Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing /
The Heavy-Section Steel Irradiation Program at Oak Ridge National Laboratory includes a task to investigate the propensity for temper embrittlement in coarse grain regions of heat-affected zones in prototypic reactor pressure vessel (RPV) steel weldments as a consequence of irradiation and thermal a...
Main Authors: | , , , , |
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Corporate Authors: | , , |
Format: | Conference Proceeding Book |
Language: | English |
Published: |
West Conshohocken, Pa. :
ASTM International,
2001
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Subjects: |