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公开(公告)号：US20220246314A1
公开(公告)日：2022-08-04
申请号：US17167139
申请日：2021-02-04
申请人： Marshall G. Millett
发明人： Marshall G. Millett
摘要： 210Pb and 227Ac are used in thermal energy production as precursor isotopes, which have been isolated and are allowed to age to the point of secular equilibrium with their progeny, referring to the decay product isotopes in the radioactive decay chain of each. Both 210Pb and 227Ac are in the radioactive decay chains of naturally occurring uranium isotopes, and are each subject to their own natural radioactive decay. While not particularly energetic through their own decay, they (1) are separable from their parent isotopes or may be created in a reactor, (2) have half-lives of around 22 years, and (3) are precursors (natural radioactive decay parents) to subsequent rapid and energetic decay processes. These two isotopes can offer significant advantages as RPS fuel compared to the currently used 238Pu.
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公开(公告)号：US20210225532A1
公开(公告)日：2021-07-22
申请号：US16306403
申请日：2017-12-25
发明人： Boris Yakovlevich ZIL'BERMAN , Nikolaj Dmitrievich GOLETSKIJ , Nikita Vladimirovich KOVALEV , Andrej Borisovich SINYUKHIN
IPC分类号： G21C3/58
摘要： The fuel of NPPs on thermal neutrons. A fuel composition is proposed, which includes a mixture of regenerated plutonium and enriched uranium in the form of oxides, in which the enriched natural uranium is used as enriched uranium as well as regenerated plutonium, with a ratio of components, determined by the energy potential, equal to the potential of freshly prepared NPP fuel from enriched natural uranium, which provides the loading of the reactor core up to 100%. Possible options of the specified components are claimed, including unlimited cycling of the secondary regenerated plutonium and uranium. The use of the proposed composition makes it possible to use of the uranium and plutonium energy potential at maximum level, including accumulated SNF, and sharply reduce the volume of warehouses, up to their decommissioning, as well as significantly simplify the logistics and technology of manufacturing nuclear fuel from recycled materials.
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公开(公告)号：US20210020324A1
公开(公告)日：2021-01-21
申请号：US16722660
申请日：2019-12-20
申请人： Texas Thorium, LLC
发明人： Lin Shao , Yassin A. Hassan
摘要： A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example of the disclosed method includes the steps of providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing a nucleus capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level and generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. In the example, the externally generated proton beam is directed into the vessel such that at least some protons forming the beam will interact with an atom forming a part of the at least one salt contained in the vessel to causing interaction between the externally generated proton beam and the at least one salt contained in the vessel to produce (p, n) reactions resulting in the generation of neutrons within the vessel and an absorption reaction involving the generated neutrons and Thorium within the vessel. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton's interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases. the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.
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公开(公告)号：US20210020323A1
公开(公告)日：2021-01-21
申请号：US16554264
申请日：2019-08-28
申请人： Texas Thorium, LLC
发明人： Lin Shao , Yassin A. Hassan
摘要： A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example includes the steps of providing a vessel containing a molten salt fuel, generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton's interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.
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5.发明授权公开(公告)号：US10685757B2
公开(公告)日：2020-06-16
申请号：US15476870
申请日：2017-03-31
发明人： Jeffrey A. Katalenich , Bruce D. Reid , Robert O. Gates , Andrew W. Prichard , Bruce E. Schmitt , Jim Livingston
摘要： Reactor target assemblies are provided that can include a housing defining a perimeter of at least one volume and Np or Am spheres within the one volume. Reactor assemblies are provided that can include a reactor vessel and a bundle of target assemblies within the reactor vessel, at least one of the target assemblies comprising a housing defining a volume with Np or Am spheres being within the volume. Irradiation methods are also provided that can include irradiating Np or Am spheres within a nuclear reactor, then removing the irradiated spheres from the reactor and treating the irradiated spheres.
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公开(公告)号：US20200027582A1
公开(公告)日：2020-01-23
申请号：US16529425
申请日：2019-08-01
申请人： X-ENERGY, LLC
摘要： Nuclear fuel elements may include: a fuel zone including fuel particles disposed in parallel layers in a matrix including graphite powder; and a shell comprising graphite and surrounding the fuel zone. The fuel particles may include fissile particles, burnable poison particles, breeder particles, or a combination thereof. The fuel zone may include a central region and a peripheral region surrounding the central region, and a fuel particle density of the peripheral region may be greater than a fuel particle density of the central region.
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公开(公告)号：US20170221590A1
公开(公告)日：2017-08-03
申请号：US15518920
申请日：2015-10-12
申请人： THOR ENERGY AS
CPC分类号： G21C3/328 , G21C3/045 , G21C3/16 , G21C3/326 , G21C3/58 , G21C3/623 , G21C7/005 , G21C7/06 , Y02E30/31 , Y02E30/38 , Y02E30/39
摘要： The present invention concerns a fuel assembly for a nuclear power boiling water reactor. The fuel assembly comprises fuel rods. At least 95% of the fuel rods comprise nuclear fuel material in the form of U enriched in 235U. At least 20% of the fuel rods belong to a first set of fuel rods. The fuel rods in this first set comprise both U enriched in 235U and Th. The first set comprises a first and a second subset of fuel rods. The ratio, with regard to weight, between Th and U, in each fuel rod of said first subset, is higher than the ratio, with regard to weight, between Th and U, in each fuel rod of said second subset. The invention also concerns a nuclear power boiling water reactor and a manner of operating such a reactor.
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8.发明授权Sintered nuclear fuel body and method for producing a sintered nuclear fuel body 失效烧结核燃料体及烧结核燃料体的制造方法
公开(公告)号：US5894501A
公开(公告)日：1999-04-13
申请号：US893820
申请日：1997-07-11
申请人： Wolfgang Doerr , Harald Cura , Gerhard Gradel
发明人： Wolfgang Doerr , Harald Cura , Gerhard Gradel
CPC分类号： G21C3/623 , Y02E30/38 , Y10S376/901
摘要： A sintered nuclear fuel body includes (U, Pu)O.sub.2 mixed crystals having a mean particle size in a range from 7.5 .mu.m to 50 .mu.m. This sintered nuclear fuel body has a high retention capacity for fission gas in a power reactor. In order to produce the sintered nuclear fuel body by sintering a body in a hydrogen-containing sintering atmosphere, a powered substance selected from the group consisting of aluminum oxide, titanium oxide, niobium oxide, chromium oxide, aluminum stearate, aluminum distearate and aluminum tristearate is added to the starting powder for the body. As an alternative or in addition, the body made from the starting powder is sintered during a holding period of 10 minutes to 8 hours at a sintering temperature of 1400.degree. C. to 1800.degree. C. in a hydrogen-containing sintering atmosphere, initially with an oxygen partial pressure of 10.sup.-10 to 10.sup.-20 bar and then from 10.sup.-8 to 10.sup.-10 and then cooled in a hydrogen-containing atmosphere having an oxygen partial pressure of 10.sup.-10 to 10.sup.-20 bar.
摘要翻译： 烧结核燃料体包括（U，Pu）O 2混合晶体，其平均粒度在7.5μm至50μm的范围内。 这种烧结核燃料体在动力反应堆中具有高裂变气体的保留能力。 为了通过在含氢烧结气氛中烧结体来生产烧结核燃料体，选自氧化铝，氧化钛，氧化铌，氧化铬，硬脂酸铝，二硬脂酸铝和三硬脂酸铝的动力物质 加入到身体的起始粉末中。 作为替代或另外，在含氢烧结气氛中，在1400℃至1800℃的烧结温度下，在起始粉末制成的本体在10分钟至8小时的保持期间内烧结，最初与 氧分压为10-10至10-20巴，然后为10-8至10-10，然后在氧分压为10-10至10-20巴的含氢气氛中冷却。
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公开(公告)号：US4624828A
公开(公告)日：1986-11-25
申请号：US566596
申请日：1983-12-29
申请人： Carl A. Alexander
发明人： Carl A. Alexander
摘要： The invention discloses a metal-actinide mononitride composition with dimensional stability in extended nuclear reactor operations, with a method of operation at surface temperatures in excess of 1700.degree. C. The preferred embodiment and operating method uses a mononitride of uranium and a metal selected from the group consisting of titanium or yttrium. Parameters for determination of the metal element to stabilize the fuel are disclosed.
摘要翻译： 本发明公开了一种在延长的核反应堆操作中具有尺寸稳定性的金属 - 锕系元素一氮化物组合物，其表面温度超过1700℃的操作方法。优选的实施方案和操作方法使用铀的一氮化物和选自 由钛或钇组成的组。 公开了用于确定金属元素以稳定燃料的参数。
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