Other

The United States of America as Represented by the United States

Guy R Elliott

Nicholas E Vanderborgh

Milton W McDaniel

Barton L Houseman

Bruce L Barraclough

Wilmer L Sibbitt, Jr

James A Horton

Russell D Elliott

Howard W Hayden, Jr

James J Glass

Charles E Holley

A practical method is described for preparation of radioactive ion-exchange resin for its disposal after the ion-exchange resin has become radioactive in the process of decontaminating radioactive water. Substantially nonradioactive material, which has been derived from the radioactive ion-exchange resin can be disposed of conventionally. The concentration allows corollary reduction of the volume of radioactive waste which must be handled in very costly ways. The radioactive ion-exchange resin and materials that react with the radioactive decaying atoms are heated under controlled atmospheres to (i) form nonvolatile chemicals that hold the decaying atoms, and (ii) under controlled conditions, depolymerize, vaporize, pyrolize, and otherwise decompose and remove nonradioactive components of the ion-exchange resin from the radioactive decaying atoms.

Preparation of radioactive ion-exchange resin for its storage or disposal

A method is described for forming metallic uranium, or a uranium alloy, from uranium oxide in a manner which substantially eliminates the formation of uranium-containing wastes. A source of uranium dioxide is first provided, for example, by reducing uranium trioxide (UO.sub.3), or any other substantially stable uranium oxide, to form the uranium dioxide (UO.sub.2). This uranium dioxide is then chlorinated to form uranium tetrachloride (UCl.sub.4), and the uranium tetrachloride is then reduced to metallic uranium by reacting the uranium chloride with a metal which will form the chloride of the metal. This last step may be carried out in the presence of another metal capable of forming one or more alloys with metallic uranium to thereby lower the melting point of the reduced uranium product. The metal chloride formed during the uranium tetrachloride reduction step may then be reduced in an electrolysis cell to recover and recycle the metal back to the uranium tetrachloride reduction operation and the chlorine gas back to the uranium dioxide chlorination operation.

Process for continuous production of metallic uranium and uranium alloys

Apparatus for separating molten salt by-product phase from molten uranium or molten uranium alloy product phase using a barrier which passes molten salt but retains molten uranium or molten uranium alloy. The operation of the barrier relies on the differences in the physical behavior of said molten salt from the behavior of said molten uranium or molten uranium alloy as they interact with each other and with said barrier.

Apparatus for separating molten salt from molten salt or molten uranium

Pretreatment methods are described for aiding the separation and recovery or uranium alloy from mixtures of uranium alloy with metal oxides and metal fluorides. Hydrogen fluoride converts oxides to fluorides, and magnesium converts uranium fluoride to uranium alloy. Following pretreatments, the uranium alloys are separated by melting in a molten-salt bath, or the uranium alloy may be melted as part of the pretreatment process.

Recovery of uranium alloy

There is disclosed a process and apparatus for recovering metallic uranium from scrap containing metallic uranium by introducing such metallic uranium scrap into a bath containing, in molten form, at least one member selected from the group consisting of BaF.sub.2, CaF.sub.2, MgF.sub.2, LiF, YF.sub.3, trifluorides of lanthanides and mixtures thereof, preferably with such member constituting at least 75 mole percent of the bath at a temperature above the melting point or uranium and under an inert atmosphere and casting the purified molten metallic uranium. The bath of molten salt preferably includes means for improving contact between the molten metallic uranium scrap and the molten salt during passage of the molten uranium through the bath of molten salt.

Process and apparatus for recovering and purifying uranium scrap

A method is provided for cleaning depleted uranium and its associated radioactivity from target sands, for reusing many of the reactants used in the cleaning, and for recovering the depleted uranium content as uranyl nitrate. The method involves roasting and tumbling target sands with molten nitrate mixtures, followed by aqueous extraction to remove the nitrates, then nitric acid extraction to remove uranium oxides as uranyl nitrates which can be solvent extracted into organic phases.

Depleted-uranium recovery from and cleaning of target sands

A method is described for decontaminating magnesium fluoride resulting from the reduction of uranium fluoride to the metal by reaction with magnesium. This decontamination employs reactions with magnesium and carbon to remove radioactive components from the said magnesium fluoride in its molten state.

Reductive decontamination of magnesium fluoride

A method and apparatus are provided for reducing uranium fluoride with magnesium to form uranium metal or uranium alloys. The reduction is carried out in a molten-salt solution in which the metallic product sinks and separates while the magnesium fluoride by-product dissolves into the molten salt or forms a solid precipitate outside of the metallic region.

Magnesium reduction of uranium fluoride in molten salts

A method and apparatus are provided for reducing uranium oxide with magnesium to form uranium metal. The reduction is carried out in a molten-salt solution of density greater than 3.4 grams per cubic centimeter, thereby allowing the uranium product to sink and the magnesium oxide byproduct to float, consequently allowing separation of product and byproduct.

Magnesium reduction of uranium oxide

A method is provided for substantially self-powering turbines by expanding compressed gases released downhole or in adjacent formations. These gases do work in the turbines as the gases expand toward atmospheric pressure at the earth's surface. The method offers alternative and supplemental approaches to recovering hydrocarbon gases, water vapor, carbon dioxide, other gases, and petroleum from watered out wells and from deep or hot wells.

Substantially self-powered fluid turbines

A method and apparatus are provided for producing gaseous hydrocarbons from formations comprising solid hydrocarbon hydrates located under either a body of land or a body of water. The vast natural resources of such hydrocarbon hydrates can thus now be economically mined. Relatively warm brine or water is brought down from an elevation above that of the hydrates through a portion of the apparatus and passes in contact with the hydrates, thus melting them. The liquid then continues up another portion of the apparatus, carrying entrained hydrocarbon vapors in the form of bubbles, which can easily be separated from the liquid. After a short startup procedure, the process and apparatus are substantially self-powered.

Apparatus for recovering gaseous hydrocarbons from

In situ (subsurface) methods and devices are described for releasing gaseous hydrocarbons and steam from solution in water or brine, from captured bubbles in formation pores, and from hydrate deposits. With geopressured brines the volume of the brine is reduced so that its volume is less than the sandstone pore volume which holds the brine; at this point the reservoir creates a gas cap of methane and steam which can be produced. Gas caps are formed in natural domes, artificial domes are developed, down-hole engines and pumps are powered both by in situ forces and by surface-generated forces; all are described.

Device for in situ recovery of gaseous hydrocarbons and steam

A method is described for circulating hydrostatically pressured or geopressured brines so that dissolved methane in the brines can be recovered within the wellpipe. All processes take place downhole or in the surrounding briny formations, and the circulation is powered wholly or in large part by the pressure on the brine and natural compressive forces in the formation.

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Los Alamos, NM, United States of America

Guy R Elliott