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公开(公告)号：US11145425B2
公开(公告)日：2021-10-12
申请号：US16260889
申请日：2019-01-29
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： Edward J. Lahoda , Peng Xu , Robert L. Oelrich, Jr. , Hemant Shah , Jonathan Wright , Lu Cai
Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.
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公开(公告)号：US10984919B2
公开(公告)日：2021-04-20
申请号：US16264938
申请日：2019-02-01
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： Jason P. Mazzoccoli , Edward J. Lahoda , Peng Xu
IPC: G21C21/02 , C23C24/04 , C23C28/00 , G21C3/20 , G21C3/07 , G21C3/324 , C23C4/10 , C23C4/129 , C23C4/00 , C23C4/06 , C23C4/02 , C23C4/12
Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface, an outer volume of protective material, and an integrated middle volume of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume resulting in structural integrity for the cladding.
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公开(公告)号：US20160099080A1
公开(公告)日：2016-04-07
申请号：US14503443
申请日：2014-10-01
Applicant: Westinghouse Electric Company LLC
Inventor： Joonhyung Choi , Peng Xu
IPC: G21C3/18
Abstract: A fuel rod having a gas plenum holddown device that occupies less volume than a conventional spiral spring and is formed from a bellows-like, resilient tubular member having a hollow interior volume open to the gas plenum and an exterior sheath formed from a plurality of alternating ridges and troughs stacked in tandem and interconnected.
Abstract translation: 一种燃料棒，其具有气体压力调节装置，其占据比常规螺旋弹簧更小的体积，并且由具有通向气室的中空内部容积的波纹管状弹性管状构件形成，以及由多个交替 堆叠在一起并互连的脊和槽。
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公开(公告)号：US11043308B2
公开(公告)日：2021-06-22
申请号：US15722167
申请日：2017-10-02
Inventor： Edward J. Lahoda , Peng Xu , Robert Oelrich , Kumar Sridharan , Benjamin Maier , Greg Johnson
Abstract: A method is described for forming duplex layers including an interlayer and a corrosion resistant boundary layer on a nuclear fuel rod cladding tube for use in a water cooled nuclear reactor. The method includes forming, by thermal deposition or physical vapor deposition, on the exterior of a substrate, an inner interlayer with Mo, Ta, W or Nb or other particles, and forming, by thermal deposition or physical vapor deposition, on the interlayer, an outer corrosion resistant layer with particles selected from the group consisting of Cr, a Cr alloy, and combinations thereof. The interlayer prevents eutectic formation between the corrosion resistant layer and the substrate.
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5.发明申请公开(公告)号：US20200161010A1
公开(公告)日：2020-05-21
申请号：US16196005
申请日：2018-11-20
Inventor： Edward J. Lahoda , Peng Xu , Robert L. Oelrich, JR. , Hwasung Yeom , Kumar Sridharan
Abstract: The invention relates to SiC ceramic matrix composite (CMC) claddings with metallic, ceramic and/or multilayer coatings applied on the outer surface for improved corrosion resistance and hermeticity protection. The coating includes one or more materials selected from FeCrAl, Y, Zr and Al—Cr alloys, Cr2O3, ZrO2 and other oxides, chromium carbides, CrN, Zr- and Y-silicates and silicides. The coatings are applied employing a variety of known surface treatment technologies including cold spray, thermal spray process, physical vapor deposition process (PVD), and slurry coating.
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Patent Agency Ranking
公开(公告)号：US10446276B2
公开(公告)日：2019-10-15
申请号：US15187985
申请日：2016-06-21
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： Edward J. Lahoda , Peng Xu
IPC: C23C16/32 , G21C3/07 , C04B35/80 , G21C21/02 , C04B35/565 , C04B35/626
Abstract: A method for making a fuel rod cladding tube and a cladding tube are described. The method includes wrapping ceramic fibers, for example, SiC fibers in a SiC matrix, around a tube formed from a metal alloy, such as a zirconium alloy. The interstices of the SiC wrappings on the tube are at least partially filled with SiC nano-sized particles. The surface of the filled tube is exposed by atomic layer deposition, at temperatures ranging from 25° C. to 600° C., to at least one cycle of alternating, non-overlapping pulses of gaseous precursors containing carbon and silicon to form a SiC monolayer. The step of filling the interstices of the SiC wrappings on the tube with SiC nano-sized particles fills large voids in the SiC wrapping. The step of exposing the surface of the particle filled SiC windings to at least one cycle of gaseous pulses fills small voids in the SiC wrapping.
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7.发明授权公开(公告)号：US10128004B2
公开(公告)日：2018-11-13
申请号：US14046012
申请日：2013-10-04
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： Peng Xu , Edward J. Lahoda
Abstract: The invention pertains to a nuclear fuel assembly grid or a portion or a part of the grid, such as a grid strap and/or an integral flow mixer that is at least partially constructed of a composition containing one or more ternary compounds of the general formula I: Mn+1AXn (I) wherein, M is a transition metal, A is an element selected from the group A elements in the Chemical Periodic Table, X is carbon or nitrogen, and n is an integer from 1 to 3. The invention further pertains to a method of making the nuclear fuel assembly grid or a portion of a part of the grid, by employing a sintering process to sinter the composition containing one or more ternary compounds in powder form such that the resulting grid or a portion of or a part of the grid includes a plurality of sintered layers.
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公开(公告)号：US10062458B2
公开(公告)日：2018-08-28
申请号：US15225127
申请日：2016-08-01
Inventor： Peng Xu , Edward J. Lahoda , Lars Hallstadius , Joon Hyung Choi , Shinichi Higuichi , Fumihisa Kano
CPC classification number: G21C3/10 , C04B37/001 , C04B37/005 , C04B37/02 , C04B37/021 , C04B2235/6562 , C04B2235/6567 , C04B2235/666 , C04B2237/36 , C04B2237/365 , C04B2237/38 , C04B2237/40 , C04B2237/52 , C04B2237/765 , C04B2237/80 , C04B2237/84 , G21C3/07 , G21C21/02 , Y02E30/40
Abstract: A method of providing an end-capped tubular ceramic composite for containing nuclear fuel (34) in a nuclear reactor involves the steps of providing a tubular ceramic composite (40), providing at least one end plug (14, 46, 48), applying (42) the at least one end plug material to the ends of the tubular ceramic composite, applying electrodes to the end plug and tubular ceramic composite and applying current in a plasma sintering means (10, 50) to provide a hermetically sealed tube (52). The invention also provides a sealed tube made by this method.
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公开(公告)号：US10060018B2
公开(公告)日：2018-08-28
申请号：US14205799
申请日：2014-03-12
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： Edward J. Lahoda , Jason P. Mazzoccoli , Peng Xu
IPC: B05D1/02 , C23C4/11 , C04B35/622 , C04B35/48
CPC classification number: C23C4/11 , C04B35/48 , C04B35/62222 , C23C24/04 , C23C28/042 , C23C28/048 , C23C28/321 , C23C28/322 , C23C28/324 , C23C28/341 , C23C28/345 , C23C28/3455 , C23C28/36 , G21C3/07 , Y02E30/40 , Y02T50/6765
Abstract: A composition and method of kinetically depositing the composition to form a coating onto an exterior surface of a zirconium alloy cladding of a light water nuclear reactor which at least partially adheres to the exterior surface. The coating composition includes a first component and a second component. The first component is selected from the group consisting of zirconium, zirconium oxide and mixtures thereof. The second component is selected from the group consisting of Zr2AlC ceramic, Ti2AlC ceramic, Ti3AlC2 ceramic, Al2O3, aluminum, zirconium silicide, amorphous and semi-amorphous alloyed stainless steel, and mixtures of Zr2AlC ceramic, Ti2AlC ceramic and Ti3AlC2 ceramic. The coating has a gradient emanating from the exterior surface of the cladding toward an exposed outer surface of the coating such that percent by weight of the first component decreases and the second component increases from the exterior surface of the cladding toward the exposed outer surface of the coating.
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10.发明申请公开(公告)号：US20160254067A1
公开(公告)日：2016-09-01
申请号：US15084577
申请日：2016-03-30
Applicant: Westinghouse Electric Company LLC
Inventor： Jason P. Mazzoccoli , Edward J. Lahoda , Peng Xu
CPC classification number: G21C21/02 , C23C4/00 , C23C4/02 , C23C4/06 , C23C4/10 , C23C4/12 , C23C4/129 , C23C24/04 , C23C28/321 , C23C28/324 , G21C3/07 , G21C3/324 , G21Y2002/103 , G21Y2004/10 , Y02E30/40 , Y02T50/6765
Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.
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