
Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
出版:American Society for Testing and Materials

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CONTAINED IN VOL. 12.02, 2007Presents a method for predicting reference transition temperature adjustments for irradiated light-water cooled power reactor pressure vessel materials based on Charpy V-notch 41-J (30-ftlbf) data.