ASTM E265-07e1
(Test Method)Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
SIGNIFICANCE AND USE
Refer to Guides E 720 and 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 and fluence rate with threshold detectors.
The activation reaction produces 32P, which decays by the emission of a single beta particle in 100 % of the decays, and which emits no gamma rays. The half life of 32P is 14.262 (14) days (1) and the maximum beta energy is 1710 keV(2).
Elemental sulfur is readily available in pure form and any trace contaminants present do not produce significant amounts of radioactivity. Natural sulfur, however, is composed of 32S (95.02 % (9)), 34S (4.21 % (8)) (1), and trace amounts of other sulfur isotopes. The presence of these other isotopes leads to several competing reactions that can interfere with the counting of the 1710-keV beta particle. This interference can usually be eliminated by the use of appropriate techniques, as discussed in Section 8.
SCOPE
1.1 This test method describes procedures for measuring reaction rates and fast-neutron fluences by the activation reaction 32S(n,p)32P.
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 3 MeV.
1.3 With suitable techniques, fission-neutron fluences from about 5 × 108 to 1016 n/cm2 can be measured.
1.4 Detailed procedures for other fast-neutron detectors are described in Practice E 261.
1.5 This standard does not purport to address all of the safety problems, 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.
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´1
Designation: E265 − 07
StandardTest Method for
Measuring Reaction Rates and Fast-Neutron Fluences by
1
Radioactivation of Sulfur-32
This standard is issued under the fixed designation E265; 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
´ NOTE—Ref 3 was editorially updated in April 2009.
1. Scope E720Guide for Selection and Use of Neutron Sensors for
Determining Neutron Spectra Employed in Radiation-
1.1 This test method describes procedures for measuring
Hardness Testing of Electronics
reaction rates and fast-neutron fluences by the activation
32 32 E721Guide for Determining Neutron Energy Spectra from
reaction S(n,p) P.
Neutron Sensors for Radiation-Hardness Testing of Elec-
1.2 Thisactivationreactionisusefulformeasuringneutrons
tronics
with energies above approximately 3 MeV.
E844Guide for Sensor Set Design and Irradiation for
Reactor Surveillance, E 706 (IIC)
1.3 With suitable techniques, fission-neutron fluences from
8 16 2
about 5×10 to 10 n/cm can be measured. E944Guide for Application of Neutron Spectrum Adjust-
ment Methods in Reactor Surveillance, E 706 (IIA)
1.4 Detailed procedures for other fast-neutron detectors are
E1018Guide for Application of ASTM Evaluated Cross
described in Practice E261.
Section Data File, Matrix E706 (IIB)
1.5 This standard does not purport to address all of the
3. Terminology
safety problems, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro-
3.1 Definitions:
priate safety and health practices and determine the applica-
3.1.1 Refer to Terminology E170.
bility of regulatory limitations prior to use.
4. Summary of Test Method
2. Referenced Documents
4.1 Elemental sulfur or a sulfur-bearing compound is irra-
32
2
diatedinaneutronfield,producingradioactive Pbymeansof
2.1 ASTM Standards:
32 32
the S(n,p) P activation reaction.
E170Terminology Relating to Radiation Measurements and
Dosimetry
4.2 The beta particles emitted by the radioactive decay of
32
E181Test Methods for Detector Calibration andAnalysis of
ParecountedbytechniquesdescribedinMethodsE181and
Radionuclides
thereactionrate,asdefinedinPracticeE261,iscalculatedfrom
E261Practice for Determining Neutron Fluence, Fluence
the decay rate and irradiation conditions.
Rate, and Spectra by Radioactivation Techniques
4.3 The neutron fluence above 3 MeV can then be calcu-
lated from the spectral-averaged neutron activation cross
1
section, σ¯, as defined in Practice E261.
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
5. Significance and Use
E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices.
Current edition approved June 1, 2007. Published June 2007. Originally
5.1 Refer to Guides E720 and E844 for the selection,
approved in 1970. Last previous edition approved in 2002 as E265–98(2002).
irradiation, and quality control of neutron dosimeters.
DOI: 10.1520/E0265-07E01.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
5.2 Refer to Practice E261 for a general discussion of the
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
determination of fast-neutron fluence and fluence rate with
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. threshold detectors.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E265 − 07
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5.3 The activation reaction produces P, which decays by practicaltouseapelletmorethanonce.Aperiodofatleastone
the emission of a single beta particle in 100% of the decays, year is recommended between uses. However, see 8.2 regard-
32
and which emits no gamma rays. The half life of P is 14.262 ing long-lived interfering reaction products.
3 4
(14) days (1) andthemaximumbetaenergyis1710keV (2).
7.2 Where temperatures approaching the melting point of
5.4 Elemental sulfur is readily available in pure form and
sulfur are encountered (113°C), sulfur-bearing compounds
any trace contaminants present do not produce significant
such as ammonium sulfate (NH ) SO , lithium sulfate Li SO ,
4 2 4 2 4
amounts of radioactivity. Natural sulfur, however, is composed
or magnesium sulfate MgSO can be used. These are suitable
4
32 34
of S(95.02%(9)), S(4.21%(8)) (1),andtraceamountsof
fortemperaturesupto250,850,and1000°C,respectively.The
othersulfurisotopes.Thepres
...
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.
´1
Designation:E265–98 (Reapproved 2002) Designation:E265–07
Standard Test Method for
Measuring Reaction Rates and Fast-Neutron Fluences by
1
Radioactivation of Sulfur-32
This standard is issued under the fixed designation E265; 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
´ NOTE—Ref 3 was editorially updated in April 2009.
1. Scope
1.1 This test method describes procedures for measuring reaction rates and fast-neutron fluences by the activation reaction
32
32S(n,p) P.
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 3 MeV.
8 16 2
1.3 With suitable techniques, fission-neutron fluences from about 5 310 to 10 n/cm can be measured.
1.4 Detailed procedures for other fast-neutron detectors are described in Practice E261.
1.5 This standard does not purport to address all of the safety problems, 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
2
E261 Practice for Determining Neutron Fluence Rate, Fluence, and Spectra by Radioactivation Techniques Practice for
Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E720 Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness
Testing of Electronics
E721 Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
2
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706(IIB) E 706 (IIB)
3. Terminology
3.1 Definitions:
3.1.1 Refer to Terminology E170.
4. Summary of Test Method
32
4.1 Elemental sulfur or a sulfur-bearing compound is irradiated in a neutron field, producing radioactive P by means of the
32
32S(n,p) P activation reaction.
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4.2 The beta particles emitted by the radioactive decay of Pare counted by techniques described in Methods E181 and the
reaction rate, as defined in Practice E261, is calculated from the decay rate and irradiation conditions.
4.3 The neutron fluence above 3 MeVcan then be calculated from the spectral-averaged neutron activation cross section, s¯,as
defined in Practice E261.
1
This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.07
on Radiation Dosimetry for Radiation Effects on Materials and Devices.
Current edition approved June 10, 1998. Published January 1999. Originally published as E265–70. Last previous edition E265–93.
Current edition approved June 1, 2007. Published June 2007. Originally approved in 1970. Last previous edition approved in 2002 as E265–98(2002).
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 ----------------------
´1
E265–07
5. Significance and Use
5.1Refer to Guide E844
5.1 Refer to Guides E720 and 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 and fluence rate with threshold
detectors.
32
5.3 The activation reaction produces P, which decays by the emission of a single beta particle in 100% of the decays, and
32 3 4
which emits no gamma rays. The half life of P is 14.262 (14) days (1) and the maximum beta energy is 1710 keV (2).
5.4 Elemental sulfur is readily available in pure form and any trace contaminants present do not produce significant amounts
32
...
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