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Recovery of uranium and thorium from graphite fuels.
Process for dissolution of Borax IV reactor fuel :laboratory development
Zirflex process for PWR blanket fuel :
Three-minute irradiation at variable power density of prototype CETR fuel pellets
Processing of uranium carbide reactor fuels.
Aqueous processes for dissolution of uranium-molybdenum alloy reactor fuel elements
Processes for recovery of uranium and thorium from graphite-base fuel elements.
Dissolution of BeO- and Al₂O₃-base reactor fuel elements.
Aqueous processing of thorium fuels
The effect of irradiation on the hydrolysis of uranium carbides.
Aqueous processing of thorium fuels.
Hot-cell studies of aqueous dissolution processes for irradiated carbide reactor fuels
Off-gases from the reactions of uranium carbides with nitric acid at 90⁰C