会议专题

HEAT TRANSFER EXPERIMENTS FOR AN UPWARD FLOW OF SUPERCRITICAL PRESSURE CO2 IN A NARROW ANNULUS

Heat transfer experiments at an annulus passage were carried out in the SPHINX (Supercritical Pressure Heat Transfer Investigation for NeXt Generation), which was constructed at KAERI (Korea Atomic Energy Research Institute), to investigate the heat transfer behaviors of supercritical CO2. The collected test data are to be used for the reactor core design of the SCWR (SuperCritical Water-cooled Reactor). As a working fluid, CO2 was selected to make use of the low critical pressure and temperature of CO2 compared with water. The mass flux was in the range of 400~ 1200kg/m2 s and the heat flux was chosen up to 150kW/m2. The selected pressures were 7.75 and 8.12MPa. At a lower mass flux, a heat transfer deterioration occurs if the heat flux increases. Comparison with the tube test results showed that the degree of heat transfer deterioration becomes smaller than that in the tube.

supercritical water-cooled reactor heat transfer deterioration carbon dioxide tube annulus

Kim Yoon Yeong Hwan Yeol Hyungrae Kang Deog Ji Song Jin Ho Bae

Korea Atomic Energy Research Institute 150 Dukjin-dong, Yuseong-gu, Daejeon, S. Korea, 305-353 Korea Atomic Energy Research Institute 150 Dukjin-dong, Yuseong-gu, Daejeon, S.Korea, 305-353

国际会议

第三届超临界水冷堆设计与技术国际研讨会

上海

英文

447-456

2007-03-12(万方平台首次上网日期,不代表论文的发表时间)