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Kitamura, Tatsuaki*; Sakamoto, Kensaku; Takase, Kazuyuki
Kashika Joho Gakkai-Shi, 32(Suppl.2), p.239 - 240, 2012/10
In the thermal-hydraulic design of supercritical water-cooled reactors, it is required to establish a thermal-hydraulic analysis method which can simulate the heat transfer and fluid flow characteristics of supercritical fluids precisely. A crossing flow is a phenomenon in which the fluid flowing through the inside of a fuel bundle in the perpendicular direction moves between subchannels to a transverse direction. The crossing flow influences the removal heat of a reactor core greatly. In the present study, results of the preliminary crossing flow simulation are described.