Studies of thermionic materials for space power applications informal monthly report, sep. 1 - sep. 30, 1963
Thermionic materials for space power application - uranium carbide-zirconium carbide fuels and tungsten cladding
TUNGSTEN↗
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Research program for the long term testing of cylindrical diodes and the irradiation of fuel and insulator sixth quarterly summary report, sep. 18 - dec. 17, 1964
Thermionic converter life testing, thermal and irradiation testing of fuel clad emitters, and irradiation of high purity alumina at vacuum temperature
FUEL ELEMENT↗
Research program for the long term testing of cylindrical diodes and the irradiation of fuel and insulator seventh quarterly progress report, dec. 18, 1964 - mar. 17, 1965
Long term testing of cylindrical diodes and irradiation of fuel and insulators - thermionic converter development, thermal and irradiation testing of fuel clad emitters and alumina
ALUMINUM OXIDE↗
The scattering of a TM surface wave by a perfectly conducting strip.
Scattering of TM surface wave by metallic strip above dielectric-clad ground plane, developing expression for Green function and formula for reflection coefficient
WAVE SCATTERING↗
Zirconium alloys with small amounts of iron and copper or nickel show improved corrosion resistance in superheated steam
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.
Greenberg, S.↗
Development of protective coatings for chromium-base alloys Semiannual progress report
Feasibility of using ductile nickel-chromium alloy claddings to protect chromium alloy turbine vanes and blades
VANE↗
Development of protective coatings for chromium-base alloys
Resistance to oxidation and nitrogen absorption during cyclic oxidation of metallic cladding systems applied to chromium based alloys by gas pressure bonding
Bartlett, E. S.↗
Design, fabrication, and fabrication evaluation of high temperature fuel pins Final report
Design, fabrication, and evaluation of molybdenum clad, high temperature fuel pins used to provide irradiation data for full length reactor fuel pin design
Gulley, R. L.↗
Method for calculating allowable creep stress in linearly increasing stress environment
Constant creep data accumulation for design stress analysis on cladding material thickness around cylindrical reactor fuel element
Whitmarsh, C. L., Jr.↗
Single-mode-guide laser components.
Clad glass optical waveguides for design of lasers, modulators, couplers, detectors and filters
Schineller, E. R.↗
Fuel and fission product transport through chemically vapor-deposited fluoride tungsten.
Nuclear fuel and fission product transport rates through chemically vapor deposited fluoride W cladding determined over high temperature range
Hudson, R. G.↗
A new method for treatment of uncertainties in nuclear reactor heat transfer calculations
Probability calculations for fuel clad surface temperatures of nuclear reactors
Hansell, J. D.↗
Protective coatings for chromium alloys.
Ductile metal clads and coatings of silicides, aluminides and noble metals to protect Cr alloys against nitrogen embrittlement and air oxidation
Grisaffe, S. J.↗
High-temperature nickel-brazing alloy
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.
Powell, A. H.↗
Simplified analysis of nuclear fuel pin swelling
Effect of fuel swelling on strains in cladding of cylindrical nuclear fuel elements
Lietzke, A. F.↗
A simple method for determination of fission gases trapped in irradiated fuel forms
Fission gases trapped in fuel particles, cladding and matrix of irradiated refractory metal-uranium oxide cermets determined by gamma counting
Sheibley, D. W.↗
Determination of bonding parameters and inspection techniques for cadmium-to-stainless steel bonds and assembly of two capsule housings Final report
Bonding parameters and quality control for cadmium-stainless steel clad fuel pellet containment vessel production
Gripshover, P. J.↗
Materials technology program for a compact fast reactor for space power
Production engineering and compatibility tests of Ta-8W-2Hf clad UN nuclear fuel element for use in lithium cooled space power unit reactors
Gluyas, R. E.↗