Components irradiation test no. 13- 2n2501 transistors, ti 551 diodes and various types of thermistors
Radiation environmental testing of diode, transistor, and thermistor for use in nuclear space vehicle
NUCLEAR RADIATION↗
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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Control specimen data for structural material irradiation test program
Control data on shear and tensile properties of structural alloys for comparison with postirradiation mechanical properties
MECHANICAL PROPERTY↗
Components irradiation test no. 15 - 2N708, 2N918, S2N1486 and S2N2412 transistors and 2N2498 field effect transistor
Neutron and gamma radiation effects on field effect transistor and injection transistors
RADIATION EFFECT↗
NERVA control drum actuator irradiation test program
NERVA control drum actuator tests in cryogenic temperature, nuclear radiation, and vacuum environments
Mayer, J. J.↗
Heavy Ion Irradiation Test Report for the Samsung 850 PRO Series Solid State Drive
The purpose of this test was to determine the heavy ion-induced single-event effect (SEE) susceptibility of the Samsung solid state drive (SSD) containing the Vertical-NAND (VNAND) flash technology. This test was supported by the NASA Electronics Parts and Packaging (NEPP) Program.
Solid State Drive (SSD)↗
Polymer Irradiation Testing for NTP Systems
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Radiation↗
HFIR Irradiation Testing Supporting the Transformational Challenge Reactor
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Le Coq, Annabelle↗
Initial Irradiation Tests on the TCR Fuel Form at MIT Nuclear Reactor Laboratory
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Vasudevamurthy, Gokul↗
Current Status of HFIR Irradiation Testing Supporting the Transformational Challenge Reactor
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Le Coq, Annabelle↗
Irradiation Testing Methods for Fast Spectrum Reactor Fuels and Materials in DOE’s Thermal Spectrum Test Reactors
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Woolstenhulme, Nicolas↗
Irradiation Testing of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor
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Le Coq, Annabelle↗
Irradiation Testing of Fully Ceramic Microencapsulated (FCM) Fuel Compacts in the High Flux Isotope Reactor
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Le Coq, Annabelle↗
Dry Heatsink Capsule and Large Irradiation Test Vehicle Design for TREAT
Review of design features and how fabrication will be completed for DRIFT Capsules, Big-BUSTER, and Moderator Assemblies for Big-BUSTER in TREAT.
42 ENGINEERING↗
Fuels and Materials Irradiation Testing Needs, Recent Progress, and Future Opportunities
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Petrie, Christian↗
Parallel Irradiation Testing to Support Accelerated Down-Selection of Advanced Fuels
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Beausoleil, Geoffrey↗
Standardized Irradiation Testing and Multi-Modal Characterization for Advanced Nuclear Materials
Summary of activities from NMDQi/AMMT to be presented to the annual AMMT program integration meeting
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Post-irradiation Heating Tests of As-Irradiated AGR-3/4 TRISO Fuel Compacts
Four post-irradiation heating tests of fuel compacts from the U.S. Advanced Gas Reactor (AGR)-3/4 irradiation experiment were completed. In addition to tristructural isotropic (TRISO)-coated driver fuel, each compact contained designed-to-fail (DTF) particles with fuel kernels coated only in pyrocarbon so as to simulate exposed kernels. Tests at 1600/1700°C, 1400°C, and 1200°C were performed to measure fission product release as a function of time and temperature. Silver release was highest in the 1200°C test, supporting the observation that silver release rates are highest in the 1100–1300°C range. Compared to tests of AGR-1 compacts with no exposed kernels, the Cs-134 and Kr-85 releases were noticeably higher in AGR-3/4. The exposed kernels’ contributions to Eu and Sr release are inconclusive, due to the difficulty in distinguishing among the combined effects of higher irradiation temperatures in these particular AGR-3/4 compacts, the presence of the DTF particles, and the Fuel Accident Condition Simulator (FACS) test temperatures. These data can be used to make inferences about fission product retention in exposed kernels as a function of time and temperature.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗