Subcommittee E10.02 on Behavior and Use of Nuclear Structural Materials | ASTM

Using Artificial Intelligence (AI) on ASTM standards and related intellectual property is prohibited. Violations will result in suspension of access.

Home
FAQ

Home
FAQ

Home
Membership & Participati…

/

Technical Committees

/

Subcommittee E10.02 on B…

Subcommittee E10.02 on Behavior and Use of Nuclear Structural Materials

Loading...

About ASTM

Governance Global Cooperation Corporate Citizenship History Regional Offices and Websites Diversity, Equity, Inclusion & Belonging Culture & Careers

Membership & Participation

Membership Technical Committees Member Tools Meetings, Symposia & Workshops Academic Outreach Emerging Professionals Publish with ASTM Consumer Participation

Standards & Solutions

Standards & Publications Enterprise Solutions ASTM Compass®Digital Library Market Insights & Innovation Laboratory Services Training Courses Certification Cement & Concrete Reference Lab

News

Standardization News Press Releases Podcasts Español Editorial Calendar and Media Kit

Help

Contact ASTM Locations FAQ

Policies

Privacy Policy Logo Policy IP Policy Return Policy Copyright & Permissions

Copyright © 1996 - 2025 ASTM. All Rights Reserved. ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA, 19428-2959 USA

Matching Standards Under the Jurisdiction of E10.02 by Status

E185-25 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
-See also WK93945 proposed Revision
-See also WK93456 proposed Revision
E509/E509M-21 Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
E531-24 Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials
E636-20 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
-See also WK94534 proposed Reapproval
-See also WK94533 proposed Revision
E821-16(2023) Standard Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation
E900-21 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E1214-11(2023) Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
E1253-21 Standard Guide for Reconstitution of Charpy-Sized Specimens
E2215-24 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
E3205-20 Standard Test Method for Small Punch Testing of Metallic Materials
-See also WK94279 proposed Revision

E453-79(2001) Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties (Withdrawn 2008)
E184-79(1994) Standard Practice for Effects of High-Energy Neutron Radiation on the Mechanical Properties of Metallic Materials, E706 (IB) (Withdrawn 2002)