General Electric Company

Larry Allen Divins

Paul William Buckley

Paul Russell Wilson

Allen Wai Yee Ko

Larry E Short

Qiwei He

Slawomir Rubinsztajn

Ganesh Kailasam

John Aibangbee Osaheni

John P Banevicius

Stanlee Teresa Buddle

William Lee Gately

Michael Lee White

Robert G Stank

Robert L Tatterson

Harold L Runion

Polymer are removed from organic solvent-polymer mixtures by preparing a liquid-liquid dispersion of finely dispersed solvent droplets containing polymer in water, adding this liquid-liquid dispersion to a stirred vessel containing water or other suitable liquid and rapidly evaporating the solvent to produce a slurry of the polymer in a liquid from which the solid polymer particles are recovered.

Polycarbonate isolation through homogenization devolatization

Inorganic powder, preferably fumed silica, is rendered hydrophobic by treatment with a silylating agent in the presence of a third reagent selected from the group consisting of protonic acids, especially those having a boiling point at atmospheric pressure up to 120.degree. C., preferably formic acid, and linear phosphonitrilic halides, preferably linear phosphonitrilic chlorides.

Method for rendering inorganic powder hydrophobic

Silicon fines which have been recovered from an organochlorosilane reactor are treated with HCl or elemental chlorine at an elevated temperature to salvage chlorosilane and metal salt values. Passivation is also achieved.

Method of passivating organochlorosilane reactor fines and salvaging

An improved process for producing powdered uranium dioxide from a solution of uranyl nitrate which is suitable for the manufacture of fuel for nuclear reactors. The process is continuous and comprises an incremental precipitation of soluble uranyl nitrate with ammonium hydroxide which is interrupted with an intermediate aging period. The precipitate of ammonium uranate solids is dried and thermally converted to a powdered oxide of uranium.

Continuous process for the production of powdered uranium dioxide from

Process for recovering compounds of enriched nuclear fuel from scrap materials is disclosed. The process yields an acid solution with the nuclear fuel dissolved therein. Except for spent filter media, the scrap materials are calcined to produce an oxidized material, which is reduced to a particulate material and leached in an acid bath that contains some recycled acid to yield an acid solution of the nuclear fuel material. The scrap materials comprised of spent filter media are mulched and contacted with the acid solution. The insoluble materials are separated from the acid solution, and at least a portion of the acid solution is recycled to the leaching step, while the remainder of the acid solution is collected for subsequent treatment to recover the dissolved nuclear fuel material. Apparatus for performing the foregoing process is also disclosed.

Apparatus for recovering nuclear fuel from scrap material

A process for recovering compounds of enriched nuclear fuel from scrap materials is disclosed. The process yields an acid solution with the nuclear fuel dissolved therein. Except for spent filter media, the scrap materials are calcined to produce an oxidized material, which is reduced to a particulate material and leached in an acid bath that contains some recycled acid to yield an acid solution of the nuclear fuel material. The scrap materials comprised of spent filter media are mulched and contacted with the acid solution. The insoluble materials are separated from the acid solution, and at least a portion of the acid solution is recycled to the leaching step, while the remainder of the acid solution is collected for subsequent treatment to recover the dissolved nuclear fuel material. Apparatus for performing the foregoing process is also disclosed.

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Terre Haute, IN, United States of America

Larry Allen Divins