Patents by Inventor Charles W. Forsberg
Charles W. Forsberg has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).
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Publication number: 20110067398Abstract: Systems and methods for concentrating and storing solar energy are provided. A solar energy receiver for use with the systems and methods may include a container for holding a solar absorption material, such as a phase change material, and a cooled cover disposed above the container for condensing and collecting vaporized phase change material collected along an underside of the cover.Type: ApplicationFiled: September 20, 2010Publication date: March 24, 2011Applicant: Massachusetts Institute of TechnologyInventors: Alexander H. Slocum, Jacopo Buongiorno, Charles W. Forsberg
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Patent number: 7666387Abstract: The present invention is directed to a thermochemical method for the production of hydrogen from water. The method includes reacting a multi-valent metal oxide, water and a carbonate to produce an alkali metal-multi-valent metal oxide compound, carbon dioxide, and hydrogen.Type: GrantFiled: October 19, 2007Date of Patent: February 23, 2010Assignee: UT-Battelle, LLCInventors: Jack L Collins, Leslie R Dole, Juan J Ferrada, Charles W Forsberg, Marvin J Haire, Rodney D Hunt, Benjamin E Lewis, Jr., Raymond G Wymer
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Publication number: 20090104111Abstract: The present invention is directed to a thermochemical method for the production of hydrogen from water. The method includes reacting a multi-valent metal oxide, water and a carbonate to produce an alkali metal-multi-valent metal oxide compound, carbon dioxide, and hydrogen.Type: ApplicationFiled: October 19, 2007Publication date: April 23, 2009Applicant: UT-BATTELLE, LLCInventors: Jack L. Collins, Leslie R. Dole, Juan J. Ferrada, Charles W. Forsberg, Marvin J. Haire, Rodney D. Hunt, Benjamin E. Lewis, JR., Raymond G. Wymer
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Patent number: 6811745Abstract: A method to produce annular-shaped, metal-clad cermet components directly produces the form and avoids multiple fabrication steps such as rolling and welding. The method includes the steps of: providing an annular hollow form with inner and outer side walls; filling the form with a particulate mixture of ceramic and metal; closing, evacuating, and hermetically sealing the form; heating the form to an appropriate temperature; and applying force to consolidate the particulate mixture into solid cermet.Type: GrantFiled: January 16, 2003Date of Patent: November 2, 2004Assignee: UT-Battelle, LLCInventors: Charles W. Forsberg, Vinod K. Sikka
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Publication number: 20040141866Abstract: A method to produce annular-shaped, metal-clad cermet components directly produces the form and avoids multiple fabrication steps such as rolling and welding. The method includes the steps of providing an annular hollow form with inner and outer side walls; filling the form with a particulate mixture of ceramic and metal; closing, evacuating, and hermetically sealing the form; heating the form to an appropriate temperature; and applying force to consolidate the particulate mixture into solid cermet.Type: ApplicationFiled: January 16, 2003Publication date: July 22, 2004Inventors: Charles W. Forsberg, Vinod K. Sikka
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Patent number: 5961679Abstract: A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes.Type: GrantFiled: November 5, 1997Date of Patent: October 5, 1999Assignee: U. S. Department of EnergyInventor: Charles W. Forsberg
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Patent number: 5832392Abstract: A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.Type: GrantFiled: April 15, 1997Date of Patent: November 3, 1998Assignee: The United States of America as represented by the United States Department of EnergyInventor: Charles W. Forsberg
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Patent number: 5613241Abstract: A process for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass.Type: GrantFiled: May 18, 1995Date of Patent: March 18, 1997Assignee: Lockheed Martin Energy Systems, Inc.Inventors: Charles W. Forsberg, Edward C. Beahm, George W. Parker
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Patent number: 5461185Abstract: The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.Type: GrantFiled: April 19, 1994Date of Patent: October 24, 1995Inventors: Charles W. Forsberg, Edward C. Beahm, George W. Parker
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Patent number: 5410577Abstract: A core-melt source reduction system for ending the progression of a molten core during a core-melt accident and resulting in a stable solid cool matrix. The system includes alternating layers of a core debris absorbing material and a barrier material. The core debris absorbing material serves to react with and absorb the molten core such that containment overpressurization and/or failure does not occur. The barrier material slows the progression of the molten core debris through the system such that the molten core has sufficient time to react with the core absorbing material. The system includes a provision for cooling the glass/molten core mass after the reaction such that a stable solid cool matrix results.Type: GrantFiled: November 4, 1993Date of Patent: April 25, 1995Assignee: Martin Marietta Energy Systems, Inc.Inventors: Charles W. Forsberg, Edward C. Beahm, George W. Parker
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Patent number: 5360056Abstract: A passive cooling system for cooling an enclosure only when the enclosure temperature exceeds a maximum standby temperature comprises a passive heat transfer loop containing heat transfer fluid having a particular thermodynamic critical point temperature just above the maximum standby temperature. An upper portion of the heat transfer loop is insulated to prevent two phase operation below the maximum standby temperature.Type: GrantFiled: July 28, 1993Date of Patent: November 1, 1994Assignee: Martin Marietta Energy Systems, Inc.Inventor: Charles W. Forsberg
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Patent number: 5098645Abstract: A single canister process container for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining their integrity at temperature necessary to oxide the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container.Type: GrantFiled: March 6, 1991Date of Patent: March 24, 1992Assignee: The United States of America as represented by the United States Department of EnergyInventor: Charles W. Forsberg
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Patent number: 5076999Abstract: A passive decay-heat removal system for a water-cooled nuclear reactor employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated box located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it will become exposed to steam. Vapor produced in the evaporator passes upward to the condenser above the normal water level. In operation, condensation in the condenser removes heat from the system, and the condensed liquid is returned to the evaporator. The system is disposed such that during normal reactor operations where the water level is at its usual position, very little heat will be removed from the system, but during emergency, low water level conditions, substantial amounts of decay heat will be removed.Type: GrantFiled: October 10, 1990Date of Patent: December 31, 1991Assignee: The United States of America as represented by the United States Department of EnergyInventor: Charles W. Forsberg
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Patent number: 4666654Abstract: A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (non-borated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant.Type: GrantFiled: February 19, 1985Date of Patent: May 19, 1987Assignee: The United States of America as represented by the United States Department of EnergyInventor: Charles W. Forsberg
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Patent number: 4106154Abstract: An adhesive applicator device including an elongated shaft having a bifurcated end portion and a handle secured thereto at its end opposite the bifurcated end portion. A porous resilient applicator pad is pressed into the bifurcation in the bifurcated portion of the shaft, and includes a central pad portion disposed between the portions of the shaft defining the bifurcation, and a pair of spaced adhesive applicator portions disposed on opposite sides of the central pad portion and exposed to facilitate application of adhesive from the outer peripheral surface of the pad to an object in contact therewith.Type: GrantFiled: May 13, 1976Date of Patent: August 15, 1978Assignee: Indian Head Inc.Inventor: Charles W. Forsberg
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Patent number: 3966334Abstract: An adhesive applicator device including an elongated shaft x-shaped in section formed by the intersection of a pair of webs at a right angle. The webs have tapered end edges, so that the shaft is characterized in having a point at one end thereof where the tapered edges of the webs converge. Each web has a plurality of spaced V-shaped notches therein. The notches extend into the web in the direction of the tapered end edges, with the innermost portion of each notch nearer to the tapered edge of the web than to the opening of the respective notch. At the end of the shaft opposite its pointed end, the shaft is secured to a mounting plate. Pressed over the shaft by extension of the intersecting webs into a slot of x-shaped cross section formed therein is a cylindrical applicator pad formed of a cellular porous resilient material.Type: GrantFiled: February 6, 1975Date of Patent: June 29, 1976Assignee: Indian Head Inc.Inventor: Charles W. Forsberg