ASTM E523-16

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) along with a comparison to the current experimental database (5). 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.  
Note 1: The cross section appropriate for use under this standard is ENDF/B-VI release 8 library since it contains a covariance matrix. The ENDF/B-VII library has been released, but it does not contain a covariance matrix for this reaction. For dosimetry applications, an uncertainty metric expressed as a covariance matrix is required. 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 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 and 2.0 barns, respectively),(6) 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 1925.27 days (±0.29 days)(1)2 and emits two gamma rays having energies of 1.1732278 and 1.332492 MeV(1). The isotopic content of natural copper is 69.17 %  63Cu and 30.83 %  65Cu(2). The neutron reaction,  63Cu(n,γ)64Cu, produces a radioactive product that emits gamma rays (1.34577 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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 30-Nov-2016
• 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)

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Contact ASTM International (www.astm.org) for the latest information
Designation: E523 − 16
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 2. Referenced Documents
3
1.1 This test method covers procedures for measuring reac- 2.1 ASTM Standards:
63 60
tion rates by the activation reaction Cu(n,α) Co. The cross E170Terminology Relating to Radiation Measurements and
60
section for Co produced in this reaction increases rapidly Dosimetry
with neutrons having energies greater than about 4.5 MeV. E181Test Methods for Detector Calibration andAnalysis of
60 2
Co decays with a half-life of 1925.27 days (60.29 days)(1) Radionuclides
and emits two gamma rays having energies of 1.1732278 and E261Practice for Determining Neutron Fluence, Fluence
1.332492 MeV(1). The isotopic content of natural copper is Rate, and Spectra by Radioactivation Techniques
63 65
69.17% Cu and 30.83 % Cu(2). The neutron reaction, E844Guide for Sensor Set Design and Irradiation for
63 64
Cu(n,γ) Cu, produces a radioactive product that emits Reactor Surveillance, E 706 (IIC)
gamma rays (1.34577 MeV (E1005)) which might interfere E944Guide for Application of Neutron Spectrum Adjust-
60
with the counting of the Co gamma rays. ment Methods in Reactor Surveillance, E 706 (IIA)
E1005Test Method for Application and Analysis of Radio-
1.2 With suitable techniques, fission-neutron fluence rates
9 −2 −1 63 60 metric Monitors for Reactor Vessel Surveillance
above 10 cm ·s can be determined. The Cu(n,α) Co
E1018Guide for Application of ASTM Evaluated Cross
reaction can be used to determine fast-neutron fluences for
Section Data File, Matrix E706 (IIB)
irradiation times up to about 15 years, provided that the
analysis methods described in Practice E261 are followed. If
3. Terminology
dosimetersareanalyzedafterirradiationperiodslongerthan15
3.1 Definitions:
years, the information inferred about the fluence during irra-
3.1.1 Refer to Terminology E170.
diation periods more than 15 years before the end of the
irradiation should not be relied upon without supporting data
4. Summary of Test Method
from dosimeters withdrawn earlier.
4.1 High-purity copper (<1 ppm cobalt) is irradiated in a
1.3 Detailed procedures for other fast-neutron detectors are
60
neutron field, thereby producing radioactive Co from the
referenced in Practice E261.
63 60
Cu(n,α) Co reaction.
1.4 This standard does not purport to address all of the
4.2 The gamma rays emitted by the radioactive decay of
safety concerns, if any, associated with its use. It is the
60
Co are counted in accordance with Test Methods E181 and
responsibility of the user of this standard to establish appro-
the reaction rate, as defined by Practice E261, is calculated
priate safety and health practices and determine the applica-
from the decay rate and irradiation conditions.
bility of regulatory limitations prior to use.
4.3 The neutron fluence rate above about 4.5 MeVcan then
be calculated from the spectral-weighted neutron activation
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
cross section as defined by Practice E261.
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
Current edition approved Dec. 1, 2016. Published January 2017. Originally
3
approved in 1976. Last previous edition approved in 2011 as E523–11. DOI: For referenced ASTM standards, visit the ASTM website, www.astm.org, or
10.1520/E0523-16. contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
2
The boldface numbers in parentheses refer to a list of references at the end of Standards volume information, refer to the standard’s Document Summary page on
this standard. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E523 − 16
5. Significance and Use 7. Materials
5.1 Refer to Guide E844 for the selection, irradiation, and 7.1 Copper Metal—Purecoppermetalintheformofwireor
quality control of neutron dosimeters. foil is available.
7.1.1 Themetalshouldbetestedforimpuritiesbyaneutron
5.2 Refer to Practice E261 for a general discussion of the
activation technique. If the measurement is to be made in a
measurement of fast neutron fluence rate with threshold
63 60
thermal-neutronenvironment,theremustbenocobaltimpurity
detectors.Thegeneralshapeofthe Cu(n,α) Cocrosssection
59 60
(<1 µg/g) because the reaction Co(n,γ) Co produces th
...

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 − 11 E523 − 16
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 54.5 MeV. Co decays with
2
a half-life of 1925.27 days (60.29 days)(1) and emits two gamma rays having energies of 1.1732278 and 1.332492 MeV(1). The
63 65
isotopic content of natural copper is 69.17 % Cu and 30.83 % Cu(2). The neutron reaction,
63 64
Cu(n,γ) Cu, produces a radioactive product that emits gamma rays (1.34577 MeV (E1005)) which might interfere with the
counting of the
60
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 (for longer irradiations, see 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 and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
3
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
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
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, Matrix E706 (IIB)
3. Terminology
3.1 Definitions:
3.1.1 Refer to Terminology E170.
4. Summary of Test Method
60
4.1 High-purity copper (<1 ppm cobalt) is irradiated in a neutron field, thereby producing radioactive Co from the
63 60
Cu(n,α) Co reaction.
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 June 1, 2011Dec. 1, 2016. Published July 2011January 2017. Originally approved in 1976. Last previous edition approved in 20072011 as
E523 – 07.E523 – 11. DOI: 10.1520/E0523-11.10.1520/E0523-16.
2
The boldface numbers in parentheses refer to a list of references at the end of this standard.
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 ----------------------
E523 − 16
60
4.2 The gamma rays emitted by the radioactive decay of Co are counted in accordance with Test Methods E181 and the
reaction rate, as defined by Practice E261, is calculated from the decay rate and irradiation conditions.
4.3 The neutron fluence rate above about 54.5 MeV can then be calculated from the spectral-weighted neutron activation cross
section as defined by Practice E261.
5. 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
...