External reactor vessel cooling (ERVC) of the In-vessel retention (IVR) system is widely accepted as a feasible way to remove decay heat from the lower head of the reactor pressure vessel (RPV) under severe accident (SA) conditions. However, some issues relating to ERVC still need to be evaluated before its application, such as boiling and flow phenomena and CHF prediction, etc. To study these key issues, an experimental study program named REPEC (Reactor Pressure Vessel External Cooling) is performed at Shanghai Jiao Tong University. Steady state experiments focusing on flow boiling phenomena investigation are carried out with comprehensive measurements, including temperature distribution, pressure drop and mass flow rate. As a part of studies on boiling mechanism and flow phenomena between RPV and the insulation, the experiment is analyzed and simulated with RELAP code. The code simulation covers most of the experimental cases, and a comparison between simulation results and experimental data are presented and discussed.
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Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
Cao, Ke-Mei
Xu, Yi-Quan
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Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
Xu, Yi-Quan
Shi, Guo-Bao
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Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
Shi, Guo-Bao
Cai, Jian-Ping
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Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South Korea
Kim, Jae Cheol
Ha, Kwang Soon
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South Korea
Ha, Kwang Soon
Park, Rae Joon
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South Korea
Park, Rae Joon
Kim, Sang Baik
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South Korea
Kim, Sang Baik
Hong, Seong Wan
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305600, South Korea