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ÖÐͼ·ÖÀàºÅ:TL363 ÎÄÏ×±êʶÂë:A ÎÄÕ±àºÅ:1009-914X(2014)17-0287-02
Analysis of the impact on vessel water level
measurement due to RHRS operation and steam
generator plugging
Zhang Wei
(CNNC Hunan Taohuajiang Nuclear Power Engineering Company,Ltd,Yiyang of Hunan Prov.413000,China)
[Abstract]CCMS (Core Cooling and Monitoring System) of CPR1000 nuclear power plants measures the pressure difference between reactor
vessel top and bottom to realize the reactor vessel water level (L VSL) measurement. Based on the measurement principal of CCMS L VSL, for the
analysis of impact on vessel water level measurement due to RHRS operation and steam generator plugging, the article deduces the equation of
error and calculates it. The result shows that the uncertainty induced by RHRS operation and steam generator plugging can be ignored.
[Key words]Core cooling; Vessel water level; Error; Steam generator plugging
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