Comparison of Fracture Toughness of Irradiated Reactor Vessel Welds - Predicted by ASTM E 900 and Measured /
Recently, a new predictive model has been developed by the NRC and is being implemented in ASTM Standard E 900, that addresses radiation-induced embrittlement of ferritic steels. The model is based on extensive Charpy impact energy data of irradiated reactor vessel steels obtained from surveillance...
| Main Authors: | , |
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| Corporate Authors: | , |
| Format: | Book |
| Language: | English |
| Published: |
West Conshohocken, Pa. :
ASTM International,
2000
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| Subjects: |