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Pizza Pie With Concentric Rings of Crust
A pizza mold for forming a plurality of concentric raised ridges of dough (i.e., crust) on the surface of a pizza pie.
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| Number | Title | Issue Date |
| 7628970 | Method of preparing feedstock liquid, method of preparing uranyl nitrate solution, and method of preparing polyvinyl alcohol solution The object of the present invention is to provide a feedstock liquid, from which fuel kernels with good quality can be produced, and a method of preparing the feedstock liquid. The present invention provides a feedstock liquid with a viscosity from 4.0×10−2 ... | 12/08/2009 |
| 7374940 | Method and apparatus for determining the progress of a uranium oxyfluoride conversion reaction in a furnace and for controlling the reaction A substance in a condensed state, for example a powdered solid, is in continuous movement in the longitudinal direction (6) of a furnace (4, 5). A reactive gas mixture is brought into contact with the substance in the condensed state. A plurality of sa... | 05/20/2008 |
| 7357910 | Method for producing metal oxide nanoparticles Method for producing metal oxide nanoparticles. The method includes generating an aerosol of solid metallic microparticles, generating plasma with a plasma hot zone at a temperature sufficiently high to vaporize the microparticles into metal vapor, and directing the... | 04/15/2008 |
| 7323153 | Reprocessing method by fluoride volatility process using fractional distillation Fluorine or a fluorine compound is subjected to a reaction with a spent oxide fuel to produce fluorides of uranium and plutonium, and recovering the fluorides using a difference in volatility behavior. The method includes steps of: subjecting a mixture of UO2 | 01/29/2008 |
| 7294291 | Ceramicrete stabilization of U-and Pu-bearing materials A method of stabilizing nuclear material is disclosed. Oxides or halides of actinides and/or transuranics (TRUs) and/or hydrocarbons and/or acids contaminated with actinides and/or TRUs are treated by adjusting the pH of the nuclear material to not less than about 5... | 11/13/2007 |
| 7208129 | Reprocessing method by fluoride volatility process using solid-gas separation Fluorine or a fluorine compound is subjected to a reaction with a spent oxide fuel to produce fluorides of uranium and plutonium, and the fluorides are recovered using a difference in volatility behavior. The spent oxide fuel is subjected to a reaction with an HF ga... | 04/24/2007 |
| 7195745 | Method of preparing a product based on phosphate of thorium and/or actinide(s) The invention relates to a process for the preparation of a product based on a phosphate of at least one element M(IV), for example of thorium and/or of actinide(IV)(s). This process comprises the following stages: a) mixing... | 03/27/2007 |
| 7172741 | Method for reprocessing spent nuclear fuel It is an object to increase a reprocessing speed of spent nuclear fuel and to obtain uranium having a high purity and a plutonium mixture reusable as it is at a low cost through a simple procedure. The spent nuclear fuel 1 is subjected to fluorination ... | 02/06/2007 |
| 7011798 | Process for reprocessing spent nuclear fuels by utilizing phenomenon of cocrystallization A reprocessing process of spent nuclear fuels for roughly separating U and U—Pu from FP, TRU and the like in a nitric acid solution of spent nuclear fuels by utilizing phenomenon of cocrystallization of hexavalent U and Pu. For example, spent nuclear fuels are she... | 03/14/2006 |
| 6800262 | Method for making a uranium chloride salt product The subject apparatus provides a means to produce UCl3 in large quantities without incurring corrosion of the containment vessel or associated apparatus. Gaseous Cl is injected into a lower layer of Cd where CdCl2 is formed. Due to is lower den... | 10/05/2004 |
| 6770256 | Process for synthesizing metal oxides and metal oxides having a perovskite or perovskite-like crystal structure Metal oxides having a perovskite or perovskite-like crystal structure are prepared by a process comprising subjecting a mixture of starring powders to a high energy milling sufficient to induce chemical reaction of the components and thereby directly mechanosynthesi... | 08/03/2004 |
| 6482387 | Processes for preparing mixed metal oxide powders Described are preferred polymerized organic-inorganic processes for producing mixed metal oxide powders suitable for use in the ceramics and related industries. The preferred processes employ a non-chelating polymer such as polyvinyl alcohol or polyalkyle... | 11/19/2002 |
| 6468495 | Treatment of molten salt reprocessing wastes A method of removing from a metal salt ionic species contained therein involves contacting the metal salt with an ionic liquid to dissolve the metal salt, the ionic species or both. At least in the case where both the metal salt and the ionic species are ... | 10/22/2002 |
| 6303090 | Conversion of depleted uranium hexafluoride to a solid uranium compound A process for converting UF6 to a solid uranium compound such as UO2 and CaF. The UF6 vapor form is contacted with an aqueous solution of NH4 OH at a pH greater than 7 to precipitate at least some solid uranium ... | 10/16/2001 |
| 6224841 | Catalytic oxidation A process for the destructive oxidation of organic compounds containing one or more optionally substituted hydrocarbon groups, comprising the step of carrying out the oxidation in the presence of a catalyst comprising uranium oxide in which the average ox... | 05/01/2001 |
| 6207130 | Metal-exchanged carboxylato-alumoxanes and process of making metal-doped alumina A method has been developed for the solution-based metal exchange of carboxylato-alumoxanes [Al(O)x (OH)y (O2 CR)z ]n with a wide range of metal cations. Metal-exchanged carboxylato-alumoxanes are new... | 03/27/2001 |
| 6033636 | Method of recovering uranium and transuranic elements from spent nuclear fuel The steps for recovering uranium and transuranic elements are simplified, and the generation of waste solvent and waste materials is suppressed. Spent nuclear fuel is dissolved in nitric acid (S100) and the resulting solution is subjected to electrolytic ... | 03/07/2000 |
| 5935528 | Multicomponent fluid feed apparatus with preheater and mixer for a high temperature chemical reactor A multicomponent fluid feed apparatus is disclosed that independently preheats and then mixes two or more fluid streams being introduced into a high temperature chemical reactor to promote more rigorous and complete reactions using assemblies of inert tub... | 08/10/1999 |
| 5885465 | Method of separating short half-life radionuclides from a mixture of radionuclides The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixtur... | 03/23/1999 |
| 5881359 | Metal and fluorine values recovery from fluoride salt matrices The process for converting feed materials of high mineral content containing primary metal values and fluorine values to the primary metal or useful compounds thereof and to fluorine values or useful compounds thereof, wherein the feed materials constitut... | 03/09/1999 |
| 5757087 | Oxidation of uranium hexafluoride The present invention provides a process for the oxidation of uranium hexafluoride by injecting the uranium hexafluoride and an oxidant gas together into a reaction vessel to form a plume characterized in that a plurality of the said plumes are formed tog... | 05/26/1998 |
| 5735932 | Process for the conversion of uranium oxide to uranium metal and uranium alloys A process for preparing uranium metal or alloy thereof suitable for use in a metal-based uranium enrichment plant or other use requiring a superdense metal comprising providing a molten metal bath containing the alloy metal and feeding uranium oxide and a... | 04/07/1998 |
| 5723837 | Uranium hexafluoride purification A method of purifying a UF6 gas stream which comprises irradiating the UF6 gas stream with laser radiation in a vessel in order to selectively convert fluoride impurities in the gas stream to involatile products, removing the purifie... | 03/03/1998 |
| 5698173 | Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors A method for purifying metallic alloys of uranium for use as nuclear reactor fuels in which the metal alloy is first converted to an oxide and then dissolved in nitric acid. Initial removal of metal oxide impurities not soluble in nitric acid is accomplis... | 12/16/1997 |
| 5590391 | Down-blending of fissionable material A process for reducing the concentration of fissionable uranium containing components of a feed material to below a target concentration level, the process having the steps of providing the feed material as an aqueous system of high-enriched uranyl nitrat... | 12/31/1996 |
| 5516496 | Metal and fluorine values recovery from fluoride salt matrices The process for converting feed materials of high mineral content and substantial radioactivity levels to concentrated radionuclide products of high radioactivity levels and to other products of discard or very low radioactivity levels, wherein the feed m... | 05/14/1996 |
| 5419880 | Controlled acid-strong acid strip process A controlled multi-stage process for the stripping of uranium includes the introduction at one end of a solvent extraction device a uranium loaded organic solution. A concentrated stripping acidic aqueous solution is introduced at the other end of the sol... | 05/30/1995 |
| 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 |
| 5411722 | Compact reaction cell for homogenizing and down-blanding highly enriched uranium metal The invention is a specialized reaction cell for converting uranium metal to uranium oxide. In a preferred form, the reaction cell comprises a reaction chamber with increasing diameter along its length (e.g. a cylindrical chamber having a diameter of abou... | 05/02/1995 |
| 5405590 | Off-gas scrubber system An off-gas quencher and solid recovery scrubber unit includes a wet flue gas scrubber which has the dual responsibilities of lowering the temperature of the inlet hot gas entering through the scrubber and trapping contaminants from the gas stream into the... | 04/11/1995 |
| 5336450 | Process to remove rare earth from IFR electrolyte The invention is a process for the removal of rare earths from molten chloride electrolyte salts used in the reprocessing of integrated fast reactor fuel (IFR). The process can be used either continuously during normal operation of the electrorefiner or a... | 08/09/1994 |
| 5205999 | Actinide dissolution A process for the treatment of a material which is or is suspected to contain or carry one or more actinides or compounds thereof to dissolve such actinides or compounds comprises contacting the material with an aqueous solution having a pH in the range 5... | 04/27/1993 |
| 5188809 | Method for separating coke from a feed mixture containing zirconium and radioactive materials by flotation process A process for separating a feed mixture of zirconium and petroleum coke containing traces amount of radioative materials by flotation process utilizing a plurality of flotation cells. The process comprises grinding the feed mixture, slurrying the ground f... | 02/23/1993 |
| 5164050 | Method of obtaining uranium from oxide using a chloride process A method of obtaining uranium metal from an oxidized uranium compound, characterized in that the oxidized compound is treated with chlorine and carbon at a first stage, to obtain a chloride which is reduced by electrolysis or metallothermy using a reducin... | 11/17/1992 |
| 5160367 | Salt transport extraction of transuranium elements from lwr fuel A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl2 and a Cu--... | 11/03/1992 |
| 5147616 | Magnesium transport extraction of transuranium elements from LWR fuel A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl2 and a U-Fe... | 09/15/1992 |
| 5141723 | Uranium chloride extraction of transuranium elements from LWR fuel A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in... | 08/25/1992 |
| 5112581 | Method of separating uranium and plutonium from mixed solution containing uranium and plutonium A method of separating uranium and plutonium from a mixed solution containing uranium nitrate and plutonium nitrate comprises cooling the mixed solution to a temperature ranging from -40° to -20° C. to thereby selectively precipitate uranyl nitrate. The... | 05/12/1992 |
| 5096545 | Plutonium recovery from spent reactor fuel by uranium displacement A process for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of pluton... | 03/17/1992 |
| 5085834 | Method for separating by using crown compounds plutonium from uranium and from fission products in the initial stages for the reprocessing of irradiated nuclear fuels A method for separating plutonium from uranium and from fission products with the aid of crown ether compounds comprising contacting an aqueous solution A0 containing Pu, U and fission products with an organic solvent O0 containing at least one crown ethe... | 02/04/1992 |
