Design and performance analysis of the nuclear reactor’s lithium heat pipes for a 110‐kWe Heat Pipes‐Segmented Thermoelectric Module Converters (HP‐STMCs) Space Reactor Power system (SRPS) are presented. The evaporator length of the heat pipes is the same as the active core height (0.45 m) and the C‐C finned condenser is of the same length as the STMC panels (1.5 m). The C‐C finned condenser section is radiatively coupled to the collector shoes of the STMCs placed on both sides. The lengths of the adiabatic section, the values of the power throughput and the evaporator wall temperature depend on the radial location of the heat pipe in the reactor core and the number and dimensions of the potassium heat pipes in the heat rejection radiator. The reactor heat pipes have a total length that varies from 7.57 to 7.73 m, and a 0.2 mm thick Mo‐14%Re wick with an average pore radius of 12 μm. The wick is separated from the Mo‐14%Re wall by a 0.5 mm annulus filled with liquid lithium, to raise the prevailing capillary limit. The nominal evaporator (or reactor) temperature varies from 1513 to 1591 K and the thermal power of the reactor is 1.6 MW, which averages 12.7 kW for each of the 126 reactor heat pipes. The power throughput per heat pipe increase to a nominal 15.24 kW at the location of the peak power in the core and to 20.31 kW when an adjacent heat pipe fails. The prevailing capillary limit of the reactor heat pipes is 28.3 kW, providing a design margin ⩾ 28%.
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4 February 2004
SPACE TECHNOLOGY AND APPLICATIONS INTERNAT.FORUM-STAIF 2004: Conf.on Thermophys.in Microgravity; Commercial/Civil Next Gen.Space Transp.; 21st Symp.Space Nuclear Power & Propulsion; Human Space Explor.; Space Colonization; New Frontiers & Future Concepts
8-11 February 2004
Albuquerque, New Mexico (USA)
Research Article|
February 04 2004
Reactor Lithium Heat Pipes for HP‐STMCs Space Reactor Power System Available to Purchase
Jean‐Michel Tournier;
Jean‐Michel Tournier
Institute for Space and Nuclear Power Studies, The University of New Mexico, Albuquerque, NM, 87131
Chemical and Nuclear Engineering Dept., The University of New Mexico, Albuquerque, NM, 87131
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Mohamed S. El‐Genk
Mohamed S. El‐Genk
Institute for Space and Nuclear Power Studies, The University of New Mexico, Albuquerque, NM, 87131
Chemical and Nuclear Engineering Dept., The University of New Mexico, Albuquerque, NM, 87131
Search for other works by this author on:
Jean‐Michel Tournier
Institute for Space and Nuclear Power Studies, The University of New Mexico, Albuquerque, NM, 87131
Chemical and Nuclear Engineering Dept., The University of New Mexico, Albuquerque, NM, 87131
Mohamed S. El‐Genk
Institute for Space and Nuclear Power Studies, The University of New Mexico, Albuquerque, NM, 87131
Chemical and Nuclear Engineering Dept., The University of New Mexico, Albuquerque, NM, 87131
AIP Conf. Proc. 699, 781–792 (2004)
Citation
Jean‐Michel Tournier, Mohamed S. El‐Genk; Reactor Lithium Heat Pipes for HP‐STMCs Space Reactor Power System. AIP Conf. Proc. 4 February 2004; 699 (1): 781–792. https://doi.org/10.1063/1.1649643
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