ASTM E720-23
(Guide)Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
SIGNIFICANCE AND USE
3.1 Because of the wide variety of materials being used in neutron-activation measurements, this guide is presented with the objective of bringing improved uniformity to the specific field of interest here: hardness testing of electronics primarily in critical assembly reactor environments.
Note 2: Some of the techniques discussed are useful for 14-MeV dosimetry. See Test Method E496 for activation detector materials suitable for 14-MeV neutron effects testing.
Note 3: The materials recommended in this guide are suitable for 252Cf or other weak source effects testing provided the fluence is sufficient to generate countable activities.
3.2 This guide is organized into two overlapping subjects: the criteria used for sensor selection, and the procedures used to ensure the proper determination of activities for determination of neutron spectra. See Terminology E170 and Test Methods E181. Determination of neutron spectra with activation sensor data is discussed in Guides E721 and E944.
SCOPE
1.1 This guide covers the selection and use of neutron-activation detector materials to be employed in neutron spectra adjustment techniques used for radiation-hardness testing of electronic semiconductor devices. Sensors are described that have been used at many radiation hardness-testing facilities, and comments are offered in table footnotes concerning the appropriateness of each reaction as judged by its cross-section accuracy, ease of use as a sensor, and by past successful application. This guide also discusses the fluence-uniformity, neutron self-shielding, and fluence-depression corrections that need to be considered in choosing the sensor thickness, the sensor covers, and the sensor locations. These considerations are relevant for the determination of neutron spectra from assemblies such as TRIGA- and Godiva-type reactors and from Californium irradiators. This guide may also be applicable to other broad energy distribution sources up to 20 MeV.
Note 1: For definitions on terminology used in this guide, see Terminology E170.
1.2 This guide also covers the measurement of the gamma-ray or beta-ray emission rates from the activation foils and other sensors as well as the calculation of the absolute specific activities of these foils. The principal measurement technique is high-resolution gamma-ray spectrometry. The activities are used in the determination of the energy-fluence spectrum of the neutron source. See Guide E721.
1.3 Details of measurement and analysis are covered as follows:
1.3.1 Corrections involved in measuring the sensor activities include those for finite sensor size and thickness in the calibration of the gamma-ray detector, for pulse-height analyzer deadtime and pulse-pileup losses, and for background radioactivity.
1.3.2 The primary method for detector calibration that uses secondary standard gamma-ray emitting sources is considered in this guide and in Test Methods E181. In addition, an alternative method in which the sensors are activated in the known spectrum of a benchmark neutron field is discussed in Guide E1018.
1.3.3 A data analysis method is presented which accounts for the following: detector efficiency; background subtraction; irradiation, waiting, and counting times; fission yields and gamma-ray branching ratios; and self-absorption of gamma rays and neutrons in the sensors.
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
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 Decis...
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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: E720 − 23
Standard Guide for
Selection and Use of Neutron Sensors for Determining
Neutron Spectra Employed in Radiation-Hardness Testing of
1
Electronics
This standard is issued under the fixed designation E720; 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 U.S. Department of Defense.
1. Scope 1.3.2 The primary method for detector calibration that uses
secondary standard gamma-ray emitting sources is considered
1.1 This guide covers the selection and use of neutron-
in this guide and in Test Methods E181. In addition, an
activationdetectormaterialstobeemployedinneutronspectra
alternative method in which the sensors are activated in the
adjustment techniques used for radiation-hardness testing of
known spectrum of a benchmark neutron field is discussed in
electronic semiconductor devices. Sensors are described that
Guide E1018.
have been used at many radiation hardness-testing facilities,
1.3.3 A data analysis method is presented which accounts
and comments are offered in table footnotes concerning the
for the following: detector efficiency; background subtraction;
appropriateness of each reaction as judged by its cross-section
irradiation, waiting, and counting times; fission yields and
accuracy, ease of use as a sensor, and by past successful
gamma-ray branching ratios; and self-absorption of gamma
application. This guide also discusses the fluence-uniformity,
rays and neutrons in the sensors.
neutron self-shielding, and fluence-depression corrections that
need to be considered in choosing the sensor thickness, the 1.4 The values stated in SI units are to be regarded as
sensor covers, and the sensor locations. These considerations standard. No other units of measurement are included in this
are relevant for the determination of neutron spectra from standard.
assembliessuchasTRIGA-andGodiva-typereactorsandfrom
1.5 This standard does not purport to address all of the
Californium irradiators. This guide may also be applicable to
safety concerns, if any, associated with its use. It is the
other broad energy distribution sources up to 20 MeV.
responsibility of the user of this standard to establish appro-
priate safety, health, and environmental practices and deter-
NOTE 1—For definitions on terminology used in this guide, see
Terminology E170. mine the applicability of regulatory limitations prior to use.
1.6 This international standard was developed in accor-
1.2 This guide also covers the measurement of the gamma-
dance with internationally recognized principles on standard-
ray or beta-ray emission rates from the activation foils and
ization established in the Decision on Principles for the
other sensors as well as the calculation of the absolute specific
Development of International Standards, Guides and Recom-
activities of these foils. The principal measurement technique
mendations issued by the World Trade Organization Technical
is high-resolution gamma-ray spectrometry. The activities are
Barriers to Trade (TBT) Committee.
usedinthedeterminationoftheenergy-fluencespectrumofthe
neutron source. See Guide E721.
2. Referenced Documents
1.3 Details of measurement and analysis are covered as
2.1 General considerations of neutron-activation detectors
follows:
discussed in Practice E261, Test Method E262, and Guides
1.3.1 Corrections involved in measuring the sensor activi-
E721 and E844 are applicable to this guide. Background
ties include those for finite sensor size and thickness in the
informationforapplyingthisguidearegivenintheseandother
calibration of the gamma-ray detector, for pulse-height ana-
relevant standards as follows:
lyzer deadtime and pulse-pileup losses, and for background
2
2.2 ASTM Standards:
radioactivity.
E170Terminology Relating to Radiation Measurements and
Dosimetry
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applications and is the direct responsibility of Subcommittee
2
E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Jan. 1, 2023. Published February 2023. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1980. Last previous edition approved in 2016 as E720–16. DOI: Standards volume information, refer to the standard’s Document Summary page on
1
...
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: E720 − 16 E720 − 23
Standard Guide for
Selection and Use of Neutron Sensors for Determining
Neutron Spectra Employed in Radiation-Hardness Testing of
1
Electronics
This standard is issued under the fixed designation E720; 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.
This standard has been approved for use by agencies of the U.S. Department of Defense.
1. Scope
1.1 This guide covers the selection and use of neutron-activation detector materials to be employed in neutron spectra adjustment
techniques used for radiation-hardness testing of electronic semiconductor devices. Sensors are described that have been used at
many radiation hardness-testing facilities, and comments are offered in table footnotes concerning the appropriateness of each
reaction as judged by its cross-section accuracy, ease of use as a sensor, and by past successful application. This guide also
discusses the fluence-uniformity, neutron self-shielding, and fluence-depression corrections that need to be considered in choosing
the sensor thickness, the sensor covers, and the sensor locations. These considerations are relevant for the determination of neutron
spectra from assemblies such as TRIGA- and Godiva-type reactors and from Californium irradiators. This guide may also be
applicable to other broad energy distribution sources up to 20 MeV.
NOTE 1—For definitions on terminology used in this guide, see Terminology E170.
1.2 This guide also covers the measurement of the gamma-ray or beta-ray emission rates from the activation foils and other sensors
as well as the calculation of the absolute specific activities of these foils. The principal measurement technique is high-resolution
gamma-ray spectrometry. The activities are used in the determination of the energy-fluence spectrum of the neutron source. See
Guide E721.
1.3 Details of measurement and analysis are covered as follows:
1.3.1 Corrections involved in measuring the sensor activities include those for finite sensor size and thickness in the calibration
of the gamma-ray detector, for pulse-height analyzer deadtime and pulse-pileup losses, and for background radioactivity.
1.3.2 The primary method for detector calibration that uses secondary standard gamma-ray emitting sources is considered in this
guide and in Test Methods E181. In addition, an alternative method in which the sensors are activated in the known spectrum of
a benchmark neutron field is discussed in Guide E1018.
1.3.3 A data analysis method is presented which accounts for the following: detector efficiency; background subtraction;
irradiation, waiting, and counting times; fission yields and gamma-ray branching ratios; and self-absorption of gamma rays and
neutrons in the sensors.
1
This guide 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 Dec. 1, 2016Jan. 1, 2023. Published February 2017February 2023. Originally approved in 1980. Last previous edition approved in 20112016
as E720 – 11.E720 – 16. DOI: 10.1520/E0720-16.10.1520/E0720-23.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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E720 − 23
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
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 and healthsafety, 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
2.1 General considerations of neutron-activation detectors discussed in Practice E261, Test Method E262, and Guides E721 and
E844 are applica
...
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