PRODUCTION OF STRONTIUM-TITANATE RADIOISOTOPE FUEL FOR SNAP 7B THERMOELECTRIC GENERATOR
PRODUCTION OF STRONTIUM-TITANATE RADIOISOTOPE FUEL FOR SNAP 7B THERMOELECTRIC GENERATOR
The conversion of strontium-90 to strontium titanate heat source pellets is described. Encapsulation of the fuel in Hastelloy C containers and necessary leak testing, decontamination and calorimetry procedures are covered. Loading of the SNAP 7B thermoelectric generator was accomplished. (auth)
- University of North Texas United States
Strontium Oxides, Isotope Separation, Titanium Oxides Nesdps Office Of Nuclear Energy Space And Defense Power Systems, Production, Hastelloy, 540, 620, Calorimeters, Isotope Technology, Molybdenum Alloys, Fuel Cans, Leak Detectors, Snap Systems, Strontium 90, Nesdps Office Of Nuclear Energy Space And Defense Power Systems, Space Vehicles, Thermoelectric Cells, Nickel Alloys, Chromium Alloys, Decontamination
Strontium Oxides, Isotope Separation, Titanium Oxides Nesdps Office Of Nuclear Energy Space And Defense Power Systems, Production, Hastelloy, 540, 620, Calorimeters, Isotope Technology, Molybdenum Alloys, Fuel Cans, Leak Detectors, Snap Systems, Strontium 90, Nesdps Office Of Nuclear Energy Space And Defense Power Systems, Space Vehicles, Thermoelectric Cells, Nickel Alloys, Chromium Alloys, Decontamination
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