ASTM E264-08
(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
Refer to Guide E 844 for the selection, irradiation, and quality control of neutron dosimeters.
Refer to Practice E 261 for a general discussion of the determination of fast-neutron fluence rate with threshold detectors.
Pure nickel in the form of foil or wire is readily available, and easily handled.
58Co has a half-life of 70.86 days and emits a gamma ray with an energy of 0.8107593-MeV.
Competing activities 65Ni(2.5172 h) and 57Ni(35.60 h) are formed by the reactions 64Ni(n,γ) 65Ni, and 58Ni(n,2n)57Ni, respectively.
A second 9.04 h isomer, 58mCo, is formed that decays to 70.86-day 58Co. Loss of 58Co and 58mCo by thermal-neutron burnout will occur in environments , 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.
Fig. 2 shows a plot of cross section 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 E 1018 for descriptions of recommended tabulated dosimetry cross sections.
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 E 1018, section 6.1, since the later ENDF/B-VII data files do not include covariance information. For more details see Section H of reference 8.
FIG. 2 58Ni(n,p)58Co Cross Section
SCOPE
1.1 This test method covers procedures for measuring reaction rates by the activation reaction 58Ni(n,p)58Co.
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 Practice E 261).
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 E 261.
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 and health practices and determine the applicability of regulatory limitations prior to use.
Note—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). FIG. 1 R Correction Values as a Function of Irradiation Time and Neutron Flux
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Designation: E264 − 08
StandardTest 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 Department of Defense.
1. Scope E261Practice for Determining Neutron Fluence, Fluence
Rate, and Spectra by Radioactivation Techniques
1.1 This test method covers procedures for measuring reac-
58 58 E844Guide for Sensor Set Design and Irradiation for
tion rates by the activation reaction Ni(n,p) Co.
Reactor Surveillance, E 706 (IIC)
1.2 Thisactivationreactionisusefulformeasuringneutrons
E944Guide for Application of Neutron Spectrum Adjust-
withenergiesaboveapproximately2.1MeVandforirradiation
ment Methods in Reactor Surveillance, E 706 (IIA)
times up to about 200 days in the absence of high thermal
E1005Test Method for Application and Analysis of Radio-
neutron fluence rates (for longer irradiations, see Practice
metric Monitors for Reactor Vessel Surveillance, E 706
E261).
(IIIA)
E1018Guide for Application of ASTM Evaluated Cross
1.3 With suitable techniques fission-neutron fluence rates
7 −2 −1
densities above 10 cm ·s can be determined. Section Data File, Matrix E706 (IIB)
1.4 Detailed procedures for other fast-neutron detectors are
3. Terminology
referenced in Practice E261.
3.1 Definitions:
1.5 The values stated in SI units are to be regarded as
3.1.1 Refer to Terminology E170.
standard. No other units of measurement are included in this
standard.
4. Summary of Test Method
1.6 This standard does not purport to address all of the
4.1 High-purity nickel is irradiated in a neutron field,
safety concerns, if any, associated with its use. It is the
58 58 58
thereby producing radioactive Co from the Ni(n,p) Co
responsibility of the user of this standard to establish appro-
activation reaction.
priate safety and health practices and determine the applica-
4.2 The gamma rays emitted by the radioactive decay of
bility of regulatory limitations prior to use.
58
Co are counted in accordance with Test Methods E181 and
2. Referenced Documents
the reaction rate, as defined by Practice E261, is calculated
2
from the decay rate and irradiation conditions.
2.1 ASTM Standards:
E170Terminology Relating to Radiation Measurements and
4.3 The neutron fluence rate above about 2.1 MeVcan then
Dosimetry
be calculated from the spectral-weighted neutron activation
E181Test Methods for Detector Calibration andAnalysis of
cross section as defined by Practice E261.
Radionuclides
5. Significance and Use
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
5.1 Refer to Guide E844 for the selection, irradiation, and
Technology and Applicationsand is the direct responsibility of Subcommittee
quality control of neutron dosimeters.
E10.05 on Nuclear Radiation Metrology.
Current edition approved July 1, 2008. Published September 2008. Originally
5.2 Refer to Practice E261 for a general discussion of the
approved in 1965. Last edition approved in 2002 as E264–02. DOI: 10.1520/
determination of fast-neutron fluence rate with threshold de-
E0264-08.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or tectors.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
5.3 Pure nickel in the form of foil or wire is readily
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. available, and easily handled.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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E264 − 08
6. Apparatus
6.1 NaI (T1) or High Resolution Gamma-Ray Spectrometer.
Because of its high resolution, the germanium detector is
useful when contaminant activities are present (seeTest Meth-
ods E181 and E1005).
6.2 Precision Balance, able to achieve the required accu-
racy.
6.3 Digital Computer, useful for data analysis (optional).
7. Materials
7.1 The nickel metal must be low in contained cobalt to
60
NOTE 1—The burnup corrections were computed using effective
prevent the production of Co by thermal-neutron capture.
58
burn-up cross sections of 1650 b for Co(n,γ) and 1.4E5 b for
Nickelproducedbythecarbonyl(Mond)processissufficiently
58m
Co(n,γ).
free of cobalt for even the most adverse conditions. Whenever
FIG. 1R Correction Values as a Function of Irradiation Time and
possible, all nickel should be tested for interfering impurities
Neutron Flux
by neutron activation.
7.2 Encapsulating Materials
...
This document is not anASTM standard and is intended only to provide the user of anASTM 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:E264–02 Designation: E 264 – 08
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 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 Practice E261).
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
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 and health practices and determine the applicability of regulatory
limitations prior to use.
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, Fluence, and Spectra by Radioactivation Techniques
2
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E706 (IIC) E 706(IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
2
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E706 (IIIA) E
706(IIIA)
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
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.
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 Practice E261.
5. Significance and Use
5.1 Refer to Guide E844 for the selection, irradiation, and quality control of neutron dosimeters.
1
This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05
on Nuclear Radiation Metrology.
Current edition approved June 10, 2002. Published September 2002. Originally published as E264–65T. Last edition E264–92(1996).
Current edition approved July 1, 2008. Published September 2008. Originally approved in 1965. Last edition approved in 2002 as E264–02.
2
ForreferencedASTMstandards,visittheASTMwebsite,www.astm.org,orcontactASTMCustomerServiceatservice@astm.org.For Annual Book of ASTM Standards
, Vol 12.02.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 ----------------------
E264–08
NOTE—TheburnupcorrectionValswerecomputedusasaFingeffective
58
burn-up cross sections of I 1650 b forradiati Co(n Time,g) and Neut
58m
1.4E5 b for Co(n Flux,g).
FIG. 1R Correction Values as a Function of Irradiation Time and
Neutron Flux
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.
58
5.4 Co has a half-life of 70.86 days and emits a gamma ray with an energy of 0.8107593-MeV.Co has a half-life of 70.86
3 4
days and emits a gamma ray with an energy of 0.8107593-MeV.
65 57 64 65 58 57
5.5 C
...
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