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核三廠MUR後預期暫態未急停RCS壓力安全分析
Thesis

核三廠MUR後預期暫態未急停RCS壓力安全分析

吳文雄
Masters, National Tsing Hua University
2008

Abstract

核三廠小幅度功率提升預期暫態未急停
The reactor coolant system (RCS) pressure transients under ATWS for Maanshan PWR with MUR conditions were analyzed in this study. The main concern was to observe whether the peak RCS pressure still maintained within 3200 psig limit (defined by ASME Code Level C service limit criterion under 100% rated power). The Maanshan RETRAN model, which had been developed for PWR transients, was used for ATWS safety analysis and related sensitivity analysis under MUR conditions. In document SECY-83-293, all initializing events were classified as either turbine trip or non-turbine trip events and their ATWS risks were also evaluated according to these two events. Loss of normal feedwater (LONF) and Loss of condenser vacuum (LOCV) ATWS were identified as limiting transients of non-turbine trip and turbine trip events in this study. In order to analyze the RCS pressure variations, a moderator density coefficient (MDC) model was included to observe the influences of moderator temperature and system pressure to the reactor reactivity, and the possibility of the peak RCS pressure reaching its limit. In addition, this study also covers the following sensitivity studies, (1)MTC settings, (2)RCP trip assumption, (3)initial conditions of steam generator outlet pressure, and(4)the model of steam generator. The peak RCS pressure was found to stay within the criterion of 3200 psig even at a conservative MTC setting of -4 pcm/℉.

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