Uranium Pechiney
17Patents
0Active
17Granted
31Portfolio score
Filing activity: Sep 21, 1983 → Jun 21, 1993
Most-cited patents
| Patent | Title | Area | Cited by | Status |
|---|---|---|---|---|
| US4852645A | Thermal transfer layer | Emerging Cross-Sectional Technologies | 38 | Expired |
| US5268947A | Nuclear fuel elements comprising a trap for fission products based on oxide | Emerging Cross-Sectional Technologies | 18 | Expired |
| US5340447A | Process for the selective electrofluorination of alloys or metallic mixtures based on uranium | Chemistry; Metallurgy | 18 | Expired |
| US4524001A | Method of purifying uraniferous aqueous solutions | Chemistry; Metallurgy | 6 | Expired |
| US4634580A | Process for the purification of wet-process phosphoric acid by removal of cadmium | Emerging Cross-Sectional Technologies | 6 | Expired |
| US5272740A | Agent for trapping the radioactivity of fission products which are generated in a nuclear fuel element | Emerging Cross-Sectional Technologies | 4 | Expired |
| US4971734A | Method of making nuclear fuel pellets, comprising producing and using pourable, frittable powders obtained directly by precipitation of peroxides | Emerging Cross-Sectional Technologies | 4 | Expired |
| US4744960A | Process for the separation of rare earths and uranium of a UF.sub.4 concentrate and for putting them into useful form | Chemistry; Metallurgy | 3 | Expired |
| US4675166A | Process for the selective separation of uranium, zirconium and/or hafnium and/or molybdenum from a carbonated aqueous solution containing same | Chemistry; Metallurgy | 3 | Expired |
| US5091120A | Process for obtaining UO.sub.2 fuel pellets from metallic U without producing any effluent | Emerging Cross-Sectional Technologies | 3 | Expired |
| US4643882A | Process for recovery by a solvent of the uranium present in phosphoric acid | Chemistry; Metallurgy | 1 | Expired |
| US4758411A | Process for the recovery in the form of tetravalent fluoride of uranium extracted from phosphate-bearing solutions with the addition of metalic ions | Emerging Cross-Sectional Technologies | 1 | Expired |
| US4891192A | Process for the purification of traces of radioactive elements generated during the storage of uranium resulting from the reprocessing of irradiated nuclear fuels | Physics | 1 | Expired |
| US4613361A | High-temperature pretreatment by means of an alkaline aqueous solution of ores having an argillaceous gangue containing at least one usable element | Emerging Cross-Sectional Technologies | 1 | Expired |
| US4714596A | Process for the recovery in the form of tetravalent fluoride of uranium extracted from phosphate-bearing solutions | Emerging Cross-Sectional Technologies | 1 | Expired |
| US4649030A | Process for the purification of uraniferous and/or molybendiferous amino organic solutions which contain zirconium and/or hafnium among other impurities | Emerging Cross-Sectional Technologies | 0 | Expired |
| US4702820A | Pretreatment by alkaline wetting and holding at temperature of natural materials having an argillaceous gangue containing combustible elements | Chemistry; Metallurgy | 0 | Expired |
Source: USPTO / EPO open patent data. Counts and citation impact are objective bibliographic measures.