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2013
Conference Paper
Titel
Development and testing of an americium-241 radioisotope thermoelectric generator
Abstract
The European program to develop radioisotope space nuclear power systems includes the development of thermoelectric and Stirling power converters. Based on a number of industry academic partnerships other key technology areas under development include radioisotope fuel production and containment in the event of launcher failure or unscheduled spacecraft re-entry. Thermoelectric conversion system studies are targeted at electrical power levels <50 W electric based on current thermoelectric conversion technology. In Europe isotope selection studies have identified 241Am as the isotope of choice for a European program. 241Am fuel can be produced economically and at high isotopic purity by separation from stored separated Pu produced during the reprocessing of civil fuel. For thermoelectric conversion systems generating less than 50 W electric, detailed mission requirements and performance targets are still under development. This paper outlines the requirements for a European 241Am fuelled Radioisotope Thermoelectric Generator (RTG), describes the most recent updates in system design and provides further insight into recent laboratory prototype test campaigns.
Author(s)