Thermal-Hydraulic Test Facilities and Some Test Results of Integrated Heating Reactors

  • Jia, Haijun (Institute of Nuclear Energy Technology Tsinghua University) ;
  • Wu, Shaorong (Institute of Nuclear Energy Technology Tsinghua University) ;
  • Jiang, Shengyao (Institute of Nuclear Energy Technology Tsinghua University)
  • 발행 : 1996.11.01

초록

Since the middle of the eighties of this century a research program both for heating reactor and investigation of heating reactor thermal-hydraulics has been carried out in Institute of Nuclear Energy Technology(INET) of Tsinghua university in China. This kind of heating reactor is a light water cooled and integrated natural circulation reactor with low system pressure and low quality at the exit of core. Because of relatively long riser and low system pressure. a little change of the quality at the exit of the core will result in a relatively large variation of void fraction in the riser. Two full scale test loops. HRTL-5 and HRTL-200 simulating the HR-5 and HR-200 heating reactors in geometry and operation parameters respectively, and some test results from the HRTL-200 test facility are shown in this paper. The range of studied system pressure is from 1.0MPa to 4.0MPa, the largest heat flux is about 50 W/cm2, and the quality at the exit of test section is less than 5%.

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