There have been two main deterrents to the development of semiportable nuclear reactors. One is the high development costs; the other is the inability to satisfy with assurance the questions of operational safety. This report shows how a split-core, heat-pipe cooled reactor could conceptually eliminate these deterrents, and examines and summarizes recent work on split-core, heat-pipe reactors. A concept for a small reactor that could be developed at a comparatively low cost is presented. The concept would extend the technology of subcritical radioisotope thermoelectric generators using 238 PuO2 to the evolution of critical space power reactors using 239 PuO2. Lantz, E. and Breitwieser, R. and Niederauer, G. F. Glenn Research Center NASA-TM-X-2996, E-7542 RTOP 503-25 27120 HEAT PIPES; REACTOR CORES; REACTOR DESIGN; PLUTONIUM OXIDES; PLUTONIUM 238; REACTOR SAFETY; THERMOELECTRIC GENERATORS
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