Flaw Evaluation, Service Experience, and Materials for Hydrogen Service 2004
DOI: 10.1115/pvp2004-2555
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Advanced Nondestructive Examination Technologies for Alloy 600 Components

Abstract: Several pressurized water reactors have experienced primary coolant leaks as a result of degradation in the tubes and J-groove welds of reactor vessel head penetrations. Leakage has been attributed to primary water stress corrosion cracking (PWSCC) of the Alloy 600 nozzle material and Alloy 182/82 weld materials. More recently, other Alloy 600 components including reactor vessel bottom mounted instrumentation nozzles, dissimilar metal pipe welds, hot leg instrument penetrations, and pressurizer heater sleeves … Show more

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