Browse TRAIL Inventories

Declading of PWR blanket fuel elements with aqueous ammonium fluoride solutions

Kinetics of the thermal decomposition of uranyl fluoride.

Recycle of UO₂F₂ in the fluorox process :reaction of UO₂F₂ with hydrogen

Laboratory development of the sulfex process for the dissolution of consolidated Edison power reactor fuel

Decladding of Consolidated Edison Power reactor fuel by Sulfex and Darex processes :cyclic dissolution experiments

Recovery of uranium and thorium from graphite fuels.

Process for dissolution of Borax IV reactor fuel :laboratory development

Zirflex process for PWR blanket fuel :

Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel :laboratory development

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.

Miscellaneous experiments relating to the processing of CETR fuel by sulfex-thorex and darex-thorex processes

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


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