Browse TRAIL Inventories

Chemical Technology Division annual progress report for period ending ...

Removal of fission products from an acid aluminum nitrate solution by co-precipitatio methods

Removal of fission products from reactor wastes :Laboratory studies of liquid-liquid extraction from an acid aluminum nitrate solution

Fuel costs in spherical slurry reactors

Progress report on volatility pilot plant corrosion problems to April 21, 1957

Components of the fused-salt and sodium circuits of the aircraft reactor experiment

Thorex process :third uranium cycle studies

Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements

Dissolution of sintered thorium-uranium oxide fuel in nitric acid-fluoride solutions

Progress report on the analysis of dissolver solutions by controlled-potential coulometric titration

Recovery of uranium and plutonium from sulfuric acid decladding solutions

Solvent extraction recovery of vanadium (and uranium) from acid liquors with di(2-ethylhexyl) phosphoric acid

Sulfex process :depassivation of stainless steel

Design of chemical processing plant for homogenous reactor test

Laboratory development of the thorex process :progress report, December 1, 1955 to January 1, 1958

Development of the Sulfex process for decladding stainless-steel-clad power reactor fuel elements with sulfuric acid

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

Process for dissolution of Borax IV reactor fuel :laboratory development

Tributyl phosphate-hydrocarbon diluent repurification in radiochemical processing at ORNL :status summary

Corrosion associated with fluorination in the Oak Ridge National Laboratory fluoride volatility process

Corrosion associated with hydrofluorination in the Oak Ridge National Laboratory fluoride volatility process

Laboratory development of the acid thorex process for recovery of Consolidated Edison Throium Reactor fuel

Corrosion of stainless steel in acidic nitrate waste solutions from processing stainless steel reactor fuels

Recovery of fission products from waste solutions by solvent extraction

Reduction of uranium hexafluoride retention on beds of magnesium fluoride used for removal of technetium hexafluoride

Carburization and chemical treatments for recovery of uranium from stainless steel fuel elements

The design and evaluation of a delayed-neutron leached-hull monitor


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