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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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Heat treating various compositions of zirconium alloys improve their corrosion resistance to superheated steam at temperatures higher than 500 degrees C. This increases their potential as fuel cladding for superheated-steam nuclear-fueled reactors as well as in autoclaves operating at modest pressures.
Feasibility of using ductile nickel-chromium alloy claddings to protect chromium alloy turbine vanes and blades
Resistance to oxidation and nitrogen absorption during cyclic oxidation of metallic cladding systems applied to chromium based alloys by gas pressure bonding
Design, fabrication, and evaluation of molybdenum clad, high temperature fuel pins used to provide irradiation data for full length reactor fuel pin design
Constant creep data accumulation for design stress analysis on cladding material thickness around cylindrical reactor fuel element
Clad glass optical waveguides for design of lasers, modulators, couplers, detectors and filters
Nuclear fuel and fission product transport rates through chemically vapor deposited fluoride W cladding determined over high temperature range
Probability calculations for fuel clad surface temperatures of nuclear reactors
Ductile metal clads and coatings of silicides, aluminides and noble metals to protect Cr alloys against nitrogen embrittlement and air oxidation
Gold-nickel brazing alloy, with 5 percent indium added to depress the melting point, is used for brazing of nickel-clad silver electrical conductors which operate at temperatures to 1200 deg F. Alloy has low resistivity, requires no flux, and is less corrosive than other gold-nickel, gold-copper alloys.
Effect of fuel swelling on strains in cladding of cylindrical nuclear fuel elements
Fission gases trapped in fuel particles, cladding and matrix of irradiated refractory metal-uranium oxide cermets determined by gamma counting
Bonding parameters and quality control for cadmium-stainless steel clad fuel pellet containment vessel production
Production engineering and compatibility tests of Ta-8W-2Hf clad UN nuclear fuel element for use in lithium cooled space power unit reactors
Materials technology of Ta-W-Hf clad uranium mononitride fuel for lithium cooled compact fast space power reactor, including irradiation tests
Device, jetcord, is metal-clad linear explosive of sufficient flexibility to allow forming into intricate shapes. Total effect is termed ''cutting'' with jetcord consistently ''cutting'' a target of greater thickness than can be penetrated. Applications include sheet metal working, pipe cutting and fire-fighting.
Performance capabilities and limitations of a fiber optic coupled line scan CRT image recording system were investigated. The test program evaluated the following components: (1). P31 phosphor CRT with EMA faceplate; (2). P31 phosphor CRT with clear clad faceplate; (3). Type 7743 semi-gloss dry process positive print paper; (4). Type 777 flat finish dry process positive print paper; (5). Type 7842 dry process positive film; and (6). Type 1971 semi-gloss wet process positive print paper. Detailed test procedures used in each test are provided along with a description of each test, the test data, and an analysis of the results.
A mass reduction of the moderator and the response to the nucleon flux, responsible for the tissue-star component of the total-dose equivalent rate using a high atomic number material, are discussed. Radiation situations at SST cruising altitudes (approximately 20 km) due to solar proton flares were simulated in the stratosphere and on the ground. Actual stratospheric situations due to galactic cosmic radiation with a limited range of quality factor values (2-4) were encountered during slow ascents by balloons to 36 km. Synthetic situations obtained from high and low energy acclerator radiations were used to obtain radiation distributions having a larger range of quality factor values (11/2-9) than experienced in the stratosphere. The measurements made in these simulations related to the directly ionizing, neutron and tissue-star components of dose-equivalent rate. Due to the restricted range of neutron spectra encountered in the stratosphere, a significant mass reduction of the moderator by 4 kg was made, with the moderator clad with cadmium or some other slow neutron absorber.