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ASTM E636-95(2001)

Current Reaffirmation

Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

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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.


SDO ASTM: ASTM International
Document Number E636
Publication Date Oct. 10, 1995
Language en - English
Page Count 9
Revision Level 95(2001)
Supercedes
Committee E10.02
Publish Date Document Id Type View
Jan. 1, 2020 E0636-20 Revision
Jan. 1, 2014 E0636-14E01 Revision
Jan. 1, 2014 E0636-14 Revision
March 1, 2010 E0636-10 Revision
Feb. 1, 2009 E0636-09 Revision
June 10, 2002 E0636-02 Revision
Oct. 10, 1995 E0636-95 Revision
Oct. 10, 1995 E0636-95R01 Reaffirmation