A process hns been developed for impregnating graphite with U/sub 3/O/ sub 8/ in connection with the proposed use of such material for fuel rod elements in the Daniels' High Temperature Pile. The process as developed consists of five steps: Fabrication of the graphite in the desired shape; Pretreatment of the graphite by boiling in water and then firing in helium at 800 deg C; Impregnating the graphite by first evacuating the pretreated material and then admitting an aqueous uranyl nitrate solution whose concentration is etermined by the final uranium content desired in the raphite; Drying the impregnated graphite slowly under quilibrium conditions; and Conversion of the uranyl itrate to U/sub 3/O/sub 8/ by firing in helium at 800 deg C. By...
Zircaloy-2 clad fuel rods whose fuel was U/sup 238/ -10 wt.% Nb-5 wt.% U/ /sup 235/ were fabricated ...
The objective of this paper is to investigate the transport of uranium oxide particles that may be p...
The effect of irradiation on the hydrolytic behavior of uranium monocarbide as related to the aqueou...
The two predominate methods of dispersing uranium in graphite are reviewed and evaluated. This study...
Improved graphites for use in fuel elements were developed from artificial graphites and phenolic re...
Sound high density cylinders of graphite have been made by cold compacting finely ground artificial ...
Declassified 24 Sep 1973. The recovery of uranium from graphite -- uranium carbide fuels, such as th...
Uranium carbide dispersed in graphite was produced under vacuum by means of carbothermic reduction o...
Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel...
Uranium carbide dispersed in graphite was produced under vacuum by means of carbothermic reduction o...
Graphite elements of nuclear power plants accumulate in time a small amount of uranium, radionuclide...
Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC...
The operations in a process proposed for recovering uranium from spent uranium-- zirconium alloy fue...
Declassified 24 Sep 1973. Two chloride volatility processes for the recovery of uranium from the com...
A nucleation method based on a composite of uranium dioxide (UO2) and graphene is presented by in si...
Zircaloy-2 clad fuel rods whose fuel was U/sup 238/ -10 wt.% Nb-5 wt.% U/ /sup 235/ were fabricated ...
The objective of this paper is to investigate the transport of uranium oxide particles that may be p...
The effect of irradiation on the hydrolytic behavior of uranium monocarbide as related to the aqueou...
The two predominate methods of dispersing uranium in graphite are reviewed and evaluated. This study...
Improved graphites for use in fuel elements were developed from artificial graphites and phenolic re...
Sound high density cylinders of graphite have been made by cold compacting finely ground artificial ...
Declassified 24 Sep 1973. The recovery of uranium from graphite -- uranium carbide fuels, such as th...
Uranium carbide dispersed in graphite was produced under vacuum by means of carbothermic reduction o...
Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel...
Uranium carbide dispersed in graphite was produced under vacuum by means of carbothermic reduction o...
Graphite elements of nuclear power plants accumulate in time a small amount of uranium, radionuclide...
Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC...
The operations in a process proposed for recovering uranium from spent uranium-- zirconium alloy fue...
Declassified 24 Sep 1973. Two chloride volatility processes for the recovery of uranium from the com...
A nucleation method based on a composite of uranium dioxide (UO2) and graphene is presented by in si...
Zircaloy-2 clad fuel rods whose fuel was U/sup 238/ -10 wt.% Nb-5 wt.% U/ /sup 235/ were fabricated ...
The objective of this paper is to investigate the transport of uranium oxide particles that may be p...
The effect of irradiation on the hydrolytic behavior of uranium monocarbide as related to the aqueou...