Browse TRAIL Inventories

Critical experiments and nuclear safety at Oak Ridge National Laboratory

Boron-aluminum and boron-uranium-aluminum alloys for reactor application

Investigation of the factors affecting sensitization of army package power reactor (APPR-1) fuel elements

Declading of PWR blanket fuel elements with aqueous ammonium fluoride solutions

Segregation in uranium-aluminum alloys and its effect on the fuel loading of aluminum-base fuel elements

Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements

The ORNL gas-cooled reactor :advanced concepts

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

Recovery of uranium and plutonium from sulfuric acid decladding solutions

Sulfex process :depassivation of stainless steel

Project Aquarium :laboratory and field corrosion tests for the Geneva Conference Reactor

A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors

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


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