providing reference for core design.”
    • NUCLEAR TECHNIQUES   Vol. 44, Issue 12, Article number: 120601(2021)

    • DOI：10.11889/j.0253-3219.2021.hjs.44.120601    

      CLC： TL33

    • Received：26 April 2021，

      Revised：09 November 2021，

      Published：15 December 2021

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  • DONG Jianhua,WANG Jun,GUO Juanjuan,et al.Simulation on gap bypass flow of the prismatic high temperature gas cooled reactor core[J].NUCLEAR TECHNIQUES,2021,44(12):76-84. DOI： 10.11889/j.0253-3219.2021.hjs.44.120601.

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Related Author

DENG Chang
ZHANG Lin
LIU Xiaojing
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XU Wei
HE Hui
LIU Xiaojing
YANG Xuan

Related Institution

School of Mechanical Engineering, Shanghai Jiao Tong University
Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center
Nuclear Science and Engineering School, Shanghai Jiao Tong University
School of Energy and Power Engineering, Xi'an Jiao tong University
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China
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