ASTM E2215-16

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.

General Information

• Status: Historical
• Publication Date: 30-Nov-2016
• ICS: 27.120.10 - Reactor engineering
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.02 - Behavior and Use of Nuclear Structural Materials

Relations

• Replaces: ASTM E2215-15 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Dec-2016
• Replaced By: ASTM E2215-18 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Aug-2018
• Referred By: ASTM E509/E509M-21 - Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
• Effective Date: 01-Dec-2016
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Dec-2016
• Referred By: ASTM E1214-11(2023) - Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Dec-2016
• Referred By: ASTM E185-21 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Dec-2016
• Referred By: ASTM E636-20 - Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
• Effective Date: 01-Dec-2016
• Referred By: ASTM E1253-21 - Standard Guide for Reconstitution of Charpy-Sized Specimens
• Effective Date: 01-Dec-2016
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 01-Dec-2016
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 01-Dec-2016

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: E2215 − 16
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 E21 TestMethodsforElevatedTemperatureTensionTestsof
Metallic Materials
1.1 This practice covers the evaluation of test specimens
E23 Test Methods for Notched Bar Impact Testing of Me-
and dosimetry from light water moderated nuclear power
tallic Materials
reactor pressure vessel surveillance capsules.
E170 Terminology Relating to Radiation Measurements and
1.2 Additionally, this practice provides guidance on reas-
Dosimetry
sessing withdrawal schedule for design life and operation
E185 Practice for Design of Surveillance Programs for
beyond design life.
Light-Water Moderated Nuclear Power Reactor Vessels
1.3 This practice is one of a series of standard practices that E208 Test Method for Conducting Drop-Weight Test to
Determine Nil-Ductility Transition Temperature of Fer-
outline the surveillance program required for nuclear reactor
pressure vessels. The surveillance program monitors the ritic Steels
E509 Guide for In-Service Annealing of Light-Water Mod-
irradiation-induced changes in the ferritic steels that comprise
the beltline of a light-water moderated nuclear reactor pressure erated Nuclear Reactor Vessels
E636 Guide for Conducting Supplemental Surveillance
vessel.
Tests for Nuclear Power Reactor Vessels, E 706 (IH)
1.4 This practice along with its companion surveillance
E693 Practice for Characterizing Neutron Exposures in Iron
program practice, Practice E185, is intended for application in
and Low Alloy Steels in Terms of Displacements Per
monitoring the properties of beltline materials in any light-
2 Atom (DPA), E 706(ID)
water moderated nuclear reactor.
E844 Guide for Sensor Set Design and Irradiation for
1.5 Modifications to the standard test program and supple-
Reactor Surveillance, E 706 (IIC)
mental tests are described in Guide E636.
E853 Practice forAnalysis and Interpretation of Light-Water
Reactor Surveillance Results
1.6 The values stated in SI units are to be regarded as the
E900 Guide for Predicting Radiation-Induced Transition
standard. The values given in parentheses are for information
Temperature Shift in Reactor Vessel Materials
only.
E1214 Guide for Use of Melt Wire Temperature Monitors
2. Referenced Documents for Reactor Vessel Surveillance, E 706 (IIIE)
3 E1253 Guide for Reconstitution of Irradiated Charpy-Sized
2.1 ASTM Standards:
Specimens
A370 Test Methods and Definitions for Mechanical Testing
E1820 Test Method for Measurement of Fracture Toughness
of Steel Products
E1921 Test Method for Determination of Reference
E8/E8M Test Methods for Tension Testing of Metallic Ma-
Temperature, T , for Ferritic Steels in the Transition
o
terials
Range
4
2.2 ASME Standards:
Boiler and Pressure Vessel Code, Section III Subarticle
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
NB-2000, Rules for Construction of Nuclear Facility
Technology and Applications and is the direct responsibility of Subcommittee
E10.02 on Behavior and Use of Nuclear Structural Materials.
Components, Class 1 Components, Materials
Current edition approved Dec. 1, 2016. Published January 2017. Originally
Boiler and Pressure Vessel Code, Section XI Nonmandatory
approved in 2002. Last previous edition approved in 2015 as E2215–15. DOI:
Appendix A, Analysis of Flaws, and Nonmandatory Ap-
10.1520/E2215-16.
2
Prior to the adoption of these standard practices, surveillance capsule testing pendix G, Fracture Toughness Criteria for Protection
requirements were only contained in Practice E185.
against Failure
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
4
Standards volume information, refer to the standard’s Document Summary page on AvailablefromAmericanSocietyofMechanicalEngineers,ThirdParkAvenue,
the ASTM website. New York, NY 10016.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E2215 − 16
3. Terminology 3.1.11 limiting materials—typically, the weld and base ma-
terial with the highest predicted transition temperature using
3.1 Definitions:
the projected fluence at the end of design life of each material,
3.1.1 base metal—as-fabricated plate material or forging
determined by adding the appropriate transition te
...

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 − 15 E2215 − 16
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.
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, E 706 (IH)
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA),
E 706(ID)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
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, E 706 (IIIE)
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
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 June 1, 2015Dec. 1, 2016. Published July 2015January 2017. Originally approved in 2002. Last previous edition approved in 20102015 as
E2215–10.–15. DOI: 10.1520/E2215-15.10.1520/E2215-16.
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 [e-mail]. 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 − 16
4
2.2 ASME Standards:
Boiler and Pressure Vessel Code, Section III Subarticle NB-2000, Rules for Construction of Nuclear Facility Components, Class
1 Components, Materials
Boiler and Pressure Vessel Code, Section XI Nonmandatory Appendix A, Analysis of Flaws, and Nonmandatory Appendix G,
Fracture Toughness Criteria for Protection against Failure
3. Terminology
3.1 Definitions:
3.1.1 base metal—as-fabricated plate material or forgi
...