ASTM E721-22
(Guide)Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
SIGNIFICANCE AND USE
4.1 It is important to know the energy spectrum of the particular neutron source employed in radiation-hardness testing of electronic devices in order to relate radiation effects with device performance degradation.
4.2 This guide describes the factors which must be considered when the spectrum adjustment methodology is chosen and implemented. Although the selection of sensors (foils) and the determination of responses (activities) is discussed in Guide E720, the experiment should not be divorced from the analysis. In fact, it is advantageous for the analyst conducting the spectrum determination to be closely involved with the design of the experiment to ensure that the data obtained will provide the most accurate spectrum possible. These data include the following: (1) measured responses such as the activities of foils exposed in the environment and their uncertainties, (2) response functions such as reaction cross sections along with appropriate correlations and uncertainties, (3) the geometry and materials in the test environment, and (4) a trial function or prior spectrum and its uncertainties obtained from a transport calculation or from previous experience.
SCOPE
1.1 This guide covers procedures for determining the energy-differential fluence spectra of neutrons used in radiation-hardness testing of electronic semiconductor devices. The types of neutron sources specifically covered by this guide are fission or degraded energy fission sources used in either a steady-state or pulse mode.
1.2 This guide provides guidance and criteria that can be applied during the process of choosing the spectrum adjustment methodology that is best suited to the available data and relevant for the environment being investigated.
1.3 This guide is to be used in conjunction with Guide E720 to characterize neutron spectra and is used in conjunction with Practice E722 to characterize damage-related parameters normally associated with radiation-hardness testing of electronic semiconductor devices.
Note 1: Although Guide E720 only discusses activation foil sensors, any energy-dependent neutron-responding sensor for which a response function is known may be used (1).2
Note 2: For terminology used in this guide, see Terminology E170.
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 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: E721 − 22
Standard Guide for
Determining Neutron Energy Spectra from Neutron Sensors
1
for Radiation-Hardness Testing of Electronics
This standard is issued under the fixed designation E721; 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 mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
1.1 This guide covers procedures for determining the
energy-differential fluence spectra of neutrons used in
2. Referenced Documents
radiation-hardness testing of electronic semiconductor devices.
3
2.1 ASTM Standards:
The types of neutron sources specifically covered by this guide
E170 Terminology Relating to Radiation Measurements and
are fission or degraded energy fission sources used in either a
Dosimetry
steady-state or pulse mode.
E261 Practice for Determining Neutron Fluence, Fluence
1.2 This guide provides guidance and criteria that can be
Rate, and Spectra by Radioactivation Techniques
applied during the process of choosing the spectrum adjust-
E262 Test Method for Determining Thermal Neutron Reac-
ment methodology that is best suited to the available data and
tion Rates and Thermal Neutron Fluence Rates by Radio-
relevant for the environment being investigated.
activation Techniques
1.3 This guide is to be used in conjunction with Guide E720
E263 Test Method for Measuring Fast-Neutron Reaction
to characterize neutron spectra and is used in conjunction with
Rates by Radioactivation of Iron
Practice E722 to characterize damage-related parameters nor-
E264 Test Method for Measuring Fast-Neutron Reaction
mally associated with radiation-hardness testing of electronic
Rates by Radioactivation of Nickel
semiconductor devices.
E265 Test Method for Measuring Reaction Rates and Fast-
Neutron Fluences by Radioactivation of Sulfur-32
NOTE 1—Although Guide E720 only discusses activation foil sensors,
any energy-dependent neutron-responding sensor for which a response E266 Test Method for Measuring Fast-Neutron Reaction
2
function is known may be used (1).
Rates by Radioactivation of Aluminum
NOTE 2—For terminology used in this guide, see Terminology E170.
E393 Test Method for Measuring Reaction Rates by Analy-
1.4 The values stated in SI units are to be regarded as
sis of Barium-140 From Fission Dosimeters
standard. No other units of measurement are included in this E523 Test Method for Measuring Fast-Neutron Reaction
standard.
Rates by Radioactivation of Copper
E526 Test Method for Measuring Fast-Neutron Reaction
1.5 This standard does not purport to address all of the
Rates by Radioactivation of Titanium
safety concerns, if any, associated with its use. It is the
E704 Test Method for Measuring Reaction Rates by Radio-
responsibility of the user of this standard to establish appro-
activation of Uranium-238
priate safety, health, and environmental practices and deter-
E705 Test Method for Measuring Reaction Rates by Radio-
mine the applicability of regulatory limitations prior to use.
activation of Neptunium-237
1.6 This international standard was developed in accor-
E720 Guide for Selection and Use of Neutron Sensors for
dance with internationally recognized principles on standard-
Determining Neutron Spectra Employed in Radiation-
ization established in the Decision on Principles for the
Hardness Testing of Electronics
Development of International Standards, Guides and Recom-
E722 PracticeforCharacterizingNeutronFluenceSpectrain
Terms of an Equivalent Monoenergetic Neutron Fluence
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
for Radiation-Hardness Testing of Electronics
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 July 1, 2022. Published July 2022. Originally approved
3
in 1980. Last previous edition approved in 2016 as E721 – 16. DOI: 10.1520/ For referenced ASTM standards, visit the ASTM website, www.astm.org, or
E0721-22. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
The boldface numbers in parentheses refer to the list of references at the end of Standards volume information, refer to the standard’s Document Summary page on
this guide. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700,
...
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: E721 − 16 E721 − 22
Standard Guide for
Determining Neutron Energy Spectra from Neutron Sensors
1
for Radiation-Hardness Testing of Electronics
This standard is issued under the fixed designation E721; 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 procedures for determining the energy-differential fluence spectra of neutrons used in radiation-hardness
testing of electronic semiconductor devices. The types of neutron sources specifically covered by this guide are fission or degraded
energy fission sources used in either a steady-state or pulse mode.
1.2 This guide provides guidance and criteria that can be applied during the process of choosing the spectrum adjustment
methodology that is best suited to the available data and relevant for the environment being investigated.
1.3 This guide is to be used in conjunction with Guide E720 to characterize neutron spectra and is used in conjunction with
Practice E722 to characterize damage-related parameters normally associated with radiation-hardness testing of electronic-
semiconductor electronic semiconductor devices.
NOTE 1—Although Guide E720 only discusses activation foil sensors, any energy-dependent neutron-responding sensor for which a response function is
2
known may be used (1).
NOTE 2—For terminology used in this guide, see Terminology E170.
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 safety, health, and healthenvironmental 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
3
2.1 ASTM Standards:
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, 2016July 1, 2022. Published December 2016July 2022. Originally approved in 1980. Last previous edition approved in 20112016 as
E721 – 11.E721 – 16. DOI: 10.1520/E0721-16.10.1520/E0721-22.
2
The boldface numbers in parentheses refer to the list of references at the end of this guide.
3
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 ----------------------
E721 − 22
E170 Terminology Relating to Radiation Measurements and Dosimetry
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E262 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation
Techniques
E263 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
E264 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
E265 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
E266 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
E523 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
E526 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium
E704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
E705 Test Method for Measuring Reaction Rates by Radioa
...
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