ASTM E2215-18
(Practice)Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
SIGNIFICANCE AND USE
4.1 Neutron radiation effects are considered in the design of light-water moderated nuclear power reactors. Changes in system operating parameters may be made throughout the service life of the reactor to account for these effects. A surveillance program is used to measure changes in the properties of actual vessel materials due to the irradiation environment. This practice describes the criteria that should be considered in evaluating surveillance program test capsules.
4.2 Prior to the first issue date of this standard, the design of surveillance programs and the testing of surveillance capsules were both covered in a single standard, Practice E185. Between its provisional adoption in 1961 and its replacement linked to this standard, Practice E185 was revised many times (1966, 1970, 1973, 1979, 1982, 1993 and 1998). Therefore, capsules from surveillance programs that were designed and implemented under early versions of the standard were often tested after substantial changes to the standard had been adopted. For clarity, the standard practice for surveillance programs has been divided into the new Practice E185 that covers the design of new surveillance programs and this standard practice that covers the testing and evaluation of surveillance capsules. Modifications to the standard test program and supplemental tests are described in Guide E636.
4.3 This practice is intended to cover testing and evaluation of all light-water moderated reactor pressure vessel surveillance capsules. The practice is applicable to testing of capsules from surveillance programs designed and implemented under all previous versions of Practice E185.
4.4 The radiation-induced changes in the properties of the reactor pressure vessel are generally monitored by measuring the index temperatures, the upper-shelf energy and the tensile properties of specimens from the surveillance program capsules. The significance of these radiation-induced changes is described in Practice E185.
4...
SCOPE
1.1 This practice covers the evaluation of test specimens and dosimetry from light water moderated nuclear power reactor pressure vessel surveillance capsules.
1.2 Additionally, this practice provides guidance on reassessing withdrawal schedule for design life and operation beyond design life.
1.3 This practice is one of a series of standard practices that outline the surveillance program required for nuclear reactor pressure vessels. The surveillance program monitors the irradiation-induced changes in the ferritic steels that comprise the beltline of a light-water moderated nuclear reactor pressure vessel.
1.4 This practice along with its companion surveillance program practice, Practice E185, is intended for application in monitoring the properties of beltline materials in any light-water moderated nuclear reactor.2
1.5 Modifications to the standard test program and supplemental tests are described in Guide E636.
1.6 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
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.
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Designation: E2215 − 18
Standard Practice for
Evaluation of Surveillance Capsules from Light-Water
1
Moderated Nuclear Power Reactor Vessels
This standard is issued under the fixed designation E2215; 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
3
2.1 ASTM Standards:
1.1 This practice covers the evaluation of test specimens
A370 Test Methods and Definitions for Mechanical Testing
and dosimetry from light water moderated nuclear power
of Steel Products
reactor pressure vessel surveillance capsules.
E8/E8M Test Methods for Tension Testing of Metallic Ma-
1.2 Additionally, this practice provides guidance on reas-
terials
sessing withdrawal schedule for design life and operation
E21 TestMethodsforElevatedTemperatureTensionTestsof
beyond design life.
Metallic Materials
1.3 This practice is one of a series of standard practices that
E23 Test Methods for Notched Bar Impact Testing of Me-
outline the surveillance program required for nuclear reactor tallic Materials
pressure vessels. The surveillance program monitors the
E170 Terminology Relating to Radiation Measurements and
irradiation-induced changes in the ferritic steels that comprise
Dosimetry
the beltline of a light-water moderated nuclear reactor pressure
E185 Practice for Design of Surveillance Programs for
vessel.
Light-Water Moderated Nuclear Power Reactor Vessels
E208 Test Method for Conducting Drop-Weight Test to
1.4 This practice along with its companion surveillance
Determine Nil-Ductility Transition Temperature of Fer-
program practice, Practice E185, is intended for application in
ritic Steels
monitoring the properties of beltline materials in any light-
2 E509 Guide for In-Service Annealing of Light-Water Mod-
water moderated nuclear reactor.
erated Nuclear Reactor Vessels
1.5 Modifications to the standard test program and supple-
E636 Guide for Conducting Supplemental Surveillance
mental tests are described in Guide E636.
Tests for Nuclear Power Reactor Vessels
E693 Practice for Characterizing Neutron Exposures in Iron
1.6 The values stated in SI units are to be regarded as the
and Low Alloy Steels in Terms of Displacements Per
standard. The values given in parentheses are for information
Atom (DPA)
only.
E844 Guide for Sensor Set Design and Irradiation for
1.7 This international standard was developed in accor-
Reactor Surveillance
dance with internationally recognized principles on standard-
E853 Practice forAnalysis and Interpretation of Light-Water
ization established in the Decision on Principles for the
Reactor Surveillance Results
Development of International Standards, Guides and Recom-
E900 Guide for Predicting Radiation-Induced Transition
mendations issued by the World Trade Organization Technical
Temperature Shift in Reactor Vessel Materials
Barriers to Trade (TBT) Committee.
E1214 Guide for Use of Melt Wire Temperature Monitors
for Reactor Vessel Surveillance
E1253 Guide for Reconstitution of Irradiated Charpy-Sized
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Specimens
Technology and Applications and is the direct responsibility of Subcommittee
E1820 Test Method for Measurement of Fracture Toughness
E10.02 on Behavior and Use of Nuclear Structural Materials.
Current edition approved Aug. 1, 2018. Published August 2018. Originally
3
approved in 2002. Last previous edition approved in 2016 as E2215–16. DOI: For referenced ASTM standards, visit the ASTM website, www.astm.org, or
10.1520/E2215-18. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
Prior to the adoption of these standard practices, surveillance capsule testing Standards volume information, refer to the standard’s Document Summary page on
requirements were only contained in Practice E185. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E2215 − 18
E1921 Test Method for Determination of Reference fusion line in which the microstructure of the base metal has
Temperature, T , for Ferritic Steels in the Transition been altered by the heat of the welding process.
o
Range
3.1.9 index temperature—the temperature corresponding to
4
2.2 ASME Standards:
a predetermined level of absorbed energy, lateral expansion, or
Boiler and Pressure Vessel Code, Section III Subarticle
fracture appearance obtained from the best-fit (average)
NB-2000, Rules for Construction of Nuclear Facility
Charpy transition curve.
Components, Class 1 Components, Materials
3
...
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.
Designation: E2215 − 16 E2215 − 18
Standard Practice for
Evaluation of Surveillance Capsules from Light-Water
1
Moderated Nuclear Power Reactor Vessels
This standard is issued under the fixed designation E2215; 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
1.1 This practice covers the evaluation of test specimens and dosimetry from light water moderated nuclear power reactor
pressure vessel surveillance capsules.
1.2 Additionally, this practice provides guidance on reassessing withdrawal schedule for design life and operation beyond
design life.
1.3 This practice is one of a series of standard practices that outline the surveillance program required for nuclear reactor
pressure vessels. The surveillance program monitors the irradiation-induced changes in the ferritic steels that comprise the beltline
of a light-water moderated nuclear reactor pressure vessel.
1.4 This practice along with its companion surveillance program practice, Practice E185, is intended for application in
2
monitoring the properties of beltline materials in any light-water moderated nuclear reactor.
1.5 Modifications to the standard test program and supplemental tests are described in Guide E636.
1.6 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
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.
2. Referenced Documents
3
2.1 ASTM Standards:
A370 Test Methods and Definitions for Mechanical Testing of Steel Products
E8/E8M Test Methods for Tension Testing of Metallic Materials
E21 Test Methods for Elevated Temperature Tension Tests of Metallic Materials
E23 Test Methods for Notched Bar Impact Testing of Metallic Materials
E170 Terminology Relating to Radiation Measurements and Dosimetry
E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E208 Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels
E509 Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
E636 Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results
E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E1214 Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
E1253 Guide for Reconstitution of Irradiated Charpy-Sized Specimens
E1820 Test Method for Measurement of Fracture Toughness
1
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.
Current edition approved Dec. 1, 2016Aug. 1, 2018. Published January 2017August 2018. Originally approved in 2002. Last previous edition approved in 20152016 as
E2215–15.–16. DOI: 10.1520/E2215-16.10.1520/E2215-18.
2
Prior to the adoption of these standard practices, surveillance capsule testing requirements were only contained in Practice E185.
3
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E2215 − 18
E1921 Test Method for Determination of Reference Temperature, T , for Ferritic Steels in the Transition Range
o
4
2.2 ASME Standards:
Boiler and Pressure Vessel Code, Section III Subarticle NB-2000, Rules for Construction of Nuclear Facility Components, Class
1 Componen
...
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