ASTM E1854-96
(Practice)Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
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Standards Content (Sample)
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Designation: E 1854 – 96
Standard Practice for
Ensuring Test Consistency in Neutron-Induced
1
Displacement Damage of Electronic Parts
This standard is issued under the fixed designation E 1854; 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.
1. Scope have a vested interest in the performance of electronics in
neutron environments).
1.1 Nuclear reactors are used to provide neutron and
1.3 Methods for evaluation and control of undesired con-
gamma-ray radiation environments for the testing of electronic
tributors to damage are discussed in this practice, and refer-
piece parts, components, and systems. In these applications,
ences to relevant ASTM standards and technical reports are
reactor environments are most commonly used to determine
provided. Processes and methods used to arrive at the appro-
the degradation in performance of the electronics caused by
priate test environments and specification levels for electronics
neutron-induced displacement damage. This practice sets forth
systems are beyond the scope of this practice; however, the
requirements to ensure consistency in neutron-induced dis-
process for determining the 1-MeV equivalent displacement
placement damage testing of silicon and gallium arsenide
specifications from operational environment neutron spectra
electronic piece parts. This requires controls on facility, dosim-
should employ the methods and parameters described herein.
etry, tester, and communications processes that affect the
Some important considerations are addressed in Appendix X1.
accuracy and reproducibility of these tests. It provides back-
1.4 This standard does not purport to address all of the
ground information on the technical basis for the requirements
safety concerns, if any, associated with its use. It is the
and additional recommendations on neutron testing. In addition
responsibility of the user of this standard to establish appro-
to neutrons, reactors are used to provide gamma-ray pulses of
priate safety and health practices and determine the applica-
intensities and durations that are not achievable elsewhere.
bility of regulatory limitations prior to use.
This practice also provides background information and rec-
ommendations on gamma-ray testing of electronics using
2. Referenced Documents
nuclear reactors.
2.1 The ASTM standards listed below present methods for
1.2 Methods are presented for ensuring and validating
ensuring proper determination of neutron spectra and fluences,
consistency in neutron displacement damage testing of elec-
gamma-ray doses, and damage in silicon and gallium arsenide
tronic parts such as integrated circuits, transistors, and diodes.
devices. The proper use of these standards is the responsibility
The issues identified and the controls set forth in this practice
of the radiation metrology or dosimetry organization that is
address the characterization and suitability of the radiation
often closely affiliated with facility operations. The references
environments. They generally apply to reactor and 14-MeV
listed in each standard are also relevant to all participants as
neutron sources when used for displacement damage testing,
252
background material for testing consistency.
and apply to Cf testing when this source is used for this
2.2 ASTM Standards:
application. Facility and environment characteristics that intro-
E 170 Terminology Relating to Radiation Measurements
duce complications or problems are identified, and recommen-
2
and Dosimetry
dations are offered as to how problems can be recognized and
E 181 Test Methods for Detector Calibration and Analysis
minimized or solved. This practice may be used by facility
2
of Radionuclides
users, test personnel, facility operators, and independent pro-
E 261 Practice for Determining Neutron Fluence Rate, Flu-
cess validators to determine the suitability of a specific
2
ence, and Spectra by Radioactivation Techniques
environment within a facility and of the testing process as a
E 262 Test Method for Determining Thermal Neutron Re-
whole, with the exception of the electrical measurements,
2
action and Fluence Rates by Radioactivation Techniques
which are addressed in other standards. Additional information
E 263 Test Method for Measuring Fast-Neutron Reaction
on conducting irradiations can be found in Practices E 798 and
2
Rates by Radioactivation of Iron
F 1190. This practice also may be of use to test sponsors (that
E 264 Test Method for Measuring Fast-Neutron Reaction
is, organizations that establish test specifications or otherwise
2
Rates by Radioactivation of Nickel
E 265 Test M
...
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