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