A corrosion study involving high-alloy materials and concentrated hydrofluoric acid (HF) was conducted in support of the Molten Salt Reactor Experiment Conversion Project (CP). The purpose of the test was to obtain a greater understanding of the corrosion rates of materials of construction currently used in the CP vs those of proposed replacement parts. Results of the study will help formulate a change-out schedule for CP parts. The CP will convert slightly less than 40 kg of {sup 233}U from a gas (UF{sub 6}) sorbed on sodium fluoride pellets to a more stable oxide (U{sub 3}O{sub 8}). One by-product of the conversion is the formation of concentrated HF. Six moles of highly corrosive HF are produced for each mole of UF{sub 6} converted. This...
The factors affecting corrosion resistance both of bare and of clad uranium-base alloys are reviewed...
The corrosion behavior of zirconium-base materials, hafnium, high-strength aluminum alloys, and Type...
Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions...
The Conversion Project (CP) of the Molten Salt Reactor Experiment at Oak Ridge National Laboratory (...
The Molten Salt Reactor Experiment (MSRE) remediation requires that almost 40 kg of uranium hexafluo...
A dissertation submitted in fulfilment of the requirement for the degree of Master of Science in Eng...
Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, of...
Fuel elements clad with Zr or containing Zr as a diluent can be recovered by a fluoride-volatility p...
Several alloys were evaluated as possible construction material in chemical processing equipment for...
Five alloys were tested in the presence of water vapor and water vapor with HCl for 1000 hours using...
: : 9 7 7 8 6 9 : = 7 9 9used during the fluorination of fused-salt fuels and subsequent associated ...
Nineteen alloys were evaluated as possible materials of construction for steam heating coils, the di...
Studies carried out on corrosion associated with the hydrofluorination- dissolution phase in the fus...
Unirradiated Mark 42 fuel tubes are to be dissolved in an upcoming campaign in F-canyon. Savannah Ri...
Tests were performed on aluminum alloys to evaluate their behavior in high-temperature, high-pressur...
The factors affecting corrosion resistance both of bare and of clad uranium-base alloys are reviewed...
The corrosion behavior of zirconium-base materials, hafnium, high-strength aluminum alloys, and Type...
Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions...
The Conversion Project (CP) of the Molten Salt Reactor Experiment at Oak Ridge National Laboratory (...
The Molten Salt Reactor Experiment (MSRE) remediation requires that almost 40 kg of uranium hexafluo...
A dissertation submitted in fulfilment of the requirement for the degree of Master of Science in Eng...
Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, of...
Fuel elements clad with Zr or containing Zr as a diluent can be recovered by a fluoride-volatility p...
Several alloys were evaluated as possible construction material in chemical processing equipment for...
Five alloys were tested in the presence of water vapor and water vapor with HCl for 1000 hours using...
: : 9 7 7 8 6 9 : = 7 9 9used during the fluorination of fused-salt fuels and subsequent associated ...
Nineteen alloys were evaluated as possible materials of construction for steam heating coils, the di...
Studies carried out on corrosion associated with the hydrofluorination- dissolution phase in the fus...
Unirradiated Mark 42 fuel tubes are to be dissolved in an upcoming campaign in F-canyon. Savannah Ri...
Tests were performed on aluminum alloys to evaluate their behavior in high-temperature, high-pressur...
The factors affecting corrosion resistance both of bare and of clad uranium-base alloys are reviewed...
The corrosion behavior of zirconium-base materials, hafnium, high-strength aluminum alloys, and Type...
Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions...