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
- Status
- Published
- Publication Date
- 31-Aug-2023
- Technical Committee
- E10 - Nuclear Technology and Applications
- Drafting Committee
- E10.02 - Behavior and Use of Nuclear Structural Materials
Relations
- Effective Date
- 01-Sep-2023
- Effective Date
- 01-Mar-2024
- Effective Date
- 01-Jan-2024
- Effective Date
- 01-Nov-2023
- Effective Date
- 15-Sep-2023
- Effective Date
- 01-May-2022
- Effective Date
- 01-Nov-2019
- Effective Date
- 01-Nov-2019
- Effective Date
- 01-Jun-2018
Overview
ASTM E531-23: Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials establishes procedures for the design and execution of surveillance testing programs. This standard is essential for monitoring critical structural components made from ferrous and nickel-based alloys exposed to high-temperature environments (above 370 °C/700 °F), such as those in non-light-water moderated nuclear power reactors. Regular surveillance testing helps verify that material properties remain within design criteria, thereby supporting the safe operation, asset protection, and potential life extension of nuclear plant components.
Key Topics
- Material Surveillance Programs: Guidance on planning and implementing programs that periodically test representative specimens to evaluate property changes due to irradiation, thermal exposure, and other operational stresses.
- Specimen Requirements: Criteria for pre-exposure characterization, specimen type selection, and preparation methods, ensuring tested materials closely match the conditions faced by in-service components.
- Irradiation and Environmental Conditions: Recommendations for aligning specimen exposure to actual component environments, including neutron fluence rates, temperatures, and coolant conditions. Special attention is given to swelling, creep, and other degradation mechanisms relevant at high temperatures.
- Test Methods and Reporting: Integration with referenced ASTM standards for mechanical testing, creep and stress-rupture evaluation, fracture toughness measurements, and more, ensuring reliable, comparable data collection.
- Surveillance Scheduling: Schedules for specimen withdrawal and testing to monitor materials throughout the intended service life, with the possibility to inform component life extension decisions.
- Statistical Evaluation: Use of statistical methodologies to ensure test program significance and data reliability for safety-critical decisions.
Applications
ASTM E531-23 is highly relevant for:
- Nuclear Power Plant Operators and Engineers: Ensuring ongoing compliance with safety and performance criteria in high-temperature nuclear components through scheduled surveillance programs.
- Component Fabricators and Material Suppliers: Selecting, preparing, and documenting test specimens that reflect production materials, including welds and heat-affected zones, for inclusion in surveillance capsules.
- Regulatory Authorities: Assessing the adequacy of material surveillance programs in support of licensing, operation, and life extension of nuclear facilities.
- Asset Protection Initiatives: Using long-term material performance data to guide maintenance strategies and potential upgrades for aging nuclear infrastructure.
- Research and Development: Supporting the development of improved high-temperature alloys and advanced reactor designs by providing performance data under reactor-relevant conditions.
Related Standards
Several ASTM standards are referenced within ASTM E531-23 to ensure consistent and internationally recognized testing procedures:
- ASTM A370: Test Methods and Definitions for Mechanical Testing of Steel Products
- ASTM E8/E8M: Tension Testing of Metallic Materials
- ASTM E21: Elevated Temperature Tension Tests of Metallic Materials
- ASTM E139: Creep, Creep-Rupture, and Stress-Rupture Tests of Metallic Materials
- ASTM E1820: Measurement of Fracture Toughness
- ASTM E112: Determining Average Grain Size
- ASTM E261, E844, E482, and E2006: Guidance on neutron fluence, dosimetry, and irradiation conditions
- ASTM E2586: Statistical Analysis for Test Result Evaluation
- ASTM E185: Surveillance Programs for Light-Water Reactors (for reference)
Keywords: high-temperature nuclear materials, surveillance testing, irradiation effects, nuclear reactor safety, specimen preparation, ASTM E531-23, asset protection, component life extension, non-light-water reactors, statistical evaluation, neutron fluence, creep testing, fracture toughness, oxidation, mechanical property monitoring.
By following ASTM E531-23, organizations can enhance the reliability and safety of nuclear power plant operations, optimize asset management, and effectively respond to evolving regulatory and technical requirements in the nuclear industry.
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Frequently Asked Questions
ASTM E531-23 is a standard published by ASTM International. Its full title is "Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials". This standard covers: 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.
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.
ASTM E531-23 is classified under the following ICS (International Classification for Standards) categories: 13.280 - Radiation protection; 17.200.01 - Thermodynamics in general; 77.040.01 - Testing of metals in general. The ICS classification helps identify the subject area and facilitates finding related standards.
ASTM E531-23 has the following relationships with other standards: It is inter standard links to ASTM E531-13, ASTM A370-24, ASTM E8/E8M-24, ASTM E45-18a(2023), ASTM A370-23, ASTM E8/E8M-22, ASTM E2760-19e1, ASTM E2760-19e2, ASTM E45-18a. Understanding these relationships helps ensure you are using the most current and applicable version of the standard.
ASTM E531-23 is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.
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
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
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.
This practice 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. 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
E531 − 23
3.1.3 representative—a characteristic that is as close as but are not restricted to: yield strength, ultimate tensile
achievable to the actual properties exhibited or experienced by strength, stress-to-rupture, elongation-to-failure, reduction in
a material of interest. area, creep strength, stress rupture life, creep resistance to
creep-fatigue, linear elastic fracture toughness, plastic-elastic
3.1.4 test specimen—a coupon or a piece of metal cut from
fracture toughness, and creep crack growth rate. Relevant
a larger metallic piece which is machined to final size for
temperatures of testing shall be identified as necessary to
testing to determine physical or mechanical properties.
support component integrity. Program shall include specimens
4. Significance and Use
matching properties essential to confirming pertinent design
life calculations; a minimum of one type of specimen must be
4.1 The practice contained herein can be used as a basis for
selected. Users shall document their justification for specimen
establishing conditions for the safe operation of critical struc-
type selection and provide this documentation with the initial
tural components. The practices provide for general plant
report.
assessment and verification that materials continue meet design
5.1.7 Mechanical testing of time-independent properties
criteria and may in addition be of use for asset protection or life
identified in 5.1.6 shall be conducted to provide a pre-exposure
extension. The test specimens and procedures presented in this
baseline for the surveillance program. The number of samples
practice are for guidance when establishing a surveillance
used to determine the time-independent baseline properties
program.
should be greater than or equal to the number of specimens
4.2 This practice for high-temperature materials surveil-
following withdrawal of the surveillance capsule. These con-
lance programs is used when nuclear reactor component
trol tests are recommended to be performed simultaneously
materials are monitored by specimen testing. Periodic testing is
with the first set of tests of exposed specimens to ensure that
performed through the service life of the components to assess
deviations in test results can be attributed to the exposed
changes in selected material properties that are caused by
specimen’s environment and not to variations in testing meth-
neutron irradiation, thermal effects, chemical reactions, and
ods. If nonstandard specimens are being used, tests should be
mechanical stress. The properties of interest are those used as
conducted during the design phase to ensure expected results
design criteria for the respective nuclear components or well
are obtained.
correlated to said criteria (see 5.1.6). The need for surveillance
5.1.8 The information described in 5.1.1 – 5.1.7 should be
arises from the need to assess predictions of aging material
reported in a single document.
performance to ensure adequate component performance.
5.2 Post-Exposure Material Characterization—After expo-
4.3 This practice describes specimens and procedures re-
sure:
quired for the surveillance of multiple components. A surveil-
5.2.1 Mechanical properties identified in 5.1.6 shall be
lance program for a particular component will not necessarily
measured.
require all test types described herein.
5.2.2 The following shall be reported:
5.2.2.1 Observations from visual examination.
5. Test Specimens
5.2.2.2 Changes in specimen weight and dimensions.
5.1 Pre-Exposure Material Characterization—It is impor-
5.2.2.3 Metallographic characteristics (for example, grain
tant that test specimen materials be characterized prior to
size, microstructure, inclusion content, depth of corrosion, and
exposure and that the following shall be documented as a
cracking). Test Methods E45 and E112 should be used, as
minimum:
applicable.
5.1.1 Process history including the percentage of cold work;
5.2.2.4 Quantitative examination of surface chemistry to
material designation; manufacturer; heat number; weld and
evaluate leaching, de-alloying, and other changes to the base
fabrication procedures used; and heat treatment(s).
metal chemistry.
5.1.2 Original location and orientation in the parent mate-
5.2.3 Exposed test specimens should be cleaned in accor-
rial.
dance with accepted cleaning procedures. (Refer to ASTM
5.1.3 Specimen weight and dimensions.
Committee G01 for practices for preparing, cleaning, and
5.1.4 Chemical analysis results (including the specified
evaluating test specimens.) Special consideration should be
elements and appropriate impurity elements). Note that surface
given to specimens exposed to corrosive coolants to minimize
and bulk chemistries may vary due to certain processing
additional corrosion of the specimens once they are removed.
techniques and should be accounted for.
5.1.5 Specimen origin. All specimens shall be taken from 5.3 Specimen Preparation—Test specimens shall be stan-
the locations and orientations specified in Test Methods and dard recommended specimens where possible as described in
Definitions A370 and Test Methods E8/E8M. This includes Test Methods E8/E8M, E21, and E139.
base metal and weld metal to provide a leading indication of 5.3.1 Size—In general, when space limitations exist, smaller
material performance for normal operating and accident con- sized samples and larger quantities of test specimens are
ditions. Consideration should be given to the utility and recommended. Where it is not possible to use specimens of the
practicality of including heat-affected zone (HAZ) material as recommended size, the least deviation possible from recom-
well. mended sizes should be adhered to. Nonstandard specimens
5.1.6 Mechanical properties required for maintaining assur- shall be evaluated by the appropriate regulatory authority prior
ance of component integrity as part of the surveillance program to use as surveillance specimens to ensure that test results from
shall be identified and characterized. Properties may include, the use of nonstandard specimens can be correlated with test
E531 − 23
results from specimens of recommended size. In the event that not necessarily be limited to, materials in the regions of highest
nonstandard specimens are used for surveillance specimens, neutron fluence rate, temperature, and mechanical stress.
the archive, base line, and any thermal control specimens shall
5.4 Tension Test Specimens—The type and size of specimen
be identical to the surveillance specimens. Archive material
to be used should conform to Test Methods E8/E8M and E21.
may be maintained unmachined until testing.
The location and orientation of test specimens shall be as
5.3.2 Surface Condition—Specimens for tests in which
defined in Test Methods E8/E8M or Test Methods and Defini-
surface condition is critical to the test results should not be
tions A370, or in Practice E185. Both base metal and weld
finish machined in such critical areas (for example, compact
metal specimens shall be taken. For each material state, a
tension sample notches, creep-fatigue specimen test area,
minimum set of five specimens shall be included in each
surface of density change sample) until just prior to test.
capsule to be inserted (that is, five for a base metal, five for an
Specimens should be oversized to allow for removal of at least
HAZ, and five for a weld metal). Tests shall be conducted at the
0.1 mm (0.004 in.) of surface prior to test. If significant
operating temperature of the component of interest. If safety
corrosion is expected during operation, specimens should be
criteria require that the degradation of tensile properties of the
oversized on the basis of pre-existing test data, with conserva-
component be known at other temperatures, then additional
tive margin. With the exception of swelling specimens, where
specimens shall be included for this purpose; for example, if
possible, test specimens shall be situated/encapsulated in an
the component is ferritic steel, an additional set of five
environment as similar as achievable to the operating environ-
specimens shall be tested at shutdown temperatures or room
ment of their associated components.
temperature to demonstrate adequate ductility during a reactor
5.3.3 Number of Specimens—The number of specimens
outage/shutdown.
employed to monitor components of similar composition,
5.5 Creep and Stress Rupture in Specimens—The type and
processing, and exposure conditions shall be sufficient to
sizes of specimen to be used should conform to the specimens
evaluate the quantitative changes to the mechanical and chemi-
recommended in Test Method E139 to the extent practical but
cal properties described in 5.2 with a high degree of confi-
shall accommodate passive in-situ testing. Tests shall be
dence. Statistical assessment of specimen plans shall be con-
conducted at the operating temperature of the component of
ducted prior to implementation to ensure statistically
interest. For each material state, a minimum set of five
significant results or control related uncertainty to ensure
specimens shall be included in each capsule to be placed (that
results will be reliable enough to confirm necessary informa-
is, five for a base metal, five for an HAZ, and five for a weld
tion. The statistical methodologies described in Practice E2586
metal).
are recommended for establishing statistical properties of the
test results. The number of required tests may be reduced for
5.6 Creep Fatigue Specimens—The type and sizes of speci-
subsequent and equivalent reactors based on statistical analy-
men to be used should conform to the specimens recommended
sis. Equivalency should be determined by the governing
in Test Method E2714 to the extent practical but shall accom-
regulatory authority. It is recommended that a sufficient amount
modate passive in-situ testing. Tests shall be conducted at the
of material for two further capsules be retained for archive
operating temperature of the component of interest. Note that
purposes. Archive material shall be retained in an atmosphere
consideration should be given to potential thermal stratification
that would not affect the material characteristics of interest.
in relevant components. For each material state, a minimum set
Archive material need not be machined or otherwise finished.
of five specimens shall be included in each capsule to be placed
Reduction in specimen quantities may be justified by use of
(that is, five for a base metal, five for an HAZ, and five for a
large design margins; any such justification shall be docu-
weld metal).
mented with surveillance program design and results.
5.7 Creep Fatigue Crack Growth Specimens—The type and
5.3.4 Material—Test specimens shall be taken from the
the sizes of specimen to be used should conform to the
material used in component fabrication. The influence of
specimens recommended in Test Method E2760. The location
microsegregation on the range of compositions seen in the
and orientation of the specimens shall be as defined in Test
component and test specimens shall be considered when
Methods and Definitions A370. A set of specimens shall be
choosing the locations from which the test specimens are taken
made up of ten of each base metal, HAZ, and weld metal for
to avoid bias between test specimens and component, between
each capsule. Users may justify that one material is limiting
different types of specimens, and between different capsules.
and reduce the quantity necessary of other materials to five
The material shall be processed at the same time as the
specimens of each per capsule. Material representative of the
component or processed in a fashion identical to the compo-
most susceptible region of the HAZ to degradation shall be
nent investigated. Weld and HAZ test specimens shall be taken
selected. Testing shall be conducted at a temperature which
from excess portions of the components or material from the
provides crack growth rates representative of conditions of
same heats of the components and weld filler material utilizing
interest.
the same heat treatments, welding procedures, welding
parameters, and welders/operators. Weldments in the test 5.8 Fracture Toughness Specimens—The specimens should
specimens shall be as close as practicable to the design of the conform to the specimens recommended in Test Method
component weldment. Surveillance specimens should be
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