Palmer Quest : a feasible and valuable vision mission to the Mars polar caps
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Palmer Quest↗
Engineering topics
Lipinski, R. J.
Publications and source records attributed to Lipinski, R. J..
Mars mission concepts incorporating a 3 kWe surface fission power system
A team from JPL and the DOE has recently completed a study to investigate the utility of a 3 kWe surface fission power system for Mars missions. In the course of this study it became clear that the application of such a power system was enabling to a wide variety of potential surface missions.
nuclear reactor Mars Lander cryobot rover↗
Design concept for a nuclear reactor-powered Mars Rover
This paper describes the unique design challenges encountered in the development of this mission architecture and incorporation of the fission power system in the rover, and presents a detailed description of the final design of this innovative concept for providing long range, long duration mobility on Mars.
nuclear↗
Mission concept for a nuclear reactor-powered Mars cryobot lander
This paper describes the unique design challenges encountered in the development of this mission architecture and incorporation of the fission power system in the lander, and presents a detailed description of the final design of this trailblazing science mission.
nuclear↗
NEPTranS: a shuttle-tended NEP interplanetary transporation system
This paper discusses the preliminary design developed for the NEP Interplanetary Transfer Vehicle, including its configuration and design features, and outlines the concept for mission design, including discussion of unique requirements for launch, deployment and operations with the Space Shuttle, and rendezvous and servicing by the Shuttle in Earth orbit following a return from each target destination.
NEP↗
Direct-Drive Gas-Cooled Reactor Power System: Concept and Preliminary Testing
This paper describes the concept and preliminary component testing of a gas-cooled, UN-fueled, pin-type reactor which uses He/Xe gas that goes directly into a recuperated Brayton system to produce electricity for nuclear electric propulsion. This Direct-Drive Gas-Cooled Reactor (DDG) is designed to be subcritical under water or wet- sand immersion in case of a launch accident. Because the gas-cooled reactor can directly drive the Brayton turbomachinery, it is possible to configure the system such that there are no external surfaces or pressure boundaries that are refractory metal, even though the gas delivered to the turbine is 1144 K. The He/Xe gas mixture is a good heat transport medium when flowing, and a good insulator when stagnant. Judicious use of stagnant cavities as insulating regions allows transport of the 1144-K gas while keeping all external surfaces below 900 K. At this temperature super-alloys (Hastelloy or Inconel) can be used instead of refractory metals. Super-alloys reduce the technology risk because they are easier to fabricate than refractory metals, we have a much more extensive knowledge base on their characteristics, and, because they have a greater resistance to oxidation, system testing is eased. The system is also relatively simple in its design: no additional coolant pumps, heat exchanger, or freeze-thaw systems are required. Key to success of this concept is a good knowledge of the heat transfer between the fuel pins and the gas, as well as the pressure drop through the system. This paper describes preliminary testing to obtain this key information, as well as experience in demonstrating electrically heated testing of simulated reactor components.
Wright, S. A.↗