한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)
- 한국원자력학회 1996년도 추계학술발표회논문집(1)
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- Pages.211-216
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- 1996
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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