ASTM E636-20
Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels

Standard No.
ASTM E636-20
Release Date
2020
Published By
American Society for Testing and Materials (ASTM)
Latest
ASTM E636-20
Scope
1.1 This 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. 1.2 This 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. 1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.4 This 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 E636-20 Referenced Document

  • ASTM E1253 Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
  • ASTM E1820 Standard Test Method for Measurement of Fracture Toughness
  • ASTM E185 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
  • ASTM E1921 Standard Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range
  • ASTM E2215 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
  • ASTM E2298 Standard Test Method for Instrumented Impact Testing of Metallic Materials
  • ASTM E23 Standard Test Methods for Notched Bar Impact Testing of Metallic Materials
  • ASTM E399 Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials

ASTM E636-20 history

  • 2020 ASTM E636-20 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
  • 2014 ASTM E636-14e1 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
  • 2014 ASTM E636-14 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E?706 40;IH41;
  • 2010 ASTM E636-10 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
  • 2009 ASTM E636-09 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
  • 2002 ASTM E636-02 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
  • 1995 ASTM E636-95(2001) Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
  • 1995 ASTM E636-95 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels



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