ASTM E264-19
(Test Method)Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
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 determination of fast-neutron fluence rate with threshold detectors.
5.3 Pure nickel in the form of foil or wire is readily available, and easily handled.
5.4 58Co has a half-life of 70.85 (3) days (Refs (1) and (2))3 and emits a gamma ray with an energy of 810.7602 (20) keV (Refs (2) and (3)).
5.5 Competing activities 65Ni(2.5172 h) and 57Ni(35.9 (3) h (Ref (2)) are formed by the reactions 64Ni(n,γ) 65Ni, and 58Ni(n,2n)57Ni, respectively.
5.6 A second 9.04 h isomer, 58mCo, is formed that decays to 70.85-day 58Co. Loss of 58Co and 58mCo by thermal-neutron burnout will occur in environments (Refs (4) and (5) having thermal fluence rates of 3 × 1012 cm−2·s −1 and above. Burnout correction factors, R, are plotted as a function of time for several thermal fluxes in Fig. 1. Tabulated values for a continuous irradiation time are provided in Hogg, et al. (Ref (5))
5.7 Fig. 2 shows a plot of cross section (Ref (6)) versus energy for the fast-neutron reaction 58Ni(n,p) 58Co. This figure is for illustrative purposes only to indicate the range of response of the 58Ni(n,p) reaction. Refer to Guide E1018 for descriptions of recommended tabulated dosimetry cross sections.
FIG. 2 58Ni(n,p)58Co Cross Section
Note 1: The data is taken from the Evaluated Nuclear Data File, ENDF/B-VI, rather than the later ENDF/B-VII. This is in accordance with E1018, section 6.1, since the later ENDF/B-VII data files do not include covariance information. For more details see Section H of Ref (7).
SCOPE
1.1 This test method covers procedures for measuring reaction rates by the activation reaction 58Ni(n,p)58Co.
FIG. 1 R Correction Values as a Function of Irradiation Time and Neutron Flux
Note 1: The burnup corrections were computed using effective burn-up cross sections of 1650 b for 58Co(n,γ) and 1.4E5 b for 58mCo(n,γ).
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.1 MeV and for irradiation times up to about 200 days in the absence of high thermal neutron fluence rates, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than 200 days, the information inferred about the fluence during irradiation periods more than 200 days before the end of the irradiation should not be relied upon without supporting data from dosimeters withdrawn earlier.
1.3 With suitable techniques fission-neutron fluence rates densities above 107 cm−2·s −1 can be determined.
1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.6 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.
1.7 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.
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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.
Designation: E264 − 19
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Nickel
This standard is issued under the fixed designation E264; 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.
This standard has been approved for use by agencies of the U.S. Department of Defense.
1. Scope 2. Referenced Documents
2
2.1 ASTM Standards:
1.1 This test method covers procedures for measuring reac-
58 58
E170Terminology Relating to Radiation Measurements and
tion rates by the activation reaction Ni(n,p) Co.
Dosimetry
1.2 Thisactivationreactionisusefulformeasuringneutrons
E181Test Methods for Detector Calibration andAnalysis of
withenergiesaboveapproximately2.1MeVandforirradiation
Radionuclides
times up to about 200 days in the absence of high thermal
E261Practice for Determining Neutron Fluence, Fluence
neutron fluence rates, provided that the analysis methods
Rate, and Spectra by Radioactivation Techniques
described in Practice E261 are followed. If dosimeters are
E844Guide for Sensor Set Design and Irradiation for
analyzed after irradiation periods longer than 200 days, the
Reactor Surveillance
information inferred about the fluence during irradiation peri-
E944Guide for Application of Neutron Spectrum Adjust-
odsmorethan200daysbeforetheendoftheirradiationshould
ment Methods in Reactor Surveillance
not be relied upon without supporting data from dosimeters
E1005Test Method for Application and Analysis of Radio-
withdrawn earlier.
metric Monitors for Reactor Vessel Surveillance
E1018Guide for Application of ASTM Evaluated Cross
1.3 With suitable techniques fission-neutron fluence rates
7 −2 −1 Section Data File
densities above 10 cm ·s can be determined.
3. Terminology
1.4 Detailed procedures for other fast-neutron detectors are
referenced in Practice E261.
3.1 Definitions:
3.1.1 Refer to Terminology E170.
1.5 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this
4. Summary of Test Method
standard.
4.1 High-purity nickel is irradiated in a neutron field,
58 58 58
1.6 This standard does not purport to address all of the
thereby producing radioactive Co from the Ni(n,p) Co
safety concerns, if any, associated with its use. It is the
activation reaction.
responsibility of the user of this standard to establish appro-
4.2 The gamma rays emitted by the radioactive decay of
priate safety, health, and environmental practices and deter-
58
Co are counted in accordance with Test Methods E181 and
mine the applicability of regulatory limitations prior to use.
the reaction rate, as defined by Practice E261, is calculated
1.7 This international standard was developed in accor-
from the decay rate and irradiation conditions.
dance with internationally recognized principles on standard-
4.3 The neutron fluence rate above about 2.1 MeVcan then
ization established in the Decision on Principles for the
be calculated from the spectral-weighted neutron activation
Development of International Standards, Guides and Recom-
cross section as defined by Practice E261.
mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
5. Significance and Use
5.1 Refer to Guide E844 for the selection, irradiation, and
quality control of neutron dosimeters.
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
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 April 1, 2019. Published May 2019. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1965. Last edition approved in 2013 as E264–08(2013). DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E0264-19. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E264 − 19
NOTE 1—The burnup corrections were computed using effective
58
burn-up cross sections of 1650 b for Co(n,γ) and 1.4E5 b for
58m
Co(n,γ).
FIG. 1R Correction Values as a Function of Irradiation Time and
Neutron Flux
58 58
FIG. 2 Ni(n,p) Co Cross Section
5.2 Refer to Practice E261 for a general discussion of the
determination of fast-neutron fluence rate with threshold de
...
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: E264 − 08 (Reapproved 2013) E264 − 19
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Nickel
This standard is issued under the fixed designation E264; 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.
This standard has been approved for use by agencies of the U.S. Department of Defense.
1. Scope
58 58
1.1 This test method covers procedures for measuring reaction rates by the activation reaction Ni(n,p) Co.
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.1 MeV and for irradiation
times up to about 200 days in the absence of high thermal neutron fluence rates (for longer irradiations, see rates, provided that
the analysis methods described in Practice E261). are followed. If dosimeters are analyzed after irradiation periods longer than 200
days, the information inferred about the fluence during irradiation periods more than 200 days before the end of the irradiation
should not be relied upon without supporting data from dosimeters withdrawn earlier.
7 −2 −1
1.3 With suitable techniques fission-neutron fluence rates densities above 10 cm ·s can be determined.
1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.6 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.
1.7 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
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
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
58 58 58
4.1 High-purity nickel is irradiated in a neutron field, thereby producing radioactive Co from the Ni(n,p) Co activation
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 Jan. 1, 2013April 1, 2019. Published January 2013May 2019. Originally approved in 1965. Last edition approved in 20082013 as
E264 – 08.E264 – 08(2013). DOI: 10.1520/E0264-08R13.10.1520/E0264-19.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. 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 ----------------------
E264 − 19
58 58m
NOTE 1—The burnup corrections were computed using effective burn-up cross sections of 1650 b for Co(n,γ) and 1.4E5 b for Co(n,γ).
FIG. 1 R Correction Values as a Function of Irradiation Time and Neutron Flux
58
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 2.1 MeV can then be calculated from the spectral-weighted neutron activation cross
section as defined by
...
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