ASTM E266-23
(Test Method)Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
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 aluminum in the form of foil or wire is readily available and easily handled. 27Al has an abundance of 100 % (1).3
5.4 24Na has a half-life of 14.958 (2)4 h (2) and emits gamma rays with energies of 1.368630 (5) and 2.754049 (13) MeV (2).
5.5 Fig. 1 shows a plot of the International Reactor Dosimetry and Fusion File (IRDFF-II) cross section (3, 4) versus neutron energy for the fast-neutron reaction 27Al(n,α) 24Na (3) along with a comparison to the current experimental database (5, 6). While the RRDF-2008 and IRDFF-1.05 cross sections extend from threshold up to 60 MeV, due to considerations of the available validation data, the energy region over which this standard recommends use of this cross section for reactor dosimetry applications only extends from threshold at ~4.25 MeV up to 20 MeV. This figure is for illustrative purposes and is used to indicate the range of response of the 27Al(n,α) reaction. Refer to Guide E1018 for recommended sources for the tabulated dosimetry cross sections.
FIG. 1 27Al(n,α)24Na Cross Section, from IRDFF-II Library, with EXFOR Experimental Data
5.6 Two competing activities, 28Al (2.25 (2) minute half-life) and 27Mg (9.458 (12) minute half-life), are formed in the reactions 27Al(n,γ)28Al and 27Al(n,p)27Mg, respectively, but these can be eliminated by waiting 2 h before counting.
SCOPE
1.1 This test method covers procedures measuring reaction rates by the activation reaction 27Al(n,α)24Na.
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 6.5 MeV and for irradiation times up to about two days (for longer irradiations, or when there are significant variations in reactor power during the irradiation, see Practice E261).
1.3 With suitable techniques, fission-neutron fluence rates above 106 cm−2·s−1 can be determined.
1.4 Detailed procedures for other fast neutron detectors are referenced in Practice E261.
1.5 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.
1.6 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: E266 − 23
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Aluminum
This standard is issued under the fixed designation E266; 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 nuclides in Radiation Metrology for Reactor Dosimetry
E261 Practice for Determining Neutron Fluence, Fluence
1.1 This test method covers procedures measuring reaction
27 24 Rate, and Spectra by Radioactivation Techniques
rates by the activation reaction Al(n,α) Na.
E456 Terminology Relating to Quality and Statistics
1.2 This activation reaction is useful for measuring neutrons
E844 Guide for Sensor Set Design and Irradiation for
with energies above approximately 6.5 MeV and for irradiation
Reactor Surveillance
times up to about two days (for longer irradiations, or when
E944 Guide for Application of Neutron Spectrum Adjust-
there are significant variations in reactor power during the
ment Methods in Reactor Surveillance
irradiation, see Practice E261).
E1005 Test Method for Application and Analysis of Radio-
metric Monitors for Reactor Vessel Surveillance
1.3 With suitable techniques, fission-neutron fluence rates
6 −2 −1
above 10 cm ·s can be determined. E1018 Guide for Application of ASTM Evaluated Cross
Section Data File
1.4 Detailed procedures for other fast neutron detectors are
referenced in Practice E261.
3. Terminology
1.5 This standard does not purport to address all of the
3.1 Definitions:
safety concerns, if any, associated with its use. It is the
3.1.1 Refer to Terminologies E170 and E456.
responsibility of the user of this standard to establish appro-
priate safety, health, and environmental practices and deter-
4. Summary of Test Method
mine the applicability of regulatory limitations prior to use.
4.1 High-purity aluminum is irradiated in a neutron field,
1.6 This international standard was developed in accor-
24 27 24
thereby producing radioactive Na from the Al(n,α) Na
dance with internationally recognized principles on standard-
activation reaction.
ization established in the Decision on Principles for the
4.2 The gamma rays emitted by the radioactive decay of
Development of International Standards, Guides and Recom-
24
Na are counted (see Guide E181) and the reaction rate, as
mendations issued by the World Trade Organization Technical
defined by Practice E261, is calculated from the decay rate and
Barriers to Trade (TBT) Committee.
irradiation conditions.
2. Referenced Documents
4.3 The neutron fluence rate above about 6.5 MeV can then
2
be calculated from the spectral-weighted neutron activation
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and cross section as defined by Practice E261.
Dosimetry
5. Significance and Use
E177 Practice for Use of the Terms Precision and Bias in
ASTM Test Methods 5.1 Refer to Guide E844 for the selection, irradiation, and
E181 Guide for Detector Calibration and Analysis of Radio-
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 de-
1
This test method is under the jurisdiction of ASTM Committee E10 on Nuclear
tectors.
Technology and Applications and is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
5.3 Pure aluminum in the form of foil or wire is readily
Current edition approved June 1, 2023. Published June 2023. Originally
27
available and easily handled. Al has an abundance of 100 %
approved in 1965. Last previous edition approved in 2017 as E266 – 17. DOI:
3
(1).
10.1520/E0266-23.
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
3
Standards volume information, refer to the standard’s Document Summary page on The boldface numbers in parentheses refer to a list of References at the end of
the ASTM website. this standard.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E266 − 23
24 4 24
5.4 Na has a half-life of 14.958 (2) h (2) and emits spectrograph. If the Na content of the irradiated samples is
gamma rays with energies of 1.368630 (5) and 2.754049 (13) determined from the emission rate of the 2.754049 MeV
MeV (2). gamma ray, the probability of interference from contaminant
gamma rays
...
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: E266 − 17 E266 − 23
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Aluminum
This standard is issued under the fixed designation E266; 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
27 24
1.1 This test method covers procedures measuring reaction rates by the activation reaction Al(n,α) Na.
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 6.5 MeV and for irradiation times
up to about 2two days (for longer irradiations, or when there are significant variations in reactor power during the irradiation, see
Practice E261).
6 −2 −1
1.3 With suitable techniques, fission-neutron fluence rates above 10 cm ·s can be determined.
1.4 Detailed procedures for other fast neutron detectors are referenced in Practice E261.
1.5 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.
1.6 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
E177 Practice for Use of the Terms Precision and Bias in ASTM Test Methods
E181 Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E456 Terminology Relating to Quality and Statistics
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
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 Aug. 1, 2017June 1, 2023. Published October 2017June 2023. Originally approved in 1965. Last previous edition approved in 20112017 as
E266 – 11.E266 – 17. DOI: 10.1520/E0266-17.10.1520/E0266-23.
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 ----------------------
E266 − 23
3. Terminology
3.1 Definitions:
3.1.1 Refer to Terminologies E170 and E456.
4. Summary of Test Method
24 27 24
4.1 High-purity aluminum is irradiated in a neutron field, thereby producing radioactive Na from the Al(n,α) Na activation
reaction.
24
4.2 The gamma rays emitted by the radioactive decay of Na are counted (see Test Methods Guide 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 6.5 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 determination of fast-neutron fluence rate with threshold detectors.
27 3
5.3 Pure aluminum in the form of foil or wire is readily available and easily handled. Al has an abundance of 100 % (1)). .
24 4
5.4 Na has a half-life of 14.958 (2) h (2) and emits gamma rays with energies of 1.368630 (5) and 2.754049 (5)(13) MeV (2).
5.5 Fig. 1 shows a plot of the RussianInternational Reactor Dosimetry File (RRDF)and Fusion File
...
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