CFD Analysis for Flow Resistance of Cross-flow Gap in VHTR
VHTR (Very High Temperature Reactor) is high-efficiency nuclear reactor which is capable of generating hydrogen with high temperature of coolant. PMR(Prismatic Modular Reactor) type reactor consists of hexagonal prismatic fuel blocks and reflector blocks. The blocks are graphite which can withstand the high temperatures. However the graphite assembly could shrink due to neutron flux and then the shrinkage makes the gap of blocks wide. Most of the reactor coolant passes through the coolant channels and other coolant passes through the gap of the blocks. The core bypass flow is defined as the core flow that does not pass through the coolant channels but passes through the bypass gap between fuel elements. The increase in bypass flow makes the decrease in effective coolant flow. Since the core bypass flow has a negative impact on safety and efficiency of VHTR, core flow distribution characteristics have to be investigated to improve the core thermal margin of VHTR. The cross flow which flows between layers could make the core flow more complex. Hence, the study of cross flow is important. The CFD is powerful tool for flow analysis of the VHTR core. To apply CFD to the developing core type the analysis ability of the CFD and it can be evaluated by comparing experimental results and the CFD results. In this study, the analysis ability of the CFD for the cross flow were evaluated by comparing existing experimental results and the CFD results and the major features of cross flow were discussed.
VHTR Cross-flow Flow Resistance loss coefficient CFD
Jeong-Hun Lee Su-Jong Yoon Jong Woon Park Goon-Cherl Park
Nuclear Engr., Seoul National Univ., Daehak-dong, Gwanak-gu, Seoul, 151-742, Korea Nuclear & Energy Engr., Dongguk Univ., Seokjang-Dong, Gyeongju, Gyeongsangbuk-Do, 780-714, Korea
国际会议
4th International Symposium on Heat Transfer and Energy Conservation(第四届传热与节能国际研讨会 ISHTEC2012)
广州
英文
1-5
2012-01-06（万方平台首次上网日期，不代表论文的发表时间）