Parametric analysis of a number of space nuclear power systems with a heat-pipe energy-conversion system
Parametric analysis of a number of space nuclear power systems with a heat-pipe energy-conversion system
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DOI:
10.1007/bf02673513
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发表时间:
2000-07
期刊:
影响因子:
0.5
通讯作者:
G. M. Gryaznov;V. Evtikhin;A. N. Chumanov;I. Bogush;I. E. Lyublinskii;A. Vertkov;N. M. Afanas’ev;V. I. Ionkin;I. K. Merkurisov;V. I. Yarygin
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文献类型:
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作者:
G. M. Gryaznov;V. Evtikhin;A. N. Chumanov;I. Bogush;I. E. Lyublinskii;A. Vertkov;N. M. Afanas’ev;V. I. Ionkin;I. K. Merkurisov;V. I. Yarygin
A concept for space nuclear power systems with modular construction of the thermal electric generator based on ampul-type electricity-generating elements is examined. High-temperature heat pipes (molybdenum-lithium) are used to remove heat from the reactor core; heat transmission from the core to the heat-receiving surface of the pipes is accomplished by radiation. Heat is removed by means of medium-temperature (vanadium-potassium) heat pipes. Fast reactors with uranium dicarbide as fuel and carbon-graphite materials as the structural materials are examined for a large series. The thermoelectric generator consists of maximally unified electricity-generating elements using a metallic shunt as the interelectrode insulation.The mass/size characteristics of a large series 20–200 kW are estimated on the basis of an analysis of the thermophysical and mass/size characteristics of the basic elements of space nuclear power systems. 3 figures, 3 references.