ASTM E636-20
(Guide)Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
SIGNIFICANCE AND USE
3.1 Practices E185 and E2215 describe a minimum program for the surveillance of reactor vessel materials, specifically mechanical property changes that occur in service. This guide may be applied to generate additional information on radiation-induced property changes to better assist the determination of the optimum reactor vessel operation schemes.
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.
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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.
Designation: E636 − 20
Standard Guide for
Conducting Supplemental Surveillance Tests for Nuclear
1
Power Reactor Vessels
This standard is issued under the fixed designation E636; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope E399Test Method for Linear-Elastic Plane-Strain Fracture
Toughness K of Metallic Materials
Ic
1.1 This guide discusses test procedures that can be used in
E1253Guide for Reconstitution of Irradiated Charpy-Sized
conjunction with, but not as alternatives to, those required by
Specimens
Practices E185 and E2215 for the surveillance of nuclear
E1820Test Method for Measurement of FractureToughness
reactor vessels. The supplemental mechanical property tests
E1921 Test Method for Determination of Reference
outlined permit the acquisition of additional information on
Temperature, T , for Ferritic Steels in the Transition
o
radiation-induced changes in mechanical properties of the
Range
reactor vessel steels.
E2215Practice for Evaluation of Surveillance Capsules
1.2 This guide provides recommendations for the prepara-
from Light-Water Moderated Nuclear Power ReactorVes-
tion of test specimens for irradiation, and identifies special
sels
precautions and requirements for reactor surveillance opera-
E2298Test Method for Instrumented Impact Testing of
tions and post-irradiation test planning. Guidance on data
Metallic Materials
reduction and computational procedures is also given. Refer-
3
2.2 ASME Standards:
ence is made to other ASTM test methods for the physical
ASME Boiler and PressureVessel Code, Section IIISubsec-
conduct of specimen tests and for raw data acquisition.
tion NB (Class 1 Components)
1.3 The values stated in SI units are to be regarded as the
standard. The values given in parentheses are for information
3. Significance and Use
only.
3.1 PracticesE185andE2215describeaminimumprogram
1.4 This international standard was developed in accor-
for the surveillance of reactor vessel materials, specifically
dance with internationally recognized principles on standard-
mechanical property changes that occur in service. This guide
ization established in the Decision on Principles for the
maybeappliedtogenerateadditionalinformationonradiation-
Development of International Standards, Guides and Recom-
induced property changes to better assist the determination of
mendations issued by the World Trade Organization Technical
the optimum reactor vessel operation schemes.
Barriers to Trade (TBT) Committee.
4. Supplemental Mechanical Property Test
2. Referenced Documents
4.1 Fracture Toughness Test—This test consists of a quasi-
2
2.1 ASTM Standards:
static or dynamic test of a fatigue-precracked specimen during
E23Test Methods for Notched Bar Impact Testing of Me-
which a record of force versus displacement is used to
tallic Materials
determine material fracture toughness properties such as the
E185Practice for Design of Surveillance Programs for
plane-strain fracture toughness (J ), the J-R curve, and the
Ic
Light-Water Moderated Nuclear Power Reactor Vessels
Master Curve reference temperature (T ) (see Test Methods
o
E1820,andE1921,respectively).Thesetestmethodsgenerally
apply to ductile-to-brittle transition, or fully plastic behavior.
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
The rate of specimen loading or stress intensity increase
Technology and Applications and is the direct responsibility of Subcommittee
required for test classification as quasi-static or dynamic is
E10.02 on Behavior and Use of Nuclear Structural Materials.
indicatedbythereferencedtestmethods.Allthreetestmethods
Current edition approved Jan. 1, 2020. Published January 2020. Originally
ɛ1
specify a lower limit on loading rate for dynamic tests.
approved in 1983. Last previous edition approved in 2014 as E636–14 . DOI:
10.1520/E0636-20.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
3
Standards volume information, refer to the standard’s Document Summary page on Available from American Society of Mechanical Engineers, 345 E. 47th St.,
the ASTM website. New York, NY 10017.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E636 − 20
4.2 Fracture Toughness Test at Impact Loading Rates—This
testconsistsofimp
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
´1
Designation: E636 − 14 E636 − 20
Standard Guide for
Conducting Supplemental Surveillance Tests for Nuclear
1
Power Reactor Vessels
This standard is issued under the fixed designation E636; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1
ε NOTE—The title of this guide was updated editorially in May 2017.
1. 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.
2. Referenced Documents
2
2.1 ASTM Standards:
E23 Test Methods for Notched Bar Impact Testing of Metallic Materials
E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E399 Test Method for Linear-Elastic Plane-Strain Fracture Toughness K of Metallic Materials
Ic
E1253 Guide for Reconstitution of Irradiated Charpy-Sized Specimens
E1820 Test Method for Measurement of Fracture Toughness
E1921 Test Method for Determination of Reference Temperature, T , for Ferritic Steels in the Transition Range
o
E2215 Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
E2298 Test Method for Instrumented Impact Testing of Metallic Materials
3
2.2 ASME Standards:
ASME Boiler and Pressure Vessel Code, Section III Subsection NB (Class 1 Components)
3. Significance and Use
3.1 Practices E185 and E2215 describe a minimum program for the surveillance of reactor vessel materials, specifically
mechanical property changes that occur in service. This guide may be applied in order to generate additional information on
radiation-induced property changes to better assist the determination of the optimum reactor vessel operation schemes.
4. Supplemental Mechanical Property Test
4.1 Fracture Toughness Test—This test involves the dynamic or static testingconsists of a quasi-static or dynamic test of a
fatigue-precracked specimen during which a record of force versus displacement is used to determine material fracture toughness
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.02 on
Behavior and Use of Nuclear Structural Materials.
Current edition approved Jan. 1, 2014Jan. 1, 2020. Published February 2014January 2020. Originally approved in 1983. Last previous edition approved in 20102014 as
ɛ1
E636 – 10.E636 – 14 . DOI: 10.1520/E0636-14E01.10.1520/E0636-20.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3
Available from American Society of Mechanical Engineers, 345 E. 47th St., New York, NY 10017.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E636 − 20
properties such as the plane strain fracture toughness (Kplane-strain ), the J-integral fracture toughness (J ), the J-R curve, and
Ic Ic
the Master Curve reference temperature (T ) (see Test Methods E399, E1820, and E1921, respectively). These test meth
...
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