ASTM E721-01

Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics

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 E 720 to characterize neutron spectra.
Note 1—Although Guide E 720 only discusses activation foil sensors, any energy-dependent neutron-responding sensor for which a response function is known may be used (1).
Note 2—For terminology used in this guide, see Terminology E 170.
1.4 The values stated in SI units are to be regarded as the 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 health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 09-Aug-2001
• ICS: 83.140.10 - Films and sheets
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.07 - Radiation Dosimetry for Radiation Effects on Materials and Devices

Relations

• Replaces: ASTM E721-94 - Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
• Effective Date: 10-Aug-2001
• Replaced By: ASTM E721-07 - Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
• Effective Date: 01-Feb-2007
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 10-Aug-2001
• Referred By: ASTM F1190-18 - Standard Guide for Neutron Irradiation of Unbiased Electronic Components
• Effective Date: 10-Aug-2001
• Referred By: ASTM E720-23 - Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
• Effective Date: 10-Aug-2001
• Referred By: ASTM E265-15(2020) - Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
• Effective Date: 10-Aug-2001
• Referred By: ASTM E1855-20 - Standard Test Method for Use of 2N2222A Silicon Bipolar Transistors as Neutron Spectrum Sensors and Displacement Damage Monitors
• Effective Date: 10-Aug-2001
• Referred By: ASTM E2450-23 - Standard Practice for Application of CaF<inf>2</inf>(Mn) Thermoluminescence Dosimeters in Mixed Neutron-Photon Environments
• Effective Date: 10-Aug-2001
• Referred By: ASTM E722-19 - Standard Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics
• Effective Date: 10-Aug-2001
• Referred By: ASTM F980-16 - Standard Guide for Measurement of Rapid Annealing of Neutron-Induced Displacement Damage in Silicon Semiconductor Devices
• Effective Date: 10-Aug-2001

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:E721–01
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 E 721; 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 (e) 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. Scope E 262 Test Method for Determining Thermal Neutron Re-
3
action and Fluence Rates by Radioactivation Techniques
1.1 This guide covers procedures for determining the
E 263 Test Method for Measuring Fast–Neutron Reaction
energy-differential fluence spectra of neutrons used in
3
Rates by Radioactivation of Iron
radiation-hardness testing of electronic semiconductor devices.
E 264 Test Method for Determining Fast-Neutron Reaction
The types of neutron sources specifically covered by this guide
3
Rates by Radioactivation of Nickel
are fission or degraded energy fission sources used in either a
E 265 Test Method for Measuring Reaction Rates and
steady-state or pulse mode.
3
Fast-Neutron Fluences by Radioactivation of Sulfur-32
1.2 This guide provides guidance and criteria that can be
E 266 Test Method for Determining Fast-Neutron Reaction
applied during the process of choosing the spectrum adjust-
3
Rates by Radioactivation of Aluminum
ment methodology that is best suited to the available data and
E 393 TestMethodforMeasuringReactionRatesbyAnaly-
relevant for the environment being investigated.
3
sis of Barium-140 from Fission Dosimeters
1.3 ThisguideistobeusedinconjunctionwithGuideE 720
E 704 Test Method for Measuring Reaction Rates by Ra-
to characterize neutron spectra.
3
dioactivation of Uranium-238
NOTE 1—Although Guide E 720 only discusses activation foil sensors,
E 705 Test Method for Measuring Reaction Rates by Ra-
any energy-dependent neutron-responding sensor for which a response
3
dioactivation of Neptunium-237
2
function is known may be used (1).
E 720 Guide for Selection and Use of Neutron-Activation
NOTE 2—For terminology used in this guide, see Terminology E 170.
Foils for Determining Neutron Spectra Employed in
1.4 The values stated in SI units are to be regarded as the
3
Radiation-Hardness Testing of Electronics
standard.
E 722 Practice for Characterizing Neutron Energy Fluence
1.5 This standard does not purport to address all of the
Spectra in Terms of an Equivalent Monoenergetic Neutron
safety concerns, if any, associated with its use. It is the
3
Fluence for Radiation-Hardness Testing of Electronics
responsibility of the user of this standard to establish appro-
E 844 Guide for Sensor Set Design and Irradiation for
priate safety and health practices and determine the applica-
3
Reactor Surveillance, E706 (IIC)
bility of regulatory limitations prior to use.
E 944 Guide for Application of Neutron Spectrum Adjust-
3
ment Methods in Reactor Surveillance, (IIA)
2. Referenced Documents
E 1018 Guide for Application of ASTM Evaluated Cross
2.1 ASTM Standards:
Section Data File, Matrix E 706 (IIB)
E 170 Terminology Relating to Radiation Measurements
E 1297 Test Method for Measuring Fast-Neutron Reaction
3
and Dosimetry
3
Rates by Radioactivation of Niobium
E 261 Practice for Determining Neutron Fluence Rate, Flu-
E 1855 Test Method for Use of 2N2222A Silicon Bipolar
3
ence, and Spectra by Radioactivation Techniques
Transistors as Neutron Spectrum Sensors and Displace-
3
ments Damage Monitors
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
3. Terminology
Technology and Applications and is the direct responsibility of Subcommittee
3.1 Definitions: The following list defines some of the
E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices.
Current edition approved August 10, 2001. Published August 2001. Originally
special terms used in this guide:
published as E 721 – 80. Last previous edition E 721 – 93.
3.1.1 effect—the characteristic which changes in the sensor
2
The boldface numbers in parentheses refer to the list of references at the end of
when it is subjected to the neutron irradiation. The effect may
this guide.
3
Annual Book of ASTM Standards, Vol 12.02. be the reactions in an activation foil.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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E721
3.1.2 response—the magnitude of the effect. It can be the values (activities) from effects (reactions) with well-
measured value or that calculated by integrating the response characterized response functions (cross sections) whose re-
function
...