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97106 HYDROGEN DISTRIBUTION KINETICS IN STAINLESS STEEL DURING LWR EXPOSURE

Picture for 97106 HYDROGEN DISTRIBUTION KINETICS IN STAINLESS
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Product Number: 51300-97106-SG
ISBN: 97106 1997 CP
Author: E. P. Simonen, S. M. Bruemmer
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A calculational approach has been used to evaluate potential sources, transport, and distribution of hydrogen in light-water reactor (LWR) irradiated stainless steel. The calculations indicate that corrosion- induced hydrogen can achieve significant and uniform concentration profiles in structures of reasonable thickness, i.e., 3 mm. The LWR temperature of about 288°C is sufficient to promote diffusion without the aid of radiation-enhanced diffusion. If the in-core hydrogen fugacity is significantly higher than ex-core hydrogen fugacity, it is predicted that hydrogen outgassing will occur during times associated with exreactor slow strain rate testing. Differences between hydrogen effects on in-core irradiationassisted stress corrosion cracking (lASCC) and ex-core IASCC are expected. Hydrogen traps in stainless steel are not important at LWR temperatures. Lastly, calculated transmutation hydrogen inventories are small even when a surface oxide barrier exists blocking the release of hydrogen. Keywords: Hydrogen, kinetics, calculation, irradiation assisted stress corrosion cracking, temperature.
A calculational approach has been used to evaluate potential sources, transport, and distribution of hydrogen in light-water reactor (LWR) irradiated stainless steel. The calculations indicate that corrosion- induced hydrogen can achieve significant and uniform concentration profiles in structures of reasonable thickness, i.e., 3 mm. The LWR temperature of about 288°C is sufficient to promote diffusion without the aid of radiation-enhanced diffusion. If the in-core hydrogen fugacity is significantly higher than ex-core hydrogen fugacity, it is predicted that hydrogen outgassing will occur during times associated with exreactor slow strain rate testing. Differences between hydrogen effects on in-core irradiationassisted stress corrosion cracking (lASCC) and ex-core IASCC are expected. Hydrogen traps in stainless steel are not important at LWR temperatures. Lastly, calculated transmutation hydrogen inventories are small even when a surface oxide barrier exists blocking the release of hydrogen. Keywords: Hydrogen, kinetics, calculation, irradiation assisted stress corrosion cracking, temperature.
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Assessment of sigma phase embrittlement in austenitic stainless steels such as Type 304H, commonly used in fluid catalytic cracking (FCC) units. Other austenitic stainless steels used in other refining process units are also discussed. The detection and measuring of the amount of sigma phase were made using metallography. 
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