Review of Thermalhydraulic Experimental Researches at INET

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概要

• 論文の詳細を見る

• Over the last forty years, the Institute of Nuclear Energy Technology (INET) of Tsinghua University has been one of the leading research institutes in the field of research and development on new types of reactors in China. As the results of research and development programs on new types of reactors, three reactors which have different kinds of structure and design features have been constructed at INET; in addition, several large-scale thermalhydraulic test loops have been built in the thermalhydraulics laboratory of the INET too. Relating to the research and development of liquid-metal fast neutron breeder reactor (LMFBR), molten salt reactor (MSR), nuclear heating reactor (NHR) and high temperature gas-cooled reactor (HTGR) many thermalhydraulic experimental investigations have been carried out. A lot of design and/or operation experiences and the experimental research results on the above mentioned reactors have been obtained at the INET. After a brief introduction of the NHR and HTGR constructed at the INET, the main large-scale thermalhydraulic test loops and parts of the research interests and results from the loops are summarized and presented in the paper.

• 社団法人 日本原子力学会の論文
• 2001-06-25

著者

• Jia H

  Tsinghua Univ. Beijing Chn

• Jia Haijun

  Institute Nuclear Energy Technology Tsinghua University

• JIANG Shengyao

  Institute of Nuclear and New Energy Technology, the Key Laboratory of Advanced Reactor Engineering a

• XU Yuanhui

  Institute of Nuclear and New Energy Technology, the Key Laboratory of Advanced Reactor Engineering a

• JU Huaiming

  Institute of Nuclear Energy Technology, Tsinghua University

• WU Shaorong

  Institute of Nuclear Energy Technology, Tsinghua University

• YAO Meisheng

  Institute of Nuclear Energy Technology, Tsinghua University

• Wu Shaorong

  Institute Of Nuclear Energy Technology Tsinghua University

• Ju Huaiming

  Institute Of Nuclear Energy Technology Tsinghua University

• Yao Meisheng

  Institute Of Nuclear Energy Technology Tsinghua University

• Xu Yuanhui

  Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An

• Xu Yuanhui

  Institute Of Nuclear Energy Technology Tsinghua University

• Jiang Shengyao

  Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An

• Jiang Shengyao

  Institute Of Nuclear And New Energy Technology Of Tsinghua University

関連論文

• Gas Space and Flow Stability in Integrated Reactors
• Optimization of Hot Gas Chamber in High Temperature Reactor
• Numerical Analysis of the Lifting Beam's Influence on Flow Fields in Planar Fuel Assemblies
• Experimental and Operational Verification of the HTR-10 Once-Through Steam Generator (SG) : Heat-transfer and Hydrodynamic Features of the Once-Through Steam Generator
• Experiment and Verification Test of the Once-through Steam Generator of the 10MW High-temperature Gas-cooled Reactor Flow Stability of the Once-through Steam Generator
• Thermalhydraulic Investigation Using a Test Facility Simulating 200 MW Integral Heating Reactor
• Review of Thermalhydraulic Experimental Researches at INET
• Experimental Investigation on Feasibility of Two-Region-Designed Pebble-Bed High-Temperature Gas-Cooled Reactor
• Hydraulic Performance of Small Bending Radius Helical Coil-Pipe
• Research Method and Two-Phase Flow Stability of the Steam Generator of HTR-10
• Numerical Analysis of the Lifting Beam's Influence on Flow Fields in Planar Fuel Assemblies

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