ASTM E693-17

Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)

SIGNIFICANCE AND USE
4.1 A pressure vessel surveillance program requires a methodology for relating radiation-induced changes in materials exposed in accelerated surveillance locations to the condition of the pressure vessel (see Practice E853). An important consideration is that the irradiation exposures be expressed in a unit that is physically related to the damage mechanisms.  
4.2 A major source of neutron radiation damage in metals is the displacement of atoms from their normal lattice sites. Hence, an appropriate damage exposure index is the number of times, on the average, that an atom has been displaced during an irradiation. This can be expressed as the total number of displaced atoms per unit volume, per unit mass, or per atom of the material. Displacements per atom is the most common way of expressing this quantity. The number of dpa associated with a particular irradiation depends on the amount of energy deposited in the material by the neutrons, and hence, depends on the neutron spectrum. (For a more extended discussion, see Practice E521.)  
4.3 No simple correspondence exists in general between dpa and a particular change in a material property. A reasonable starting point, however, for relative correlations of property changes produced in different neutron spectra is the dpa value associated with each environment. That is, the dpa values themselves provide a spectrum-sensitive index that may be a useful correlation parameter, or some function of the dpa values may affect correlation.
TABLE 1 ENDF/B-VI-based Iron Displacement Cross Section    
Bin  
EngA (MeV)  
σd  (barns)  
Bin  
EngA (MeV)  
σd  (barns)  
Bin  
EngA (MeV)  
σd  (barns)  
1  
0.100E-09  
158.3543  
2  
0.1050E-09  
154.6209  
3  
0.110E-09  
151.1395  
4  
0.1150E-09  
147.8895  
5  
0.120E-09  
144.1054  
6  
0.1275E-09  
139.9202  
7  
0.1350E-09  
136.0860  
8  
0.1425E-09  
132.5445  
9  
0.150E-09  
128.7502  
10  
0.160E-09  
124.7860  
11  
0.170E...
SCOPE
1.1 This practice describes a standard procedure for characterizing neutron irradiations of iron (and low alloy steels) in terms of the exposure index displacements per atom (dpa) for iron.  
1.2 Although the methods of this practice apply to any material for which a displacement cross section σd(E) is known (see Practice E521), this practice is written specifically for iron.  
1.3 It is assumed that the displacement cross section for iron is an adequate approximation for calculating displacements in steels that are mostly iron (95 to 100 %) in radiation fields for which secondary damage processes are not important.  
1.4 Procedures analogous to this one can be formulated for calculating dpa in charged particle irradiations. (See Practice E521.)  
1.5 The application of this practice requires knowledge of the total neutron fluence and flux spectrum. Refer to Practice E521 for determining these quantities.  
1.6 The correlation of radiation effects data is beyond the scope of this practice.  
1.7 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.  
1.8 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: Historical
• Publication Date: 31-Jul-2017
• ICS: 77.080.20 - Steels
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

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: E693 − 17
Standard Practice for
Characterizing Neutron Exposures in Iron and Low Alloy
1
Steels in Terms of Displacements Per Atom (DPA)
This standard is issued under the fixed designation E693; 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
2.1 ASTM Standards:
1.1 This practice describes a standard procedure for charac-
E170 Terminology Relating to Radiation Measurements and
terizing neutron irradiations of iron (and low alloy steels) in
Dosimetry
terms of the exposure index displacements per atom (dpa) for
E521 Practice for Investigating the Effects of Neutron Ra-
iron.
diation Damage Using Charged-Particle Irradiation
1.2 Although the methods of this practice apply to any
E821 Practice for Measurement of Mechanical Properties
material for which a displacement cross sectionσ (E) is known
During Charged-Particle Irradiation
d
(see Practice E521), this practice is written specifically for iron.
E853 Practice for Analysis and Interpretation of Light-Water
Reactor Surveillance Results
1.3 It is assumed that the displacement cross section for iron
is an adequate approximation for calculating displacements in
3. Terminology
steels that are mostly iron (95 to 100 %) in radiation fields for
3.1 Definitions for terms used in this practice can be found
which secondary damage processes are not important.
in Terminology E170.
1.4 Procedures analogous to this one can be formulated for
4. Significance and Use
calculating dpa in charged particle irradiations. (See Practice
4.1 A pressure vessel surveillance program requires a meth-
E521.)
odology for relating radiation-induced changes in materials
1.5 The application of this practice requires knowledge of
exposed in accelerated surveillance locations to the condition
the total neutron fluence and flux spectrum. Refer to Practice
of the pressure vessel (see Practice E853). An important
E521 for determining these quantities.
consideration is that the irradiation exposures be expressed in
a unit that is physically related to the damage mechanisms.
1.6 The correlation of radiation effects data is beyond the
scope of this practice.
4.2 A major source of neutron radiation damage in metals is
the displacement of atoms from their normal lattice sites.
1.7 This standard does not purport to address all of the
Hence, an appropriate damage exposure index is the number of
safety concerns, if any, associated with its use. It is the
times, on the average, that an atom has been displaced during
responsibility of the user of this standard to establish appro-
an irradiation. This can be expressed as the total number of
priate safety, health, and environmental practices and deter-
displaced atoms per unit volume, per unit mass, or per atom of
mine the applicability of regulatory limitations prior to use.
the material. Displacements per atom is the most common way
1.8 This international standard was developed in accor-
of expressing this quantity. The number of dpa associated with
dance with internationally recognized principles on standard-
a particular irradiation depends on the amount of energy
ization established in the Decision on Principles for the
deposited in the material by the neutrons, and hence, depends
Development of International Standards, Guides and Recom-
on the neutron spectrum. (For a more extended discussion, see
mendations issued by the World Trade Organization Technical
Practice E521.)
Barriers to Trade (TBT) Committee.
4.3 No simple correspondence exists in general between dpa
and a particular change in a material property. A reasonable
starting point, however, for relative correlations of property
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
2
E10.05 on Nuclear Radiation Metrology. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Aug. 1, 2017. Published September 2017. Originally contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
ɛ1
approved in 1979. Last previous edition approved in 2012 as E693 – 12 . DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E0693-17. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E693 − 17
changes produced in different neutron spectra is the dpa value useful correlation parameter, or some function of the dpa
associated with ea
...

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.
´1
Designation: E693 − 12 E693 − 17
Standard Practice for
Characterizing Neutron Exposures in Iron and Low Alloy
1
Steels in Terms of Displacements Per Atom (DPA)
This standard is issued under the fixed designation E693; 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
ε NOTE—The title of this practice was updated editorially in May 2017.
1. Scope
1.1 This practice describes a standard procedure for characterizing neutron irradiations of iron (and low alloy steels) in terms
of the exposure index displacements per atom (dpa) for iron.
1.2 Although the methods of this practice apply to any material for which a displacement cross section σ (E) is known (see
d
Practice E521), this practice is written specifically for iron.
1.3 It is assumed that the displacement cross section for iron is an adequate approximation for calculating displacements in
steels that are mostly iron (95 to 100 %) in radiation fields for which secondary damage processes are not important.
1.4 Procedures analogous to this one can be formulated for calculating dpa in charged particle irradiations. (See Practice E521.)
1.5 The application of this practice requires knowledge of the total neutron fluence and flux spectrum. Refer to Practice E521
for determining these quantities.
1.6 The correlation of radiation effects data is beyond the scope of this practice.
1.7 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 safety, health, and healthenvironmental practices and determine the
applicability of regulatory limitations prior to use.
1.8 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
2
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E521 Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation
E821 Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results
3. Terminology
3.1 Definitions for terms used in this practice can be found in Terminology E170.
4. Significance and Use
4.1 A pressure vessel surveillance program requires a methodology for relating radiation-induced changes in materials exposed
in accelerated surveillance locations to the condition of the pressure vessel (see Practice E853). An important consideration is that
the irradiation exposures be expressed in a unit that is physically related to the damage mechanisms.
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.05 on
Nuclear Radiation Metrology.
Current edition approved June 1, 2012Aug. 1, 2017. Published June 2012September 2017. Originally approved in 1979. Last previous edition approved in 20072012 as
ɛ1
E693 – 01E693 – 12 (2007). DOI: 10.1520/E0693-12E01.10.1520/E0693-17.
2
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 ----------------------
E693 − 17
4.2 A major source of neutron radiation damage in metals is the displacement of atoms from their normal lattice sites. Hence,
an appropriate damage exposure index is the number of times, on the average, that an atom has been displaced during an
irradiation. This can be expressed as the total number of displaced atoms per unit volume, per unit mass, or per atom of the
material. Displacements per atom is the most common way of expressing this quantity. The number of dpa associated with a
particular irradiation depends on the amount of energy deposited in the material by the neutr
...