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KMID : 0371819980300060609
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Nuclear Engineering and Technology
1998 Volume.30 No. 6 p.609 ~ p.616
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Estimation of Thermal Aging Embrittlement of LWR Primary Pressure Boundary Components
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Kim Sunki
Kim Yongsoo
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Abstract
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Cast duplex stainless steels are extensively used for primary pressure boundary components. These components are, however, embrittled due to the precipitation of α´ phase by spinodal decomposition and other processes when exposed to reactor operating temperature for a design lifetime or life extension conditions. This report presents a procedure for estimating the current condition and the residual life of safety-related stainless steel components by using ANL database and correlations. The database of Charpy impact energy suggests that CF-8M grade is the most susceptible to thermal aging and CF-3 grade is the least. Thus, the integrity of CF-8M alloys may be degraded seriously and the degree of deterioration may exceed acceptance limit after several years of service in the nuclear reactors.
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