-
11.发明申请公开(公告)号：US20190164658A1
公开(公告)日：2019-05-30
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 , C23C4/129 , C23C28/00 , C23C4/02 , G21C3/324 , C23C4/12 , C23C4/10 , C23C4/06 , G21C3/07 , C23C24/04
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.
-
公开(公告)号：US20190066853A1
公开(公告)日：2019-02-28
申请号：US16051712
申请日：2018-08-01
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： EDWARD J. LAHODA , FRANK A. BOYLAN , HO Q. LAM , MITCHELL E. NISSLEY , RAYMOND E. SCHNEIDER , ROBERT L. OELRICH , SUMIT RAY , RADU POMIRLEANU , ZESES KAROUTAS , MICHAEL J. HONE
Abstract: A high temperature control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.
-
13.发明申请公开(公告)号：US20180254114A1
公开(公告)日：2018-09-06
申请号：US15450167
申请日：2017-03-06
Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
Inventor： EDWARD J. LAHODA , ANDREW J. MUELLER
CPC classification number: G21C21/02 , G21C3/042 , G21C3/045 , G21C3/047 , G21C3/10 , G21C3/20 , Y02E30/40
Abstract: A method is described that includes the steps of making a thin walled Zr alloy tube, loading nuclear fuel pellets into the tube, compressing the tube onto the fuel pellets to substantially reduce free space around the fuel pellets, positioning end plugs at each of two ends of the tube, filling the tube with a heat transferring gas, and coating the compressed tube with a corrosion resistant material using a thermal deposition process, such as cold spray, before inserting the tube into a pre-formed SiC composite cover having at least one closed end.
-
公开(公告)号：US20180025794A1
公开(公告)日：2018-01-25
申请号：US15284182
申请日：2016-10-03
Inventor： EDWARD J. LAHODA , PENG XU , ZESES KAROUTAS , SIMON MIDDLEBURGH , SUMIT RAY , KUMAR SRIDHARAN , BENJAMIN MAIER , GREG JOHNSON
IPC: G21C3/07 , C23C4/11 , C23C4/134 , G21C21/02 , C23C24/04 , C22C27/04 , C22C30/02 , C22F1/18 , C23C4/073 , C23C4/18
CPC classification number: G21C3/07 , C22C27/04 , C22C30/02 , C22F1/18 , C23C4/073 , C23C4/10 , C23C4/11 , C23C4/134 , C23C4/18 , C23C24/04 , C23C24/08 , C23C28/30 , C23C28/34 , G21C21/02 , Y02E30/40
Abstract: A method is described herein for coating the substrate of a component for use in a water cooled nuclear reactor to provide a barrier against corrosion. The method includes providing a zirconium alloy substrate; and coating the substrate with particles selected from the group consisting of metal oxides, metal nitrides, FeCrAl, FeCrAlY, and high entropy alloys. Depending on the metal alloy chosen for the coating material, a cold spray or a plasma arc spray process may be employed for depositing various particles onto the substrate. An interlayer of a different material, such as a Mo, Nb, Ta, or W transition metal or a high entropy alloy, may be positioned in between the Zr-alloy substrate and corrosion barrier layer.
-
公开(公告)号：US20170365364A1
公开(公告)日：2017-12-21
申请号：US15187985
申请日：2016-06-21
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： EDWARD J. LAHODA , PENG XU
CPC classification number: G21C3/07 , C04B35/565 , C04B35/6263 , C04B35/6264 , C04B35/806 , C04B2235/3826 , C04B2235/5244 , C04B2235/5445 , C04B2235/5454 , C04B2235/614 , C04B2235/616 , C04B2235/72 , C04B2235/77 , C04B2235/79 , C23C16/325 , G21C21/02 , Y02E30/40
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.
-
Patent Agency Ranking
公开(公告)号：US20160358673A1
公开(公告)日：2016-12-08
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 , G21Y2002/302 , G21Y2004/301 , 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.
-
公开(公告)号：US20200258642A1
公开(公告)日：2020-08-13
申请号：US16273591
申请日：2019-02-12
Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
Inventor： PENG XU , LU CAI , SYLVESTER F. OGUNJI , EDWARD J. LAHODA , LARS HALLSTADIUS
Abstract: The present invention relates to nuclear fuel compositions including uranium dioxide with integral fuel burnable absorber, and triuranium disilicide and a composite of uranium mononitride and triuranium disilicide with or without integral fuel burnable absorber, and methods of sintering these compositions. The sintering is conducted using SPS/FAST apparatus and techniques. The sintering time and temperature is reduced using SPS/FAST as compared to conventional sintering methods for nuclear fuel compositions. The nuclear fuel compositions of the present invention are particularly useful in light water reactors.
-
公开(公告)号：US20200051702A1
公开(公告)日：2020-02-13
申请号：US16573544
申请日：2019-09-17
Inventor： EDWARD J. LAHODA , PENG XU , ZESES KAROUTAS , SUMIT RAY , KUMAR SRIDHARAN , BENJAMIN MAIER , GREG JOHNSON
Abstract: A zirconium alloy cladding tube for use in a water cooled nuclear reactor under normal operating conditions and under high temperature oxidation conditions is described. The cladding tube has a coating uniformly deposited thereon. The coating, which may be up to 300 microns thick, is selected from the group consisting of chromium, a chromium-based alloy, and combinations thereof.
-
公开(公告)号：US20190237206A1
公开(公告)日：2019-08-01
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.
-
公开(公告)号：US20190139654A1
公开(公告)日：2019-05-09
申请号：US16174767
申请日：2018-10-30
Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
Inventor： EDWARD J. LAHODA , PENG XU , Robert L. Oelrich, JR. , FRANK A. BOYLAN , HEMANT SHAH , SUMIT RAY , FAUSTO FRANCESCHINI , JAVIER E. ROMERO , JONATHAN WRIGHT
Abstract: An improved, accident tolerant fuel for use in light water and heavy water reactors is described. The fuel includes a zirconium alloy cladding having a chromium or chromium alloy coating and an optional interlayer of molybdenum, tantalum, tungsten, and niobium between the zirconium alloy cladding and the coating, and fuel pellets formed from U3Si2 or UN and from 100 to 10000 ppm of a boron-containing integral fuel burnable absorber, such as UB2 or ZrB2, either intermixed within the fuel pellet or coated over the surface of the fuel pellet.
-
-
-
-
-
-
-
-
-
Search Results
25
records
(took 0.023 seconds)
