L OCA 后物理现象对压力容器水位测量影响分析.pdfVIP

４８１２ Vol ．４８ ，No ．１２ ２０１４１２ Atomic Energy Science and Technology Dec ．２０１４ LOCA ，， ，， （， ５１８０４９） ：CPR１０００ （LOCA ）（CCMS） （L VSL ），LOCA ， L VSL 。 ， L VSL ， L VSL， SOP ， 。 ：；；；； ：TL３６３ ：A ：１０００‐６９３１（２０１４）１２‐２２９２‐０６ doi ：１０ ．７５３８／ zk ．２０１４ ．４８ ．１２ ．２２９２ y Analysis of Impact on Vessel Water Level Measurement due to Post‐LOCA Physical Phenomenon MA Ting‐wei ，WANG Zhen‐ ing ，SUN Chen ，LI Run‐sheng ，WU Guang‐un y j （China N uc lear Pow e r Eng inee r ing Co ．， L td ．， Shenz hen ５１８０４９ ， China） 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 quantita‐ tively calculated ． The analysis results show that several minutes after discharging through the break ，the error of the L VSL measurement induced by the special phenom ‐ enon 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 com‐ bined with SOP （state oriented procedure ） show s that the over‐estimated error will not hinder the implementation of the safety important actions for accident management ． Key words ： LOCA ；core cooling ；vessel