ASTM E531-23
(Practice)Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials
Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials
SIGNIFICANCE AND USE
4.1 The practice contained herein can be used as a basis for establishing conditions for the safe operation of critical structural components. The practices provide for general plant assessment and verification that materials continue meet design criteria and may in addition be of use for asset protection or life extension. The test specimens and procedures presented in this practice are for guidance when establishing a surveillance program.
4.2 This practice for high-temperature materials surveillance programs is used when nuclear reactor component materials are monitored by specimen testing. Periodic testing is performed through the service life of the components to assess changes in selected material properties that are caused by neutron irradiation, thermal effects, chemical reactions, and mechanical stress. The properties of interest are those used as design criteria for the respective nuclear components or well correlated to said criteria (see 5.1.6). The need for surveillance arises from the need to assess predictions of aging material performance to ensure adequate component performance.
4.3 This practice describes specimens and procedures required for the surveillance of multiple components. A surveillance program for a particular component will not necessarily require all test types described herein.
SCOPE
1.1 This practice covers procedures for surveillance program design and specimen testing to establish changes occurring in the mechanical properties of ferrous and nickel-based materials due to irradiation and thermal effects of nuclear component metallic materials used for high-temperature structural applications above 370 °C (700 °F). This should include consideration of gamma heating. This practice currently only applies to an initial program based on initial estimates of design life of components.
1.2 This practice was developed for non-light-water moderated nuclear power reactors.
1.3 This practice does not provide specific procedures for extending surveillance programs beyond their original design lifetimes.
1.4 This practice does not consider in-situ monitoring techniques but may provide insights into the proper periodicity and design of such.
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
1.7 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.
General Information
Relations
Standards Content (Sample)
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: E531 − 23
Standard Practice for
Surveillance Testing of High-Temperature Nuclear
1
Component Materials
This standard is issued under the fixed designation E531; 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. Scope 2. Referenced Documents
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2.1 ASTM Standards:
1.1 This practice covers procedures for surveillance pro-
A370 Test Methods and Definitions for Mechanical Testing
gram design and specimen testing to establish changes occur-
of Steel Products
ring in the mechanical properties of ferrous and nickel-based
E8/E8M Test Methods for Tension Testing of Metallic Ma-
materials due to irradiation and thermal effects of nuclear
terials
component metallic materials used for high-temperature struc-
E21 Test Methods for Elevated Temperature Tension Tests of
tural applications above 370 °C (700 °F). This should include
Metallic Materials
consideration of gamma heating. This practice currently only
E29 Practice for Using Significant Digits in Test Data to
applies to an initial program based on initial estimates of
Determine Conformance with Specifications
design life of components.
E45 Test Methods for Determining the Inclusion Content of
1.2 This practice was developed for non-light-water moder-
Steel
ated nuclear power reactors.
E112 Test Methods for Determining Average Grain Size
E139 Test Methods for Conducting Creep, Creep-Rupture,
1.3 This practice does not provide specific procedures for
and Stress-Rupture Tests of Metallic Materials
extending surveillance programs beyond their original design
E185 Practice for Design of Surveillance Programs for
lifetimes.
Light-Water Moderated Nuclear Power Reactor Vessels
1.4 This practice does not consider in-situ monitoring tech- E261 Practice for Determining Neutron Fluence, Fluence
niques but may provide insights into the proper periodicity and Rate, and Spectra by Radioactivation Techniques
design of such. E482 Guide for Application of Neutron Transport Methods
for Reactor Vessel Surveillance
1.5 The values stated in SI units are to be regarded as the
E844 Guide for Sensor Set Design and Irradiation for
standard. The values given in parentheses are for information
Reactor Surveillance
only.
E1820 Test Method for Measurement of Fracture Toughness
E2006 Guide for Benchmark Testing of Light Water Reactor
1.6 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the Calculations
E2586 Practice for Calculating and Using Basic Statistics
responsibility of the user of this standard to establish appro-
priate safety, health, and environmental practices and deter- E2714 Test Method for Creep-Fatigue Testing
E2760 Test Method for Creep-Fatigue Crack Growth Testing
mine the applicability of regulatory limitations prior to use.
1.7 This international standard was developed in accor-
3. Terminology
dance with internationally recognized principles on standard-
3.1 Definitions of Terms Specific to This Standard:
ization established in the Decision on Principles for the
3.1.1 capsule—a set of specimens to be placed into the
Development of International Standards, Guides and Recom-
system and extracted at the same time.
mendations issued by the World Trade Organization Technical
3.1.2 critical component—critical components are those that
Barriers to Trade (TBT) Committee.
are required for the safe operation of the subject design (that is,
important to safety). In the context of this practice, it is
assumed that these components are structural.
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This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applications and is the direct responsibility of Subcommittee
2
E10.02 on Behavior and Use of Nuclear Structural Materials. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Sept. 1, 2023. Published October 2023. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1975. Last previous edition approved in 2013 as E531 – 13, which was Standards volume information, refer to the standard’s Document Summary page on
withdrawn in 2022 and reinstated September 2023. DOI: 10.1520/E0531-23. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E531 − 23
3.1.3 representative—a characteristic that is as close as b
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