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The SCC of stainless steels has been an issue facing light water reactors (LWRs) since 1965 when sensitized components failed in the Dresden boiling water reactor (BWR). Numerous experimental efforts have been performed to characterize the SCC of stainless steel in LWRs in the last several decades and many of these efforts have been reported at each of the prior Environmental Degradation of Materials Conferences. Recent research has focused on characterizing SCCGR dependencies in hydrogen deaerated water. Testing of cold worked (CW) stainless steel has shown that heavily CW stainless steel has Arrhenius temperature functionality with a thermal activation energy of roughly 75 kJ/mol . In moderately to low CW stainless steel, a departure from Arrhenius temperature functionality is observed due to high temperature SCCGR retardation (HTR). This paper further extends this research and describes tests which were conducted to characterize the SCCGR temperature dependency of sensitized and CW 304 SS in hydrogenated water.
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UNS S31400 stainless steel was tested as a reactor material for a thermal cracking process of agricultural, silvicultural, industrial and anthropogenic resources containing HCl. This material was chosen as it offers proper corrosion resistance in hot gases besides a good price and a high availability.