Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels

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Authors: E10 Committee
Cited by: 0

Abstract

Significance and Use3.1 Practices E185 and E2215 describe a minimum program for the surveillance of reactor vessel materials, specifically mechanical property changes that occur in service. This guide may be applied to generate additional information on

Fields of Study & Subjects

High Temperature Alloys and Creep Nuclear Materials and Properties Fatigue and fracture mechanics

Publication details

Publication date
1 February 2026
Language
EN