Abstract
Hydrogen charging conditions that completely embrittle an ultra-high strength steel have a negligible effect on 212-B pressure vessel steel in tensile and delayed failure tests, Much higher hydrogen charges reduce the notch tensile strength. Delayed failure is observed only at stresses greater than 90% of the notch tensile strength of the hydrogenated metal. The primary purpose of the present investigation was to determine whether or not irradiated reactor pressure vessel steels become susceptible to hydrogen embrittlement. Tests on 212-B irradiated to give a 35% increase in strength and a nil-ductility (NDT) temperature shift of 110°C showed the same relationship between delayed failure limits and notch tensile strength. Catastrophic embrittlement due to hydrogen (like delayed failures at 25 to 50% of the notch tensile strength in 4340) are not observed in 212-B steel, even for irradiated material and with the high hydrogen contents studied. Delayed failure behavior was similar to that observed in unirradiated material. Therefore, catastrophic hydrogen embrittlement of a well-designed nuclear reactor pressure vessel is not believed credible.
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