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

ASTM-E636 - 2020 EDITION - CURRENT
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Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
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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.

To find similar documents by ASTM Volume:

12.02 (Nuclear (II), Solar, and Geothermal Energy)

To find similar documents by classification:

27.120.10 (Reactor engineering)

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Document Number

ASTM-E0636-20

Revision Level

2020 EDITION

Status

Current

Modification Type

Revision

Publication Date

Jan. 1, 2020

Document Type

Guide

Page Count

7 pages

Committee Number

E10.02