发明名称 CORE SUPPORT STRUCTURE OF REACTOR VESSEL
摘要 PROBLEM TO BE SOLVED: To surely measure reactor average temperature in piping connecting to outlet nozzles by arranging flow stabilization members in the core structure for almost all region of outside core region and between upper core support plates. SOLUTION: A perforation member 50 is provided on an upper core plate in the upper plenum corresponding to the core periphery in an open region S'-S' where no core support structure such as control rod cluster guide tube 22, upper core support column 23, etc., exists, that is, a location having no primary coolant flow of penetrating the upper core plate. The perforation member 50 is provided with almost all length between the upper core plate and the upper core support plate partitioning the upper plenum and desirably has nearly the same cross sectional area.
申请公布号 JP2000121776(A) 申请公布日期 2000.04.28
申请号 JP19980293919 申请日期 1998.10.15
申请人 MITSUBISHI HEAVY IND LTD 发明人 ICHIKAWA TOSHIRO;MATSUSHIMA YOKO;KUBO NOBORU;NAKAJIMA MAKOTO;IZUMI HAJIME
分类号 G21C15/02;G21C5/10;G21C13/02;G21C15/00;(IPC1-7):G21C15/02 主分类号 G21C15/02
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