|NEEP602 Fall97 - Lecture 22|
G. L. Bennett et. al., 1994, "Prelude to the Future: A Brief History of Nuclear Thermal Propulsion in the United States", p. 221 in A Critical Review of Space Nuclear Power and Propulsion, 1984-93, ed. M. El Genk, American Institute of Physics Press, New York.
Bennett, G. L. 1995, "Space Applications", CRC Handbook of Thermoelectrics, ed. D. M. Rowe, CRC Press, p. 515. See also articles by Gunn, S. V., 1989, "Development of Nuclear Rocket Technology", American Institute of Aeronautics and Astronautics Paper 89-2386
D. Buden, 1994, "Summary of Space Nuclear Reactor Power Systems (1983-1992)", p. 21 in A Critical Review of Space Nuclear Power and Propulsion, 1984-93, ed. M. El Genk, American Institute of Physics Press, New York.
National Council on Radiation Protection, 1989, "Guidance on Radiation Received in Space Activities", NCRP report #98, July 31, 1989
Westinghouse Corporation, 1967, "NRX-A6 Test Predictions", WANL-TME-1613
1.) What limits the practical power level of a RTG using 238Pu?
2.) Assume you were asked to provide 500 watts of electricity and the end of life (EOL) of a 20 year mission. How much 238Pu (in kg) would you have to start with if the thermoelectrics were 4% efficient?
3.) What are the pro and con arguments for RTG's vs. small fission reactors concerning launch pad accidents?
4.) (For the Nuclear Engineers) Can you imagine why the rocket designers chose Graphite reactors over Fast Breeder reactors for a Mars mission?
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