ASTM E526-17
(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 Test Method 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)3 days(1).4 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 isotopic content of natural titanium recommended for 46Ti is 8.25 %. (2)
5.6 The radioactive products of the neutron reactions 47Ti(n,p)47Sc (τ1/2 = 3.3485 (9) d) (1) and 48Ti(n,p)48Sc (τ1/2 = 43.67 h), (2) 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 (3); 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 Russian Reactor Dosimetry File (RRDF-2002) cross section (4) versus neutron energy for the fast-neutron reactions of titanium which produce 46Sc [that is, NatTi(n,X)46Sc]. This cross section is identical, for energies up to 20 MeV, to what is found in the latest International Atomic Energy Agency (IAEA) International Reactor Dosimetry and Fusion File, IRDFF-1.05 (5). Included in the plot is the 46Ti(n,p) reaction and the 47Ti(n,np) contribution to the 46Sc production, normalized per 46Ti atom using the natural...
SCOPE
1.1 This test method covers procedures for measuring reaction rates by the activation reactions 46Ti(n,p) 46Sc + 47Ti(n, np)46Sc + 47Ti(n,d)46Sc.
Note 1: The cross section for the 47Ti(n,np+d) reaction is relatively small for energies less than 12 MeV and is not easily distinguished from that of the 46Ti(n,p) reaction. This test method will apply to the composite natTi(n,X) 46Sc 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).
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 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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Designation: E526 − 17
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 2. Referenced Documents
2
2.1 ASTM Standards:
1.1 This test method covers procedures for measuring reac-
46 46 47
E170Terminology Relating to Radiation Measurements and
tion rates by the activation reactions Ti(n,p) Sc + Ti(n,
46 47 46
Dosimetry
np) Sc + Ti(n,d) Sc.
E177Practice for Use of the Terms Precision and Bias in
47
NOTE 1—The cross section for the Ti(n,np+d) reaction is relatively
ASTM Test Methods
small for energies less than 12 MeV and is not easily distinguished from
E181Test Methods for Detector Calibration andAnalysis of
46
thatofthe Ti(n,p)reaction.Thistestmethodwillapplytothecomposite
nat 46 Radionuclides
Ti(n,X) Sc reaction that is typically used for dosimetry purposes.
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
E944Guide for Application of Neutron Spectrum Adjust-
1.3 With suitable techniques, fission-neutron fluence rates
9 –2 –1 ment Methods in Reactor Surveillance
above 10 cm ·s can be determined. However, in the pres-
46 E1005Test Method for Application and Analysis of Radio-
ence of a high thermal-neutron fluence rate, Sc depletion
metric Monitors for Reactor Vessel Surveillance
should be investigated.
E1018Guide for Application of ASTM Evaluated Cross
1.4 Detailed procedures for other fast-neutron detectors are Section Data File
referenced in Practice E261.
3. Terminology
1.5 The values stated in SI units are to be regarded as
3.1 Definitions:
standard. No other units of measurement are included in this
standard. 3.1.1 Refer to Terminologies E170 and E456.
1.6 This standard does not purport to address all of the
4. Summary of Test Method
safety concerns, if any, associated with its use. It is the
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
priate safety, health, and environmental practices and deter- thereby producing radioactive Sc from the Ti(n,p) Sc
mine the applicability of regulatory limitations prior to use. activation reaction.
1.7 This international standard was developed in accor-
4.2 The gamma rays emitted by the radioactive decay of
46
dance with internationally recognized principles on standard-
Sc are counted in accordance with Methods E181 and the
ization established in the Decision on Principles for the
reaction rate, as defined by Test Method E261, is calculated
Development of International Standards, Guides and Recom-
from the decay rate and the irradiation conditions.
mendations issued by the World Trade Organization Technical
4.3 The neutron fluence rate above about 4.4 MeVcan then
Barriers to Trade (TBT) Committee.
be calculated from the spectral-weighted neutron activation
cross section as defined by Test Method E261.
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 Aug. 1, 2017. Published October 2017. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approvedin1976.Lastpreviouseditionapprovedin2013asE526–08(2013).DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E0526-17. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E526 − 17
5. Significance and Use File (RRDF-2002) cross section (4) versus neutron energy for
46
the fast-neutron reactions of titanium which produce Sc [that
5.1 Refer to Guide E844 for the selection, irradiation, and
Nat 46
is, Ti(n,X) Sc]. This cross section is identical, for energies
quality control of neutron dosimeters.
up to 20 MeV, to what is found in the latest International
5.2 Refer to Test Method E261 for a general discussion of
Atomic Energy Agency (IAEA) In
...
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: E526 − 08 (Reapproved 2013) E526 − 17
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. 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
46 46 47 46
1.1 This test method covers procedures for measuring reaction rates by the activation reactions Ti(n,p) Sc + Ti(n, np) Sc
47 46
+ Ti(n,d) Sc.
47
NOTE 1—Since the The cross section for the (n,np)Ti(n,np+d) reaction is relatively small for energies less than 12 MeV and is not easily distinguished
46 nat 46
from that of the (n,p) reaction, thisTi(n,p) reaction. This test method will referapply to the (n,p)composite Ti(n,X) reaction only. 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 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
46
a 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 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
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
E262E456 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioacti-
vation TechniquesTerminology 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
3. Terminology
3.1 Definitions:
3.1.1 Refer to TerminologyTerminologies E170 and E456.
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, 2013Aug. 1, 2017. Published January 2013October 2017. Originally approved in 1976. Last previous edition approved in 20082013 as
E526 – 08.E526 – 08(2013). DOI: 10.1520/E0526-08R13.10.1520/E0526-17.
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 ----------------------
E526 − 17
4. Summary of Test Method
46 46 46
4.1 High-purity titanium is irradiated in a fast-neutron field, thereby producing radioactive Sc from the Ti(n,p) Sc
activation reaction.
46
4.2 The gamma rays emitted by the radioactive decay of Sc are counted in accordance with Methods E181 and the reaction
rate, as defined by Test Method E261, is calculated from the decay rate and the irradiation conditions.
4.3 The neu
...
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