Standard Historical Last Updated: Aug 16, 2017 Track Document
ASTM E636-95(2001)

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, E706 (IH) E0636-95R01 ASTM|E0636-95R01|en-US Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH) Standard new BOS Vol. 12.02 Committee E10
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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.

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Details
Book of Standards Volume: 12.02
Developed by Subcommittee: E10.02
Pages: 9
DOI: 10.1520/E0636-95R01
ICS Code: 27.120.10