ASTM E1253-13

Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens

SIGNIFICANCE AND USE
3.1 Practice E185 defines the minimum requirements for light-water reactor surveillance program Charpy V-notch specimens and Practice E2215 describes the evaluation of test specimens from surveillance capsules. It may be desirable to extend the original surveillance program beyond available specimens for plant aging management issues, such as plant license renewal, to better define existing data, or to determine fracture toughness of a material when no standard fracture toughness test specimens are available. The ability to reconstitute the broken halves of existing specimens can provide such data.  
3.2 Charpy-sized specimens are typically machined from virgin material, that is, material not previously mechanically tested. There are occasions that exist when either (1) no full size specimen blanks are available or (2) the material available with the desired history (such as having been subjected to irradiation) is not sufficient for the machining of full-size specimens, or both.  
3.3 An solution to this problem, which is addressed in this guide, is to fabricate new specimens using the broken halves of previously irradiated and tested specimens or other material irradiated for this purpose. In this guide, the central segment of each new specimen utilizes a broken half of a previously tested specimen and end tabs that are welded to the central segment, or the central section may simply be a piece of virgin material shorter than a Charpy-sized specimen. While specifically addressing reconstitution of irradiated pressure vessel steels, this guide can also provide guidance for reconstitution of Charpy-sized specimens for other situations involving material availability.
SCOPE
1.1 This guide covers procedures for the reconstitution of ferritic pressure vessel steels used in nuclear power plant applications, Type A Charpy (Test Methods E23) specimens and Charpy-sized specimens suitable for testing in three point bending in accordance with Test Methods E1921 or E1820. Materials from irradiation programs (principally broken specimens) are reconstituted by welding end tabs of similar material onto remachined specimen sections that were unaffected by the initial test. Guidelines are given for the selection of suitable specimen halves and end tab materials, for dimensional control, and for avoidance of overheating the notch area. A comprehensive overview of the reconstitution methodologies can be found in Ref  (1).2  
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.3 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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 31-Dec-2012
• ICS: 19.060 - Mechanical testing
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.02 - Behavior and Use of Nuclear Structural Materials

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: E1253 − 13
Standard Guide for
1
Reconstitution of Irradiated Charpy-Sized Specimens
This standard is issued under the fixed designation E1253; 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 E1921 Test Method for Determination of Reference
Temperature, T , for Ferritic Steels in the Transition
o
1.1 This guide covers procedures for the reconstitution of
Range
ferritic pressure vessel steels used in nuclear power plant
E2215 Practice for Evaluation of Surveillance Capsules
applications, Type A Charpy (Test Methods E23) specimens
from Light-Water Moderated Nuclear Power Reactor Ves-
and Charpy-sized specimens suitable for testing in three point
sels
bending in accordance with Test Methods E1921 or E1820.
Materials from irradiation programs (principally broken speci-
3. Significance and Use
mens) are reconstituted by welding end tabs of similar material
3.1 Practice E185 defines the minimum requirements for
onto remachined specimen sections that were unaffected by the
initial test. Guidelines are given for the selection of suitable light-waterreactorsurveillanceprogramCharpyV-notchspeci-
mens and Practice E2215 describes the evaluation of test
specimen halves and end tab materials, for dimensional
control, and for avoidance of overheating the notch area. A specimens from surveillance capsules. It may be desirable to
extend the original surveillance program beyond available
comprehensive overview of the reconstitution methodologies
2
can be found in Ref (1). specimens for plant aging management issues, such as plant
license renewal, to better define existing data, or to determine
1.2 The values stated in SI units are to be regarded as the
fracture toughness of a material when no standard fracture
standard. The values given in parentheses are for information
toughness test specimens are available. The ability to reconsti-
only.
tute the broken halves of existing specimens can provide such
1.3 This standard does not purport to address all of the
data.
safety concerns, if any, associated with its use. It is the
3.2 Charpy-sized specimens are typically machined from
responsibility of the user of this standard to establish appro-
virgin material, that is, material not previously mechanically
priate safety and health practices and determine the applica-
tested. There are occasions that exist when either (1) no full
bility of regulatory limitations prior to use.
size specimen blanks are available or (2) the material available
2. Referenced Documents with the desired history (such as having been subjected to
irradiation) is not sufficient for the machining of full-size
3
2.1 ASTM Standards:
specimens, or both.
E23 Test Methods for Notched Bar Impact Testing of Me-
3.3 An solution to this problem, which is addressed in this
tallic Materials
guide, is to fabricate new specimens using the broken halves of
E185 Practice for Design of Surveillance Programs for
previously irradiated and tested specimens or other material
Light-Water Moderated Nuclear Power Reactor Vessels
irradiated for this purpose. In this guide, the central segment of
E220 Test Method for Calibration of Thermocouples By
each new specimen utilizes a broken half of a previously tested
Comparison Techniques
specimen and end tabs that are welded to the central segment,
E1820 Test Method for Measurement of Fracture Toughness
or the central section may simply be a piece of virgin material
shorter than a Charpy-sized specimen. While specifically
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
addressing reconstitution of irradiated pressure vessel steels,
Technology and Applicationsand is the direct responsibility of Subcommittee
this guide can also provide guidance for reconstitution of
E10.02 on Behavior and Use of Nuclear Structural Materials.
Current edition approved Jan. 1, 2013. Published January 2013. Originally Charpy-sized specimens for other situations involving material
approved in 1993. Last previous edition approved in 2007 as E1253-07. DOI:
availability.
10.1520/E1253-13.
2
The boldface numbers in parentheses refer to the list of references at the end of
4. Reconstitution Technique
this standard.
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
4.1 Welding Process:
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
4.1.1 Anyweldingprocessmaybechosen,providedthatthe
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. heat input and dimensional constraints, as prescribed in this
Copyright © ASTM Internationa
...

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: E1253 − 07 E1253 − 13
Standard Guide for
1
Reconstitution of Irradiated Charpy-Sized Specimens
This standard is issued under the fixed designation E1253; 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 guide covers procedures for the reconstitution of ferritic pressure boundaryvessel steels used in nuclear power plant
applications, Type A Charpy (Test Methods E23) specimens and Charpy-sized specimens suitable for testing in three point bending
in accordance with Test Methods E1921 or E1820. Materials from irradiation programs (principally broken specimens) are
reconstituted by welding end tabs of similar material onto remachined specimen sections that were unaffected by the initial test.
Guidelines are given for the selection of suitable specimen halves and end tab materials, for dimensional control, and for avoidance
2
of overheating the notch area. A comprehensive overview of the reconstitution methodologies can be found in Ref (1).
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.3 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 and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
3
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
E220 Test Method for Calibration of Thermocouples By Comparison Techniques
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
3. Significance and Use
3.1 Practice E185 defines the minimum requirements for light-water reactor surveillance program Charpy V-notch specimens
and Practice E2215 describes the evaluation of test specimens from surveillance capsules. It may be desirable to extend the original
surveillance program beyond available specimens for plant aging management issues, such as plant license renewal, to better define
existing data, or to determine fracture toughness of a material when no standard fracture toughness test specimens are available.
The ability to reconstitute the broken halves of existing specimens can provide such data.
3.2 Charpy-sized specimens are typically machined from virgin material, that is, material not previously mechanically tested.
There are occasions that exist when either (1) no full size specimen blanks are available or (2) the material available with the
desired history (such as having been subjected to irradiation) is not sufficient for the machining of full-size specimens, or both.
3.3 An approachsolution to this problem, which is addressed in this guide, is to fabricate new specimens using the broken halves
of previously irradiated and tested specimens or other material irradiated for this purpose. In this guide, the central segment of each
new specimen utilizes a broken half of a previously tested specimen and end tabs that are welded to the central segment, or the
central section may simply be a piece of virgin material shorter than a Charpy-sized specimen. While specifically addressing
reconstitution of irradiated pressure vessel steel,steels, this guide can also provide guidance for reconstitution of Charpy-sized
specimens for other situations involving material availability.
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.02 on
Behavior and Use of Nuclear Structural Materials.
Current edition approved Feb. 1, 2007Jan. 1, 2013. Published March 2007January 2013. Originally approved in 1993. Last previous edition approved in 19992007 as
E1253-99.-07. DOI: 10.1520/E1253-07.10.1520/E1253-13.
2
The boldface numbers in parentheses refer to the list of references at the end of this standard.
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM
...