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- 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