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Secondary Side Inter granular Attack and Stress Corrosion Cracking (IGA/SCC) have affected all major steam generator designs. According to the statistics, roughly 50% of all Pressurized Water Reactor plants are attacked by IGA/SCC. The characteristics of IGA/SCC and eddy current inspection and evaluation for nuclear power plant steam generator tubes were studied. It was found that the combined effects of stress. temperature and susceptible material could lead to IGA/SCC initiation and growth. In most cases, the IGA/SCC has been located at the top of the hot leg tube sheet, in open tube sheet crevice areas, and typically at the lower hot leg tube support plate intersections. For eddy current inspection and evaluation, it is necessary to monitor the vertical tracks of the differential mix and the low frequency absolute channel. Mainly we discussed the characteristics of two kinds of IGA/SCC and offered basic criterions to do data analysis.