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A Stirling radioisotope generator (SRG) is a type of radioisotope generator based on a Stirling engine powered by a large radioisotope heater unit. The hot end of the Stirling converter reaches high temperature and heated helium drives the piston, with heat being rejected at the cold end of the engine. A generator or alternator converts the ...
The advanced Stirling radioisotope generator (ASRG) is a radioisotope power system first developed at NASA's Glenn Research Center. It uses a Stirling power conversion technology to convert radioactive-decay heat into electricity for use on spacecraft .
There is a potential for nuclear-powered Stirling engines in electric power generation plants. Replacing the steam turbines of nuclear power plants with Stirling engines might simplify the plant, yield greater efficiency, and reduce the radioactive byproducts. A number of breeder reactor designs use liquid sodium as a coolant. If the heat is to ...
A supply of liquid oxygen is carried to support burning of diesel fuel to power the engine. Stirling engines are also fitted to Swedish Södermanland-class submarines, the Archer-class submarines in service in Singapore, and the Japanese Sōryū-class submarines, with the engines license-built by Kawasaki Heavy Industries. In a submarine ...
Gilbert cloud chamber, assembled An alternative view of kit contents. The lab contained a cloud chamber allowing the viewer to watch alpha particles traveling at 12,000 miles per second (19,000,000 m/s), a spinthariscope showing the results of radioactive disintegration on a fluorescent screen, and an electroscope measuring the radioactivity of different substances in the set.
A Stirling radioisotope generator is a Stirling engine driven by the temperature difference produced by a radioisotope. A more efficient version, the advanced Stirling radioisotope generator, was under development by NASA, but was cancelled in 2013 due to large-scale cost overruns. [8]
Diagram of an RTG used on the Cassini probe. A radioisotope thermoelectric generator (RTG, RITEG), sometimes referred to as a radioisotope power system (RPS), is a type of nuclear battery that uses an array of thermocouples to convert the heat released by the decay of a suitable radioactive material into electricity by the Seebeck effect.
It reached 850 °C (1,560 °F) and generated about 5.5 kW of fission power. The test evaluated failure scenarios including shutting down the Stirling engines, adjusting the control rod, thermal cycling, and disabling the heat-removal system. A Scram test concluded the experiment. The test was considered to be a highly successful demonstration. [17]