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- 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
