Preliminary Study of Bypass Flow in Prismatic Core of Very High Temperature Reactor Using Small-Scale Model
Very high temperature reactor (VHTR) is one of the candidates for Generation IV reactor. It can be continuously operated with average core outlet temperature between 900°C and 950°C, so the core temperature is one of the key features in the design of VHTR. Bypass flow in the prismatic core of VHTR i...
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| Format: | Others |
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2013
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| Online Access: | http://hdl.handle.net/1969.1/148222 |