RDHA710SE10A2S
Neutron Test Report
December 2005
International Rectifier currently does not have a DSCC approved Radiation Hardness Assurance Program
for MIL-PRF-38534.
Neutron Test Report
RDHA710SE10A2S
December 2005
Table of Contents
Introduction .………………………………………………. 3
Summary of Results ……………………………………... 3
Test Method .……………………………………………… 3
Test Plan .…………………………………………………. 3
Test Facility .………………………………………………. 5
Test Results ………………………………………………. 6
Conclusion .……………………………………………….. 7
Appendix A – Electrical Data
Appendix B – Radiation Test Specification
Appendix C – Neutron Test Setup
Appendix D – Neutron Exposure Certificates
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Neutron Test Report
RDHA710SE10A2S
December 2005
INTRODUCTION
This test report covers the neutron fluence tests performed on the RDHA710SE10A2S
Solid-State-Relay in a hermetic package. The neutron fluence test was performed to
determine the effects displacement damage had on the device performance. On
December 21, 2005, International Rectifier characterized this device for neutron hardness
at the University of Massachusetts, Nuclear Research Facility using their Fast Neutron
Irradiator.
SUMMARY OF RESULTS
All of the test samples passed the post radiation test requirements for fluence levels up to
2E12 n/cm
2
. The results show degradation in the device’s propagation delay after
exposure to neutron irradiation of 2E12 n/cm
2
.
TEST METHOD
The test method used in the development of the Test Plan was MIL-PRF-883, method
1017 Neutron Irradiation. This method established the basic requirements for the
performance and execution of the tests.
TEST PLAN
The samples were exposed to neutron irradiation in an un-biased state with all of the
device leads shorted in a conductive bag. Post radiation testing of the devices occurred
after the decay of radioactivity of the devices reached an acceptable safe level
determined by the facilities personnel. The rate of decay was dependent on the amount of
exposure to neutrons and the package materials. The devices were contained in a 20 +/-
10C environment to minimize the effects due to annealing. The devices were tested on
December 21, 2005 for post exposure effects.
The Radiation Test Specification is included in Appendix B. The testing occurred in the
following manner:
1.0
Purpose
The purpose of this test is to characterize and establish Neutron effects for International Rectifier’s hybrid
low dropout regulator devices
.
The data resulting from the tests may be incorporated in the IR data sheet for
the product.
2.0
Test Responsibility
International Rectifier shall be responsible for conducting the tests, which shall be performed at the
University of Massachusetts Research Reactor facility. International Rectifier shall be responsible for the
final Test Report.
3.0
Test Facility
3.1 Nuclear Reactor
The University of Massachusetts Research Reactor shall be used to provide the necessary Neutron
beam and energy. University of Massachusetts Research Reactor (UMRR) shall provide adequate
dosimetry for verification of the neutron beam parameters.
205 Crawford St, Leominster, Ma 01453
Tel: 976-534-5776
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Neutron Test Report
RDHA710SE10A2S
December 2005
3.2 Test Equipment
The necessary test equipment including interface board, cables, power supplies, measurement
system, etc. shall be provided by International Rectifier.
3.3 Sample Size
Sample size shall be determined based on device type, characterization parameters. As a
minimum, the sample size shall meet the requirements of Mil-STD-883, method 1017. The sample
size for this test is 10 devices and one device for a control sample.
4.0
Test Device
4.0 The following device is planned for Neutron characterization:
a. RDHA710SE10A2S
4.1 All devices shall be subjected to 160hrs of burn-in and verified for correct electrical performance
prior to arrival at UMRR.
4.2 The device leads will be open during this test and all parts shall be contained inside a
conductive ESD bag during irradiation.
5.0
6.0
Test Method
Neutron Source
MIL-STD-883, Method 1017 shall be used to establish procedure for all testing described herein.
The nuclear reactor at Lowell, Mass is capable of providing fast neutron flux level > 10
11
n/cm
2
– s with
relatively low thermal fluence and gamma irradiation. The Fast Neutron Irradiator (FNI) offers near uniform
spectrum over a large cross-sectional area (12
11
x 12
11
x 6
11
). The dosimetry system used to verify the
radiation exposure was P-32, ASTM E-265.
7.0
Record Keeping
The Reactor facility shall provide dosimetry data for the FNI. IR will be responsible for collecting and
compiling the test data.
8.0
Test Procedure
International Rectifier shall control the following test procedure, based on Test Method 1017. IR’s design
engineering department shall be responsible for selecting the neutron fluence level the product is exposed
to.
The facility personnel shall be responsible for loading and moving the device container.
Exposure levels shall be 1E10 n/cm
2
, 1E11 n/cm
2
, and 1E11 n/cm
2
.
Step
1
2
3
4
5
6
7
8
9
Test Procedure - Table 1
Description
Pre test all devices prior to radiation exposure.
Place all devices in ESD safe bag all device pins are
open
Place devices into the shielded container
Lower the container into the irradiation chamber
Expose the devices to pre-determined level
Remove devices at completion of exposure time
Allow devices to decay to safe level
Test devices after post irradiation
End test. Read and Record data
Conditions
Per T090132G
Unbiased
Facilities personnel
See exposure levels
Facilities personnel
Facilities personnel
Per T090132G
205 Crawford St, Leominster, Ma 01453
Tel: 976-534-5776
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Neutron Test Report
RDHA710SE10A2S
December 2005
9.0
Test Report
The Test Report shall include the following information.
a.
Device type(s), serial numbers, wafer lot identification (per active component)
b.
Test dates
c.
Facility, source type
d.
Fluence
e.
Certificate of Exposure
f.
Bias conditions
g.
Comments and observations
h.
Pre and Post Electrical data
i.
Summary descriptive including graphs
TEST FACILITY
The University of Massachusetts, Lowell, Nuclear Research Reactor is a 1 Mega-Watt,
Uranium
235
enhanced core reactor. The Fast Neutron Irradiation (FNI) chamber (see
Figure 1) is designed to give a fast flux level from 10
10
to 10
16
n/cm
2
-s with relatively low
thermal fluence and gamma dose rates. It is also designed to provide a 1MeV equivalent
flux over the effective range.
LEAD/BORON
SHIELDING
LEAD/ VOID
REACTOR FUEL
IRRADIATION
CHAMBER
FLUX FILTER
Figure 1
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