会议专题

Heat transfer characteristics of one side heated vertical rectangular channel

The once-through steam generator (OTSG) is an essential component of the nuclear power system. A compressible model with fixed boundaries is composed to study thermohydraulics characteristic of an annular tube once-through steam generator. It has double heat sides for heat transfer, the secondary side fluid flows through the annuli and varies from subcooled water to superheated steam. Because of the compressible characteristic of the secondary side fluid, special compressible fluid model was applied. The fluid network method was applied to solve the coupling between pressure and velocity. The steady conduction model was used to compute the heat transfer from the first primary side to the secondary side of the annular tube. GEAR algorithm was applied to solve the differential equations. Steady and transient analysis was carried out and the results can be useful for the plant design and the safety analysis.

Very High Temperature Reactor Vessel cooling system Natural convection heat transfer Vertical rectangular channel Porous material

Tetsuaki Takeda Akira Honma Yuta Sugai Koji Toriyama

Graduate school of Medicine and Engineering, University of Yamanashi Takeda 4-3-11, Kofu-shi, Yamanashi-ken, 400-8511, JAPAN

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1819-1830

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)