Thermionic reactor ion propulsion spacecraft for unmanned outer planet exploration
Thermionic reactor electric propulsion for unmanned outer planets exploration, discussing spacecraft design, launch vehicle, weight factors, etc
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Thermionic reactor electric propulsion for unmanned outer planets exploration, discussing spacecraft design, launch vehicle, weight factors, etc
Thermionic reactor electric spacecraft propulsion system for unmanned outer planets missions, investigating voltage and radiator temperature effects on weight
Nuclear thermionic systems conceptual design with converters outside reactor to reduce weight
Design optimization of out-of-core cylindrical thermionic converter module with heat pipes and integral finned radiator
Design and operation of split fueled cores with axial heat pipes for 350 kwe out-of-core thermionic power converter system
Externally fueled thermionic reactor power plant incorporation into unmanned ion propulsion spacecraft
Impact resistant power packages for unmanned planetary probe landers, discussing radioisotope thermionic multiconverter array optimal configuration
Open loop transient analysis of thermionic diode kinetics experiment with analog computer nuclear reactor simulator
Double ended full length external fuel thermionic converter, describing component fabrication, assembly sequence, joining methods, vacuum test procedures and converter load control
Design, fabrication and testing of electrically heated externally configured thermionic diodes with emitter using mandrel side of CVD fluoride tungsten for electrode surface
Out-of-core heat pipe heated and cooled thermionic converter module mechanical design, fabrication and subcomponent performance evaluation
Out-of-core nuclear thermionic converter system design feature concerning heat pipes, vapor-cooled radiators, modularity and reliability
Cesium-filled thermionic energy converters are examined as candidate electrical energy sources in spacecraft requiring tens to hundreds of kilowatts of electric power. The high operating temperatures necessary for a large specific power and high efficiency inevitably impose stringent constraints on the converter fabrication to achieve the desired reliability of the power system. The converter physics for reducing operating temperatures and cesium plasma losses are studied to achieve high reliability without sacrificing the power performance of the converters. Various cesium parameters which affect the converter performance are: (1) electron temperatures, (2) plasma ion densities, and (3) electric potential profiles. These were investigated using a Langmuir probe in a simulated converter. The parameters were measured in different cesium discharge modes.
A 25.4-cm long externally configured converter was performance tested by electrically heating the emitter to simulate reactor thermal power input. The measured maximum output power was limited by the maximum input power available from the electric RF induction heater. With maximum heater input power, the converter electric output was 178 W (1.95 W/sq cm) at an emitter temperature of 1946 K. This electric output power was smaller than expected. A reactor-core-length (25.4-cm long) cylindrical thermionic converter power and maintaining the emitter-to-collector gap without shorting are of major importance to the feasibility of a 25.4-cm-long reactor fuel element. The emitter of the converter is located externally to the collector to increase the fuel-volume fraction and to allow redundant collector cooling in a reactor configuration.
The effect of collector, guard-ring potential imbalance on the observed collector-current-density J, collector-to-emitter voltage V characteristic was evaluated in a planar, fixed-space, guard-ringed thermionic converter. The J,V characteristic was swept in a period of 15 msec by a variable load. A computerized data acquisition system recorded test parameters. The results indicate minimal distortion of the J,V curve in the power output quadrant for the nominal guard-ring circuit configuration. Considerable distortion, along with a lowering of the ignited-mode striking voltage, was observed for the configuration with the emitter shorted to the guard ring. A limited-range performance map of an etched-rhenium, niobium, planar converter was obtained by using an improved computer program for the data acquisition system.
A nuclear thermionic reactor as the electric power source for an electric propulsion spacecraft introduces a nuclear radiation environment that affects the spacecraft configuration, the use and location of electrical insulators and the science experiments. The spacecraft is conceptually configured to minimize the nuclear shield weight by: (1) a large length to diameter spacecraft; (2) eliminating piping penetrations through the shield; and (3) using the mercury propellant as gamma shield. Since the alumina material is damaged by the high nuclear radiation environment in the reactor it is desirable to locate the alumina insulator outside the reflector or develop a more radiation resistant insulator.
The application of a thermionic reactor power system to the modular space station is described. The nominal net power is 40 kWe, with the power system designed to be applicable over the power range from 25 to 60 kWe. The power system is designed to be launched by the space shuttle. Radiation protection is provided by LiH neutron shielding and W gamma shielding in a shaped 4 pion configuration, i.e., the reactor is shielded on all sides but not to equal extent. Isodose contours are presented for the region around the modular space station. Levels and spectral distribution of radiation are given for later evaluation of effects on space station experiments. Parametric data on the effects of separation distance on power system mass are presented.
Most thermionic reactors are designed to allow the fission gases to escape out of the emitter. A scheme to allow the fission gases to escape is proposed. Because of the low activity of the fission products, this method should pose no radiation hazards.