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Multidisciplinary Simulation of Graphite-Composite and Cermet Fuel Elements for NTP Point of Departure Designs
This paper compares the expected performance of two Nuclear Thermal Propulsion fuel types. High fidelity, fluid/thermal/structural + neutronic simulations help predict the performance of graphite-composite and cermet fuel types from point of departure engine designs from the Nuclear Thermal Propulsion project. Materials and nuclear reactivity issues are reviewed for each fuel type. Thermal/structural simulations predict thermal stresses in the fuel and thermal expansion mis-match stresses in the coatings. Fluid/thermal/structural/neutronic simulations provide predictions for full fuel elements. Although NTP engines will utilize many existing chemical engine components and technologies, nuclear fuel elements are a less developed engine component and introduce design uncertainty. Consequently, these fuel element simulations provide important insights into NTP engine performance.
Surface failure of titanium carbide cermet and silicon carbide balls in rolling contact at temperatures to 2000 degrees f
Surface failure of titanium carbide cermet and silicon carbide ball in rolling contact at temperatures to 2,000-deg f
A high temperature, electrically insulating cermet seal having high strength and thermal conductance
High strength, thermal conductance cermet seal for thermionic diode
High temperature creep-rupture properties of a tungsten-uranium dioxide cermet produced from coated particles
High temperature creep rupture strength of tungsten uranium dioxide cermets
Thermal conductivity of coated particle uranium dioxide tungsten cermets
Thermal conductivity measurements on tungsten coated uranium dioxide cermets
A high temperature, electrically insulating cermet seal having high strength and thermal conductance.
High temperature cermet seal for research thermionic diode, discussing resistivity, structural integrity, thermal shock resistance, tensile strengths and thermal conductance
A high-temperature, electrically insulating cermet seal having high strength and thermal conductance.
High temperature insulating cermet seal for thermionic diodes noting high shock resistance and thermal conductance
High-temperature cermets. I - Compatibility.
Refractory oxides, carbides and borides in combination with metals investigated for stability in high temperature cermet applications
High-temperature cermets. II - Wetting and fabrication.
Wetting and fabrication characteristics of high temperature cermets
Development of silicon nitride and cermet resistors for use in a binary counter, metal insulator field effect transistor circuit Final report, 1 Dec. 1966 - 31 Mar. 1968
Silicon nitride and cermet resistors for binary counter metal insulator field effect transistor circuit
Fabrication of cermets of uranium nitride and tungsten or molybdenum from mixed powders and from coated particles
Fabrication of cermets of uranium nitride and tungsten or molybdenum from mixed powders and from coated particles for nuclear fuel elements
A procedure for furnace brazing butt joints in tungsten-uranium dioxide cermet cylinders at 3000 deg C
Furnace brazing butt joints in tungsten-uranium dioxide cermet cylinders at 3000 deg C
Thermal and radiation stability of thin-film cermet resistive elements
Thermal and radiation stability of thin films cermet resistive elements with silicon monoxide
Method of making a cermet Patent
Cermet for nuclear fuel constructed by pressing metal coated ceramic particles in die at temperature to cause bonding of metal coatings, and tested for thermal stability
Thermal and radiation stability of thin-film cermet resistive elements
Thin film cermet resistive elements physical controls electrical properties, physical controls, thermal and radiation stability
Some neutron and gamma radiation characteristics of plutonium cermet fuel for isotopic power sources
Gamma and neutron measurements on various types of plutonium sources are presented in order to show the effects of O-17, O-18 F-19, Pu-236, age of the fuel, and size of the source on the gamma and neutron spectra. Analysis of the radiation measurements shows that fluorine is the main contributor to the neutron yields from present plutonium-molybdenum cermet fuel, while both fluorine and Pu-236 daughters contribute significantly to the gamma ray intensities.
In-pile and out-of-pile testing of a molybdenum-uranium dioxide cermet fueled themionic diode
The behavior of Mo-UO2 cermet fuel in a diode for thermionic reactor application was studied. The diode had a Mo-0.5 Ti emitter and niobium collector. Output power ranged from 1.4 to 2.8 W/cm squared at emitter and collector temperatures of 1500 deg and 540 C. Thermionic performance was stable within the limits of the instrumentation sensitivity. Through 1000 hours of in-pile operation the emitter was dimensionally stable. However, some fission gases (15 percent) leaked through an inner clad imperfection that occurred during fuel fabrication.