ASTM E693-01

Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706(ID)

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 general procedures of this practice apply to any material for which a displacement cross section d(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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 09-Jan-2001
• ICS: 77.080.20 - Steels
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E693-94 - Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706(ID)
• Effective Date: 10-Jan-2001
• Replaced By: ASTM E693-01(2007) - Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E 706(ID)
• Effective Date: 01-Jun-2007
• Referred By: ASTM E3084-17(2022)e1 - Standard Practice for Characterizing Particle Irradiations of Materials in Terms of Non-Ionizing Energy Loss (NIEL)
• Effective Date: 10-Jan-2001
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 10-Jan-2001
• Referred By: ASTM E1018-20e1 - Standard Guide for Application of ASTM Evaluated Cross Section Data File
• Effective Date: 10-Jan-2001
• Referred By: ASTM E2215-19 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 10-Jan-2001
• Referred By: ASTM E482-22 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
• Effective Date: 10-Jan-2001
• Referred By: ASTM E944-19 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
• Effective Date: 10-Jan-2001
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 10-Jan-2001
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 10-Jan-2001
• Referred By: ASTM E1035-18(2023) - Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
• Effective Date: 10-Jan-2001
• Referred By: ASTM E722-19 - Standard Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics
• Effective Date: 10-Jan-2001
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 10-Jan-2001
• Referred By: ASTM E261-16(2021) - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 10-Jan-2001

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: E 693 – 01
Standard Practice for
Characterizing Neutron Exposures in Iron and Low Alloy
Steels in Terms of Displacements Per Atom (DPA),
1
E 706(ID)
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.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
1. Scope E821 Practice for Measurement of Mechanical Properties
2
During Charged-Particle Irradiation
1.1 This practice describes a standard procedure for charac-
E853 Practice for Analysis and Interpretation of Light-
terizing neutron irradiations of iron (and low alloy steels) in
2
Water Reactor Surveillance Results, E706 (IA)
terms of the exposure index displacements per atom (dpa) for
iron.
3. Terminology
1.2 Although the general procedures of this practice apply
3.1 Definitions for terms used in this practice can be found
toanymaterialforwhichadisplacementcrosssection s (E)is
d
in Terminology E170.
known(seePracticeE521),thispracticeiswrittenspecifically
for iron.
4. Significance and Use
1.3 Itisassumedthatthedisplacementcrosssectionforiron
4.1 Apressure vessel surveillance program requires a meth-
is an adequate approximation for calculating displacements in
odology for relating radiation-induced changes in materials
steels that are mostly iron (95 to 100%) in radiation fields for
exposed in accelerated surveillance locations to the condition
which secondary damage processes are not important.
of the pressure vessel (see Practices E560 and E853). An
1.4 Procedures analogous to this one can be formulated for
important consideration is that the irradiation exposures be
calculating dpa in charged particle irradiations. (See Practice
expressed in a unit that is physically related to the damage
E521.)
mechanisms.
1.5 The application of this practice requires knowledge of
4.2 Amajorsourceofneutronradiationdamageinmetalsis
the total neutron fluence and flux spectrum. Refer to Practice
the displacement of atoms from their normal lattice sites.
E521 for determining these quantities.
Hence,anappropriatedamageexposureindexisthenumberof
1.6 The correlation of radiation effects data is beyond the
times, on the average, that an atom has been displaced during
scope of this practice.
an irradiation. This can be expressed as the total number of
1.7 This standard does not purport to address all of the
displaced atoms per unit volume, per unit mass, or per atom of
safety concerns, if any, associated with its use. It is the
thematerial.Displacementsperatomisthemostcommonway
responsibility of the user of this standard to establish appro-
ofexpresssingthisquantity.Thenumberofdpaassociatedwith
priate safety and health practices and determine the applica-
a particular irradiation depends on the amount of energy
bility of regulatory limitations prior to use.
deposited in the material by the neutrons, and hence, depends
on the neutron spectrum. (For a more extended discussion, see
2. Referenced Documents
Practice E521.)
2.1 ASTM Standards:
4.3 Nosimplecorrespondenceexistsingeneralbetweendpa
E170 Terminology Relating to Radiation Measurements
2 and a particular change in a material property. A reasonable
and Dosimetry
starting point, however, for relative correlations of property
E521 Practice for Neutron Radiation Damage Simulation
2 changes produced in different neutron spectra is the dpa value
by Charged-Particle Irradiation
associated with each environment. That is, the dpa values
E560 Practice for Extrapolating Reactor Vessel Surveil-
2 themselves provide a spectrum-sensitive index that may be a
lance Dosimetry Results, E706 (IC)
useful correlation parameter, or some function of the dpa
values may affect correlation.
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear 4.4 Since dpa is a construct that depends on a model of the
Technology and Applications and is the direct responsibility of Subcommittee
neutron interaction processes in the material lattice, as well as
E10.05 on Nuclear Radiation Metrology.
the cross section (probability) for each of these processes, the
Current edition approved Jan. 10, 2001. Published June 2001. Originally
value of dpa would be different if improved models or cross
published as E693–79. Last previous edition E693–94.
2
Annual Book of ASTM Standards, Vol 12.02.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

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E 693
sections are used. The calculated dpa cross section for ferritic
where:
iron, as given in this practice, is determined by the procedure
s (E) = the displacement cross
...