DocumentCode :
2602438
Title :
The development of a radionuclide thermochemical generator (RTCG) equipped with a sodium solid-electrolyte energy converter
Author :
Chechurov, V.A. ; Tarasov, V.A. ; Grodko, V.A. ; Shvangiradze, R.R. ; Kononykhin, V.S. ; Kucheryaev, A.G. ; Artemova, K.K. ; Ryukhin, Yu A.
Author_Institution :
VNIIRT, Moscow, USSR
fYear :
1989
fDate :
6-11 Aug 1989
Firstpage :
2707
Abstract :
The use of thermoelectrochemical energy conversion for the development of modular radionuclide power devices (RPDs) of output electric power 0.5-1.5 kW and with efficiency exceeding 10-15% is discussed. Experimental RPD prototypes based on radionuclide thermochemical generators (RTCGs) of output powers up to 200 W have been developed, the efficiency being 12%. Methods of circulating the working medium within the RTCG module using arrangements to ensure the support due to the inert gas pressure and the support due to capillary forces under conditions of gravitational field have been investigated and are discussed. Manufacturing procedures for the module components have been developed and tested
Keywords :
electrochemistry; electrolytes; nuclear power; sodium; thermochemistry; 0.5 to 1.5 kW; 10 to 15 percent; 12 percent; Na electrolyte; circulation; development; nuclear power; output electric power; radionuclide thermochemical generator; thermoelectrochemical energy conversion; working medium; Containers; Energy conversion; Power engineering and energy; Power generation; Production; Radiation safety; Radioactive decay; Temperature; Thermoelectricity; Thermomechanical processes;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Energy Conversion Engineering Conference, 1989. IECEC-89., Proceedings of the 24th Intersociety
Conference_Location :
Washington, DC
Type :
conf
DOI :
10.1109/IECEC.1989.74857
Filename :
74857
Link To Document :
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