ASTM E523-21

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper

SIGNIFICANCE AND USE
5.1 Refer to Guide E844 for the selection, irradiation, and quality control of neutron dosimeters.  
5.2 Refer to Practice E261 for a general discussion of the measurement of fast neutron fluence rate with threshold detectors. The general shape of the  63Cu(n,α) 60Co cross section is also shown in Fig. 1 (3, 4, 5) along with a comparison to the current experimental database (6). This figure is for illustrative purposes only to indicate the range of the response of the  63Cu(n,α)60Co reaction. Refer to Guide E1018 for descriptions of recommended tabulated dosimetry cross sections.
FIG. 1 63Cu(n,α)60Co Cross Section with EXFOR Experimental Data  
Note 1: The cross section appropriate for use under this standard is from the IRDFF-II library (5) which, up to an incident neutron energy of 20 MeV, is drawn from the RRDF-2002 library (3) and is identical to the adopted cross section in the IRDF-2002 library (4). See Guide E1018.  
5.3 The major advantages of copper for measuring fast-neutron fluence rate are that it has good strength, is easily fabricated, has excellent corrosion resistance, has a melting temperature of 1083°C, and can be obtained in high purity. The half-life of  60 Co is long and its decay scheme is simple and well known.  
5.4 The disadvantages of copper for measuring fast neutron fluence rate are the high reaction apparent threshold of 4.5 MeV, the possible interference from cobalt impurity (>1 μg/g), the reported possible thermal component of the (n,α) reaction, and the possibly significant cross sections for thermal neutrons for  63Cu and  60Co [that is, 4.50(2) and 2.0(2) barns, respectively], (7), which will require burnout corrections at high fluences.
SCOPE
1.1 This test method covers procedures for measuring reaction rates by the activation reaction  63Cu(n,α) 60Co. The cross section for  60Co produced in this reaction increases rapidly with neutrons having energies greater than about 4.5 MeV. 60Co decays with a half-life of 5.2711(8)2 years (1)3,4 and emits two gamma rays having energies of 1.173228(3) and 1.332492(4) MeV (1). The isotopic content of natural copper is 69.174(20) %  63Cu and 30.826(20) %  65Cu (2). The neutron reaction,  63Cu(n,γ)64Cu, produces a radioactive product that emits gamma rays [1.34577(6) MeV (E1005)] which might interfere with the counting of the  60Co gamma rays.  
1.2 With suitable techniques, fission-neutron fluence rates above 109 cm−2·s−1  can be determined. The  63Cu(n,α)60Co reaction can be used to determine fast-neutron fluences for irradiation times up to about 15 years, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than 15 years, the information inferred about the fluence during irradiation periods more than 15 years before the end of the irradiation should not be relied upon without supporting data from dosimeters withdrawn earlier.  
1.3 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.  
1.4 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.  
1.5 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-Mar-2021
• ICS: 17.240 - Radiation measurements
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• 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: E523 − 21
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Copper
This standard is issued under the fixed designation E523; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
1.1 This test method covers procedures for measuring reac-
63 60 mendations issued by the World Trade Organization Technical
tion rates by the activation reaction Cu(n,α) Co. The cross
60 Barriers to Trade (TBT) Committee.
section for Co produced in this reaction increases rapidly
with neutrons having energies greater than about 4.5 MeV.
2. Referenced Documents
60 2 3,4
Codecayswithahalf-lifeof5.2711(8) years (1) andemits
5
2.1 ASTM Standards:
two gamma rays having energies of 1.173228(3) and
E170Terminology Relating to Radiation Measurements and
1.332492(4)MeV (1).Theisotopiccontentofnaturalcopperis
63 65
Dosimetry
69.174(20)% Cu and 30.826(20) % Cu (2). The neutron
63 64
E181Test Methods for Detector Calibration andAnalysis of
reaction, Cu(n,γ) Cu, produces a radioactive product that
Radionuclides
emits gamma rays [1.34577(6) MeV (E1005)] which might
60
E261Practice for Determining Neutron Fluence, Fluence
interfere with the counting of the Co gamma rays.
Rate, and Spectra by Radioactivation Techniques
1.2 With suitable techniques, fission-neutron fluence rates
E844Guide for Sensor Set Design and Irradiation for
9 −2 −1 63 60
above 10 cm ·s can be determined. The Cu(n,α) Co
Reactor Surveillance
reaction can be used to determine fast-neutron fluences for
E944Guide for Application of Neutron Spectrum Adjust-
irradiation times up to about 15 years, provided that the
ment Methods in Reactor Surveillance
analysis methods described in Practice E261 are followed. If
E1005Test Method for Application and Analysis of Radio-
dosimetersareanalyzedafterirradiationperiodslongerthan15
metric Monitors for Reactor Vessel Surveillance
years, the information inferred about the fluence during irra-
E1018Guide for Application of ASTM Evaluated Cross
diation periods more than 15 years before the end of the
Section Data File
irradiation should not be relied upon without supporting data
from dosimeters withdrawn earlier.
3. Terminology
1.3 Detailed procedures for other fast-neutron detectors are
3.1 Definitions:
referenced in Practice E261.
3.1.1 Refer to Terminology E170.
1.4 This standard does not purport to address all of the
4. Summary of Test Method
safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro-
4.1 High-purity copper (<1 ppm cobalt) is irradiated in a
60
priate safety, health, and environmental practices and deter- neutron field, thereby producing radioactive Co from the
63 60
mine the applicability of regulatory limitations prior to use.
Cu(n,α) Co reaction.
1.5 This international standard was developed in accor-
4.2 The gamma rays emitted by the radioactive decay of
dance with internationally recognized principles on standard- 60
Co are counted in accordance with Test Methods E181 and
the reaction rate, as defined by Practice E261, is calculated
1
This test method is under the jurisdiction ofASTM Committee E10 on Nuclear
from the decay rate and irradiation conditions.
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
4.3 The neutron fluence rate above about 4.5 MeV can then
Current edition approved April 1, 2021. Published April 2021. Originally
be calculated from the spectral-weighted neutron activation
approved in 1976. Last previous edition approved in 2016 as E523–16. DOI:
cross section as defined by Practice E261.
10.1520/E0523-21.
2
The lightface numbers in parentheses are the magnitude of plus or minus
uncertainties in the last digit(s) listed.
3 5
The boldface numbers in parentheses refer to a list of references at the end of For referenced ASTM standards, visit the ASTM website, www.astm.org, or
this standard. contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
4
For dosimetry purposes, a year is defined in accordance with BIPM (1) as 365 Standards volume information, refer to the standard’s Document Summary page on
242 198 days = 31 556 926 s; see Terminology E170. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E523 − 21
5. Significance and Use 7. Materials
5.1 Refer t
...

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: E523 − 16 E523 − 21
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Copper
This standard is issued under the fixed designation E523; 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
63 60
1.1 This test method covers procedures for measuring reaction rates by the activation reaction Cu(n,α) Co. The cross section
60 60
for Co produced in this reaction increases rapidly with neutrons having energies greater than about 4.5 MeV. Co decays with
2 3,4
a half-life of 1925.275.2711(8) days (60.29 days)years (1) and emits two gamma rays having energies of
63
1.17322781.173228(3) and 1.3324921.332492(4) MeV (1). The isotopic content of natural copper is 69.17 %69.174(20) % Cu
65 63 64
and 30.8330.826(20) % Cu (2). The neutron reaction, Cu(n,γ) Cu, produces a radioactive product that emits gamma rays
60
(1.34577[1.34577(6) MeV (E1005)))] which might interfere with the counting of the Co gamma rays.
9 −2 −1 63 60
1.2 With suitable techniques, fission-neutron fluence rates above 10 cm ·s can be determined. The Cu(n,α) Co reaction can
be used to determine fast-neutron fluences for irradiation times up to about 15 years, provided that the analysis methods described
in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than 15 years, the information inferred
about the fluence during irradiation periods more than 15 years before the end of the irradiation should not be relied upon without
supporting data from dosimeters withdrawn earlier.
1.3 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.
1.4 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.
1.5 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
5
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E181 Test Methods for Detector Calibration and Analysis of Radionuclides
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
1
This test method 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 Dec. 1, 2016April 1, 2021. Published January 2017April 2021. Originally approved in 1976. Last previous edition approved in 20112016 as
E523 – 11.E523 – 16. DOI: 10.1520/E0523-16.10.1520/E0523-21.
2
The lightface numbers in parentheses are the magnitude of plus or minus uncertainties in the last digit(s) listed.
3
The boldface numbers in parentheses refer to a list of references at the end of this standard.
4
For dosimetry purposes, a year is defined in accordance with BIPM (1) as 365 242 198 days = 31 556 926 s; see Terminology E170.
5
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 ----------------------
E523 − 21
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
E1018 Guide for Application of ASTM Evaluated Cross Section Data File
3. Terminology
3.1 Definitions:
3.1.1 Refer to Terminology E170.
4. Summary of Test Method
60 63 60
4.1 High-purity copper (<1 ppm cobalt) is irradiated in a neutron field, thereby producing radioactive Co from the Cu(n,α) Co
...