ASTM E 636 : 2020 : R2026
Current
The latest, up-to-date edition.
Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
English
01-02-2026
| Committee |
E 10
|
| DocumentType |
Guide
|
| Pages |
7
|
| PublisherName |
American Society for Testing and Materials
|
| Status |
Current
|
| Supersedes |
1.1ÂThis guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in mechanical properties of the reactor vessel steels.
1.2ÂThis guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and post-irradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.
1.3ÂThe values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.4ÂThis international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
| ASTM E 185 : 2025 | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
| ASTM E 509/E509M : 2021 | Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels |
| ASTM E 1005 : 2021 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
| ASTM E 2215 : 2024 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
| ASTM E 706 : 2023 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards |
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