Engineering topics
Publications and source records attributed to Lanzo, C. D..
Experimental and theoretical investigations were carried out to determine the feasibility of using a small scale fissioning uranium plasma as the power source in a driver reactor. The driver system is a light water cooled and moderated reactor of the MTR type. The eight experiments and proposed configurations for the reactor are outlined.
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In-Pile experimental tests were conducted on two fuel pins mounted side-by-side in a holder assembly. The fuel pins consisted of stacked fully enriched UO2 pellets enclosed in a type 316 stainless steel clad 1/2 inch outside diameter and 3 inches in length. Each fuel pin contained four pellets for a total of 22 grams of fuel weight. The experiment was operated to maintain the maximum clad temperature at 395 K corresponding to a fuel temperature at the central void surface of 2350 K. Total primary coolant water flow past the pin holder was calculated to be 110 gallons per minute. Forty-four gallons per minute at a velocity of 36.5 feet per second flowed around each fuel pin. Calculations indicated the maximum heat flux was at the point of the highest temperature and was equal to 0.24 kW/sq cm or 7.62 Btu/hr sq ft. A series of high resolution neutron radiographs of the nuclear fueled vapor transport capsule was taken. The thermal neutrons emitted from the core of the 60 megawatt Plum Brook reactor facility were used.
Establishing an arc between water-cooled tungsten-tipped electrodes, maintaining the arc along the centerline of a central jet of argon gas, and surrounding the argon jet with a coaxial sheath of nitrogen stabilizes operation of a low-frequency ac electric arc.
Flow characteristics of curved porous wall gas core reactors for nuclear rocket engines, visualizing simulated fuel flow with air-smoke combination
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Summaries of recent gaseous reactor fluid mechanics experiments
Curved porous wall gas core reactor flow distribution experiment
Gaseous reactor fluid mechanics for nuclear rocket engines, discussing experiments on geometries used in open cycle engine for acceptable uranium loss rate
Gas core reactor curved porous walls geometry tested with clear and smoky air injection, noting mass flow ratio in reactor cavity
Alternating current plasma arc coaxial flow stabilization
Transmittance and absorption cross sections of carbon particles suspended in flowing stream of nitrogen gas
Transmissivity of carbon particle-seeded nitrogen jet for heat transfer predictions
Alternating current plasma arc coaxial flow stabilization
Coaxial flow stabilization of alternating-current plasma arc
Simulated fuel assembly-type flow measurement apparatus for coolant flow in reactor core
Temperature probe used in a high temperature, high velocity gas stream consists of cooled outer shell and a cooled platinum sensing tube with iron constantan thermocouples.