ASTM E636-95
Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)

Standard No.

ASTM E636-95

Release Date

1995

Published By

American Society for Testing and Materials (ASTM)

Status

Be replaced

Replace By

ASTM E636-95(2001)

Latest

ASTM E636-20

Scope

1.1 This guide covers test methods and procedures that can be used in conjunction with, but not as alternatives to, those required by Practice E185 for the surveillance of nuclear reactor vessels. The supplemental test methods outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and tensile strength 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 postirradiation test planning. Guidance on data reduction and computational procedures also is given for individual test methods. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.

ASTM E636-95 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)