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ASTM E509/E509M PDF
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Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
| Published by | Publication Date | Number of Pages |
| ASTM | 02/01/2021 | 12 |
ASTM E509/E509M – Standard Guide forIn-Service Annealing of Light-Water Moderated Nuclear ReactorVessels
1.1”This guide covers the general procedures for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical properties, especially fracture toughness, of the reactor vessel materials previously degraded by neutron embrittlement. The improvement in mechanical properties generally is assessed using Charpy V-notch impact test results, or alternatively, fracture toughness test results or inferred toughness property changes from tensile, hardness, indentation, or other miniature specimen testing (1).2
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