Uranium 233 Patents (Class 376/181)
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Patent number: 9368244Abstract: In an embodiment, a hybrid molten salt reactor includes a source of energetic neutrons, the energetic neutrons having a typical energy per neutron of 14 MeV or greater, a critical molten salt reactor, and a molten salt comprising a dissolved mixture of fissile actinides and fertile actinides. The molten salt circulates in a loop through the reactor vessel and around the source of energetic neutrons. The fissile actinides and fertile actinides sustain an exothermic nuclear reaction in which the actinides are irradiated by the energetic neutrons, the energetic neutrons inducing subcritical nuclear fission, and undergo critical nuclear fission when circulating through the critical molten salt reactor. A portion of the daughter neutrons generated by nuclear reactions are captured by the fertile actinides in the molten salt and induce transmutation of the fertile actinides into fissile actinides and sustain critical fission chain reactions in the molten salt reactor.Type: GrantFiled: April 23, 2014Date of Patent: June 14, 2016Inventor: Robert Daniel Woolley
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Publication number: 20150139379Abstract: A lightly hydrided/deuterated metallic plutonium-thorium fuel for use in a fast fission pool-type nuclear reactor cooled with liquid metal coolants, including lithium-7 lead eutectic, lead bismuth eutectic or lead. When so used, plutonium-239 is consumed, and merchantable heat is produced along with fissile uranium-233, which can be denatured with uranium-238 and used in light water reactors as fuel.Type: ApplicationFiled: December 23, 2014Publication date: May 21, 2015Inventor: Charles S. Holden
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Publication number: 20150078504Abstract: In an embodiment, a hybrid molten salt reactor includes a source of energetic neutrons, the energetic neutrons having a typical energy per neutron of 14 MeV or greater, a critical molten salt reactor, and a molten salt comprising a dissolved mixture of fissile actinides and fertile actinides. The molten salt circulates in a loop through the reactor vessel and around the source of energetic neutrons. The fissile actinides and fertile actinides sustain an exothermic nuclear reaction in which the actinides are irradiated by the energetic neutrons, the energetic neutrons inducing subcritical nuclear fission, and undergo critical nuclear fission when circulating through the critical molten salt reactor. A portion of the daughter neutrons generated by nuclear reactions are captured by the fertile actinides in the molten salt and induce transmutation of the fertile actinides into fissile actinides and sustain critical fission chain reactions in the molten salt reactor.Type: ApplicationFiled: April 23, 2014Publication date: March 19, 2015Inventor: Robert Daniel Woolley
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Patent number: 5774514Abstract: A method for producing energy from a nuclear fuel material contained in an enclosure, through a process of breeding of a fissile element from a fertile element of the fuel material via a .beta.-precursor of the fissile element and fission of the fissile element. A high energy particle beam is directed into the enclosure for interacting with heavy nuclei contained in the enclosure so as to produce high energy spallation neutrons. The neutrons thereby produced are multiplied in steady sub-critical conditions by the breeding and fission process. The breeding and fission process is carried out inside the enclosure.Type: GrantFiled: April 24, 1996Date of Patent: June 30, 1998Inventor: Carlo Rubbia
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Patent number: 5386439Abstract: During operation of a light water moderated and cooled nuclear reactor, rods varying the neutron energy spectrum are introduced into the core of the reactor in the course of a first phase of the cycle in order to reduce the ratio of the volume of moderator to the volume of fissile material in the core. In a second phase of the cycle the spectrum displacement rods are extracted. The rods are of a mixture of thorium energy neutrons. The rods may be of fertile material and--depleted uranium. The invention is of particular interest in PWRs.Type: GrantFiled: December 30, 1986Date of Patent: January 31, 1995Assignee: FramatomeInventors: Claude Leroy, Jean Paul Millot, Eric Gonse
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Patent number: 5037601Abstract: A nuclear power plant that is of a walk-away type with an encapsulated reaction core in a glass matrix pool having a reactive Thorium/U.sup.233 composition in a containment structure that radiates thermal energy for use in a closed gas cycle with a split path having a common compressor with an output that divides into a first path communicating with the thermal source and a second path communicating with an intercooler, the two paths combining in a turbine with an expander that discharges to a common collector for return to the compressor.Type: GrantFiled: August 23, 1990Date of Patent: August 6, 1991Inventor: Hector A. Dauvergne
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Patent number: 4663110Abstract: A fusion blanket includes a chamber wall, a multiplication section, an enrichment section and a reflector in radially outward succession, respectively. The chamber wall isolates the fusion reaction chamber from the remainder of the blanket. Fusion neutrons bombard atoms in the multiplication section to free further neutrons which are then available for breeding fuel. The enrichment section contains fertile fuel of sufficient dilution to maximize the enrichment rate and minimize fast fission. Materials may be included in the multiplication section and the enrichment section to reduce thermal neutron flux, thereby suppressing thermal fission. Additionally, tritium may be bred in both sections. The fertile material is exposed to neutron bombardment until the desired enrichment is achieved. The particles may be removed and mixed to minimize nonuniformities in enrichment. The particles may then be fabricated into fuel elements for fission reactors.Type: GrantFiled: May 21, 1985Date of Patent: May 5, 1987Assignee: GA Technologies Inc.Inventor: Edward T. Cheng
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Patent number: 4483816Abstract: A combination of passive and active neutron measurements which yields quantitative information about the isotopic composition of transuranic wastes from nuclear power or weapons material manufacture reactors is described. From the measurement of prompt and delayed neutron emission and the incidence of two coincidentally emitted neutrons from induced fission of fissile material in the sample, one can quantify .sup.233 U, .sup.235 U and .sup.239 Pu isotopes in waste samples. Passive coincidence counting, including neutron multiplicity measurement and determination of the overall passive neutron flux additionally enables the separate quantitative evaluation of spontaneous fission isotopes such as .sup.240 Pu, .sup.244 Cm and .sup.252 Cf, and the spontaneous alpha particle emitter .sup.241 Am.Type: GrantFiled: March 31, 1982Date of Patent: November 20, 1984Assignee: The United States of America as represented by the Department of EnergyInventors: John T. Caldwell, Walter E. Kunz, James D. Atencio
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Patent number: 4393510Abstract: The production of a novel nuclear fuel utilizing clean uranium 233 in combination with other nuclear materials is made possible by utilization of an equally novel reactor configuration and method of operation. Clean uranium 233 is produced from thorium in a light water reactor while utilizing discrete separation of the thorium being irradiated from the fissile fuel. This clean uranium 233 is then incorporated directly as fissile isotope enrichment into a new nuclear fuel which may be done without encountering the usual difficulties and hazards in the handling of uranium 233 or the expense and delays associated with gaseous diffusion enrichment. The thorium from this process may be directly reprocessed for reactor charging without radiation hazard also.Type: GrantFiled: July 1, 1976Date of Patent: July 12, 1983Assignee: Pacific Nuclear Fuels, Inc.Inventors: Linton W. Lang, Robert L. Stetson
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Patent number: 4381281Abstract: The production of a novel nuclear fuel, utilizing uranium 233 low in uranium 232 content in combination with other nuclear materials is made possible by utilization of an equally novel reactor configuration and method of operation. Uranium 233 is produced from thorium in a light water reactor (LWR) while utilizing discrete separation of the thorium being irradiated from the fissile fuel. This uranium 233 is then incorporated directly as fissile isotope enrichment into a new nuclear fuel which may be done without encountering the usual difficulties and hazards in the handling of uranium 233 or the expense and delays associated with gaseous diffusion enrichment. Thorium from this process may be directly reprocessed for reactor charging without radiation hazard also.Type: GrantFiled: May 4, 1981Date of Patent: April 26, 1983Assignee: Pacific Nuclear Fuels, Inc.Inventors: Linton W. Lang, Robert L. Stetson
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Patent number: 4362691Abstract: The production of a novel nuclear fuel, utilizing uranium 233 low in uranium 232 content in combination with other nuclear materials is made possible by utilization of an equally novel reactor configuration and method of operation. Uranium 233 is produced from thorium in a light water reactor (LWR) while utilizing discrete separation of the thorium being irradiated from the fissile fuel. This uranium 233 is then incorporated directly as fissile isotope enrichment into a new nuclear fuel which may be done without encountering the usual difficulties and hazards in the handling of uranium 233 or the expense and delays associated with gaseous diffusion enrichment. Thorium from this process may be directly reprocessed for reactor charging without radiation hazard also.Type: GrantFiled: January 14, 1980Date of Patent: December 7, 1982Assignee: Pacific Nuclear Fuels, Inc.Inventors: Linton W. Lang, Robert L. Stetson