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- W2359322243 abstract "To assess the validity of the L VSL(vessel water level)measurement of the CCMS(core cooling and monitoring system)in CPR1000 nuclear power plants under condition of LOCA(loss of coolant accident),the error of the L VSL measurement due to the post-LOCA physical phenomenon which may have impact on the measurement of dynamic and static pressures,and the special phenomenon in vessel-head was quantitatively calculated.The analysis results show that several minutes after discharging through the break,the error of the L VSL measurement induced by the special phenomenon in vessel-head and cold-leg or hot-leg break flow rate can be ignored.The flow rate of the break on the vessel-head and the stagnant water in the control rod guide tube will induce a significant over-estimated error to the L VSL measurement.The analysis combined with SOP(state oriented procedure)shows that the over-estimated error will not hinder the implementation of the safety important actions for accident management." @default.
- W2359322243 created "2016-06-24" @default.
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- W2359322243 date "2014-01-01" @default.
- W2359322243 modified "2023-09-27" @default.
- W2359322243 title "Analysis of Impact on Vessel Water Level Measurement due to Post-LOCA Physical Phenomenon" @default.
- W2359322243 hasPublicationYear "2014" @default.
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