ASTM E526-22
(Test Method)Standard Test Method for Measuring Fast-Neutron Reaction Rates By Radioactivation of Titanium
Standard Test Method for Measuring Fast-Neutron Reaction Rates By Radioactivation of Titanium
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 Titanium has good physical strength, is easily fabricated, has excellent corrosion resistance, has a melting temperature of 1668 °C, and can be obtained with satisfactory purity.
5.4 46Sc has a half-life of 83.787 (16)4 days (2). The 46Sc decay emits a 0.889271 (2) MeV gamma 99.98374 (35) % of the time and a second gamma with an energy of 1.120537 (3) MeV 99.97 (2) % of the time.
5.5 The recommended “representative isotopic abundances” for natural titanium (3) are:
8.25 (3) % 46Ti
7.44 (2) % 47Ti
73.72 (2) % 48Ti
5.41 (2) % 49Ti
5.18 (2) % 50Ti
5.6 The radioactive products of the neutron reactions 47Ti(n,p)47Sc (τ1/2 = 3.3485 (9) d) (2) and 48Ti(n,p)48Sc (τ1/2 = 43.67 h), (3) might interfere with the analysis of 46Sc.
5.7 Contaminant activities (for example, 65Zn and 182Ta) might interfere with the analysis of 46Sc. See 7.1.2 and 7.1.3 for more details on the 182Ta and 65Zn interference.
5.8 46Ti and 46Sc have cross sections for thermal neutrons of 0.59 ± 0.18 and 8.0 ± 1.0 barns, respectively (4); therefore, when an irradiation exceeds a thermal-neutron fluence greater than about 2 × 1021 cm–2, provisions should be made to either use a thermal-neutron shield to prevent burn-up of 46Sc or measure the thermal-neutron fluence rate and calculate the burn-up.
5.9 Fig. 1 shows a plot of the International Reactor Dosimetry and Fusion File, IRDFF-II cross section (5) versus neutron energy for the fast-neutron reactions of titanium which produce 46Sc (that is, natTi(n,X)46Sc). Included in the plot is the 46Ti(n,p) reaction and the 47Ti(n,np:d) contributions to the 46Sc production, normalized per natTi atom with the individual isotopic contributions weighted using the natural abundances (3). This figure ...
SCOPE
1.1 This test method covers procedures for measuring reaction rates by the activation reaction natTi(n,X)46Sc. The “X” designation represents any combination of light particles associated with the production of the residual 46Sc product. Within the applicable neutron energy range for fission reactor applications, this reaction is a properly normalized combination of three different reaction channels: 46Ti(n,p)46Sc; 47Ti(n, np)46Sc; and 47Ti(n,d)46Sc.
Note 1: The 47Ti(n,np)46Sc reaction, ENDF-6 format file/reaction identifier MF=3, MT=28, is distinguished from the 47Ti(n,d)46Sc reaction, ENDF-6 format file/reaction identifier MF=3/MT=104, even though it leads to the same residual product (1).2 The combined reaction, in the IRDFF-II library, has the file/reaction identifier MF=10/MT=5.
Note 2: The cross section for the combined 47Ti(n,np:d) reaction is relatively small for energies less than 12 MeV and, in fission reactor spectra, the production of the residual 46Sc is not easily distinguished from that due to the 46Ti(n,p) reaction.
1.2 The reaction is useful for measuring neutrons with energies above approximately 4.4 MeV and for irradiation times, under uniform power, up to about 250 days (for longer irradiations, or for varying power levels, see Practice E261).
1.3 With suitable techniques, fission-neutron fluence rates above 109 cm–2·s–1 can be determined. However, in the presence of a high thermal-neutron fluence rate, 46Sc depletion should be investigated.
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 an...
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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: E526 − 22
Standard Test Method for
Measuring Fast-Neutron Reaction Rates By Radioactivation
1
of Titanium
This standard is issued under the fixed designation E526; 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 priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
1.1 This test method covers procedures for measuring reac-
nat 46 1.7 This international standard was developed in accor-
tion rates by the activation reaction Ti(n,X) Sc. The “X”
dance with internationally recognized principles on standard-
designation represents any combination of light particles asso-
46 ization established in the Decision on Principles for the
ciated with the production of the residual Sc product.Within
Development of International Standards, Guides and Recom-
the applicable neutron energy range for fission reactor
mendations issued by the World Trade Organization Technical
applications, this reaction is a properly normalized combina-
46 46 47 Barriers to Trade (TBT) Committee.
tion of three different reaction channels: Ti(n,p) Sc; Ti(n,
46 47 46
np) Sc; and Ti(n,d) Sc.
2. Referenced Documents
47 46
NOTE 1—The Ti(n,np) Sc reaction, ENDF-6 format file/reaction
3
2.1 ASTM Standards:
47 46
identifierMF=3,MT=28,isdistinguishedfromthe Ti(n,d) Screaction,
E170Terminology Relating to Radiation Measurements and
ENDF-6 format file/reaction identifier MF=3/MT=104, even though it
2
Dosimetry
leads to the same residual product (1). The combined reaction, in the
IRDFF-II library, has the file/reaction identifier MF=10/MT=5.
E177Practice for Use of the Terms Precision and Bias in
47
NOTE 2—The cross section for the combined Ti(n,np:d) reaction is
ASTM Test Methods
relatively small for energies less than 12 MeV and, in fission reactor
46 E181Test Methods for Detector Calibration andAnalysis of
spectra,theproductionoftheresidual Scisnoteasilydistinguishedfrom
46
Radionuclides
that due to the Ti(n,p) reaction.
E261Practice for Determining Neutron Fluence, Fluence
1.2 The reaction is useful for measuring neutrons with
Rate, and Spectra by Radioactivation Techniques
energies above approximately 4.4 MeV and for irradiation
E456Terminology Relating to Quality and Statistics
times, under uniform power, up to about 250 days (for longer
E844Guide for Sensor Set Design and Irradiation for
irradiations, or for varying power levels, see Practice E261).
Reactor Surveillance
1.3 With suitable techniques, fission-neutron fluence rates
E944Guide for Application of Neutron Spectrum Adjust-
9 –2 –1
above 10 cm ·s can be determined. However, in the
ment Methods in Reactor Surveillance
46
presence of a high thermal-neutron fluence rate, Sc depletion
E1005Test Method for Application and Analysis of Radio-
should be investigated.
metric Monitors for Reactor Vessel Surveillance
E1018Guide for Application of ASTM Evaluated Cross
1.4 Detailed procedures for other fast-neutron detectors are
Section Data File
referenced in Practice E261.
1.5 The values stated in SI units are to be regarded as
3. Terminology
standard. No other units of measurement are included in this
3.1 Definitions:
standard.
3.1.1 Refer to Terminologies E170 and E456.
1.6 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
4. Summary of Test Method
responsibility of the user of this standard to establish appro-
4.1 High-purity titanium is irradiated in a fast-neutron field,
46 46 46
thereby producing radioactive Sc from the Ti(n,p) Sc
1
47 46
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
reaction as well as the Ti(n,np:d) Sc activation reactions.
Technology and Applications and is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
Current edition approved July 1, 2022. Published August 2022. Originally
3
approved in 1976. Last previous edition approved in 2017 as E526–17. DOI: For referenced ASTM standards, visit the ASTM website, www.astm.org, or
10.1520/E0526-22. contact ASTM Customer Service at service@astm.org. 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
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...
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.
´1
Designation: E526 − 17 E526 − 22
Standard Test Method for
Measuring Fast-Neutron Reaction Rates byBy
1
Radioactivation of Titanium
This standard is issued under the fixed designation E526; 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
ε NOTE—Editorial changes, such as removing extra spacing, correcting notation and a variable, were made in November
2017.
1. Scope
nat 46
1.1 This test method covers procedures for measuring reaction rates by the activation reactionsreaction Ti(n,X) Ti(n,p)Sc. The
46
“X” designation represents any combination of light particles associated with the production of the residual Sc + product. Within
the applicable neutron energy range for fission reactor applications, this reaction is a properly normalized combination of three
46 46 47 46 47 46
different reaction channels: Ti(n,p) Sc; Ti(n, np) Sc +Sc; and Ti(n,d) Sc.
47 46 47 46
NOTE 1—The Ti(n,np) Sc reaction, ENDF-6 format file/reaction identifier MF=3, MT=28, is distinguished from the Ti(n,d) Sc reaction, ENDF-6
2
format file/reaction identifier MF=3/MT=104, even though it leads to the same residual product (1). The combined reaction, in the IRDFF-II library, has
the file/reaction identifier MF=10/MT=5.
47
NOTE 2—The cross section for the combined Ti(n,np+d)Ti(n,np:d) reaction is relatively small for energies less than 12 MeV and and, in fission reactor
46 46
spectra, the production of the residual Sc is not easily distinguished from that of due to the Ti(n,p) reaction. This test method will apply to the
nat 46
composite Ti(n,X) Sc reaction that is typically used for dosimetry purposes.
1.2 The reaction is useful for measuring neutrons with energies above approximately 4.4 MeV and for irradiation times, under
uniform power, up to about 250 days (for longer irradiations, or for varying power levels, see Practice E261).
9 –2 –1
1.3 With suitable techniques, fission-neutron fluence rates above 10 cm ·s can be determined. However, in the presence of a
46
high thermal-neutron fluence rate, Sc depletion should be investigated.
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.
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, 2017July 1, 2022. Published October 2017August 2022. Originally approved in 1976. Last previous edition approved in 20132017 as
E526 – 08E526 – 17.(2013). DOI: 10.1520/E0526-17E01.10.1520/E0526-22.
2
The boldface numbers in parentheses refer to a list of references at the end of this standard.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E526 − 22
2. Referenced Documents
3
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 Test Methods for Detector Calibration and Analysis of Radionuclides
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 Eval
...
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