Celebrity Inventors
Lawrence Welk, the bandleader who entertained millions of Americans over a generation of broadcasting his TV show, once received a patent: for a music-themed design of an ashtray.
PatentStorm News
Make the Most of Our Site
See this month's Top Inventors and Most Cited Patents.
Stay on top of the latest innovations by subscribing to an RSS feed.
Registered users: Manage your profile.
| Number | Title | Issue Date |
| 5500158 | UO2 pellet and method for production thereof A process for producing a UO2 pellet comprising the steps of producing UO2 powder in accordance with the ADU (ammonium diuranate) method or the AUC (ammonium uranyl carbonate) method, forming a compact of said UO2 powder, ... | 03/19/1996 |
| 5419886 | Method for generation of finely divided reactive plutonium oxide powder A method of preparing active, sinterable, finely-divided plutonium oxide (PuO2) powder from plutonium metal is disclosed. The process yields plutonium fissile material which can be easily blended to form a uniformly homogeneous powder for the f... | 05/30/1995 |
| 4873031 | Method of controlling the crystal grain size of uranium dioxide pellet A method of controlling the crystal grain size of UO2 pellets is disclosed, which comprises (1) providing an aqueous uranyl solution which is free of hydrofluoric acid and nitric acid and which contains uranyl fluoride (UO2 F2)... | 10/10/1989 |
| 4816187 | Binder system for the manufacture of nuclear pellets, and the method and product thereof A fugitive binder composition for compression molding uranium dioxide nuclear fuel comprising the reaction product of a strongly alkali water solution of a diamine and oxalate ions with uranium oxide which is free of carbonates and carbamates, and having ... | 03/28/1989 |
| 4774051 | Sintered nuclear fuel compact and method for its production A sintered nuclear fuel compact of UO2 or the mixed oxides (U, Pu)O2 and (U, Th)O2, with which reactivity losses in a nuclear reactor having relatively long fuel element cycles are avoided, has in its sintered matrix neutr... | 09/27/1988 |
| 4720370 | Nuclear reactor fuel structure containing uranium alloy wires embedded in a metallic matrix plate A flat or curved plate structure, to be used as fuel in a nuclear reactor, comprises elongated fissionable wires or strips embedded in a metallic continuous non-fissionable matrix plate. The wires or strips are made predominantly of a malleable uranium al... | 01/19/1988 |
| 4687605 | Manufacturing automation system for nuclear fuel rod production An automated fuel rod production system includes a radioactive powder fabrication and processing stage, a pellet fabrication stage, a pellet processing stage, a tube preparation stage and a fuel rod fabrication and inspection stage, all of which provide a... | 08/18/1987 |
| 4671904 | Method for producing oxidic sintered nuclear fuel bodies UO2 base powder exhibiting any specific surface and crystallite diameter properties is mixed with rare earth (SE) oxide-containing powder, the particles of which exhibit at least in one surface layer, a crystal lattice of the fluorite type, wit... | 06/09/1987 |
| 4670198 | Binder system for the manufacture of nuclear fuel pellets, and the method and product thereof A reproducible method and stable binder composition for preserving the induced plasticity of a particulate ceramic material admixture comprising uranium dioxide and a fugitive binder, and product thereof, for subsequent compaction by compressing molding i... | 06/02/1987 |
| 4668444 | Process for the production of isotrophic spherical fuel or absorber elements for high temperature reactors Substantially isotropic spherical fuel and absorber elements for high temperature reactors are produced by molding corresponding fuel particles and graphite molding compositions. There is used as graphite molding powder a mixture of graphitized granules o... | 05/26/1987 |
| 4666639 | Process for the production of spherical fuel elements To produce spherical fuel or absorber elements for high temperature reactors a mixture of coated nuclear fuel or absorber particles and graphite molding composition is molded into spheres, carbonized in a furnace having gas flushing and calcined in a vacu... | 05/19/1987 |
| 4634571 | Process for the production of plate-shaped fuel elements for research reactors For the production of plate-shaped fuel elements for research reactors having charges of more than 26 volume % of uranium compound in the aluminum matrix according to the known picture frame technique, 0.01 to 0.3 mm thick aluminum layers are applied by r... | 01/06/1987 |
| 4578229 | Method for the manufacture of oxidic sintered nuclear fuel bodies Method for the manufacture of oxidic nuclear fuel bodies by a heat treatment of blanks obtained from UO2 starting power or a mixture of UO2 and PuO2 starting powder at a treatment temperature in the range of 1000° C. to 1... | 03/25/1986 |
| 4528130 | Method for dissolving hard-to-dissolve thorium and/or plutonium oxides Method for dissolving hard-to-dissolve thorium and/or plutonium oxides, especially dioxides such as ThO2, PuO2 or (U/Pu)O2 mixed oxides by heating the oxides in a hermetically sealed vessel in fluoride-free nitric acid. Th... | 07/09/1985 |
| 4522769 | Method for the manufacture of nuclear fuel products An improved method for compression molding typically brittle, particulate ceramic materials comprising uranium dioxide in the manufacture of nuclear fuel products.... | 06/11/1985 |
| 4460522 | Method of producing low density oxide fuel pellet A method of producing an oxide fuel pellet having a low density is provided which comprises adding a manganese compound to an oxide fuel powder selected from a group consisting of uranium dioxide powder and a mixed powder of uranium dioxide and plutonium ... | 07/17/1984 |
| 4427579 | Method of producing fugitive binder-containing nuclear fuel material A nuclear fuel material green body of density from about 30 to 70% of theoretical density having tensile strenght and plasticity adequate to maintain the integrity of the body during processing leading to ultimate sintered condition is produced by adding ... | 01/24/1984 |
| 4397778 | Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water a... | 08/09/1983 |
| 4309305 | In vitro removal of actinide (IV) ions A compound of the formula: ##STR1## wherein X is hydrogen or a conventional electron-withdrawing group, particularly --SO3 H or a salt thereof; n is 2, 3, or 4; m is 2, 3, or 4; and p is 2 or 3. The present compounds are useful as specific... | 01/05/1982 |
| 3943210 | Preparation of metal hydride bodies by improved powder metallurgy process A method of fabricating a group IVB metal hydride body having a hydrogen content of at least 55 atom percent and a high density, which comprises mixing together powders of said metal hydride having less than about 55 atom percent hydrogen with powders of ... | 03/09/1976 |
