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Publication of BE757712ApublicationCriticalpatent/BE757712A/en
B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
B01J2/00—Processes or devices for granulating materials, e.g. fertilisers in general; Rendering particulate materials free flowing in general, e.g. making them hydrophobic
B01J2/02—Processes or devices for granulating materials, e.g. fertilisers in general; Rendering particulate materials free flowing in general, e.g. making them hydrophobic by dividing the liquid material into drops, e.g. by spraying, and solidifying the drops
B01J2/06—Processes or devices for granulating materials, e.g. fertilisers in general; Rendering particulate materials free flowing in general, e.g. making them hydrophobic by dividing the liquid material into drops, e.g. by spraying, and solidifying the drops in a liquid medium
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Chemical & Material Sciences
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Organic Chemistry
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Chemical Kinetics & Catalysis
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Inorganic Compounds Of Heavy Metals
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Abstract
Particles are made by introducing a soln. or dispersion of salts thereof, in the form of drops into a soln. of a reactant (R) which precipitates the drops in the form of spherical particles, the drops being introduced across the inert liquid layer, pref. a hydrocarbon or an alcohol, esp. isoamyl alcohol, which is substantially immiscible with the other components, and which has a density lower the (R) solution. The particles are used for nuclear reactor fuels.
BE757712D1970-10-20Spherical particles containing uranium, thor - ium or plutonium or other transuranic elements
BE757712A
(en)
Packaging for transport of irradiated fuel elements - incorporating empty compartment and neutron poison between groups of housings giving control of criticality
Structural changes in briefly treated uranium dioxide with and without neutron irradiation as an aid in determining temperature distribution in fuel elements for nuclear reactors(Structural changes in briefly treated uranium dioxide with and without neutron irradiation as aid in determining temperature distribution in fuel elements for nuclear reactors)
Irradiation of mixed UO sub 2- PuO sub 2 oxide samples for fast neutron reactor fuel elements(Thermal neutron irradiation on mixed uranium dioxide-plutonium dioxide samples for fast reactor fuel elements)
Determination of some physical properties of loops and experiment holes in the MR reactor(Determining neutron properties of loops containing fuel assemblies and of positions for irradiating structural materials in MR reactor)
Study of the release of fission gases from UO 2 samples irradiated with different doses Quarterly progress report, Jan.- Mar. 1966(Apparatus for handling uranium dioxide specimens irradiated with different neutron flux doses for releasing fission gases from samples)