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公开(公告)号：US11443857B2
公开(公告)日：2022-09-13
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.
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Patent Agency Ranking
公开(公告)号：US10566095B2
公开(公告)日：2020-02-18
申请号：US15284076
申请日：2016-10-03
Inventor： Edward J. Lahoda , Peng Xu , Zeses Karoutas , Sumit Ray , Kumar Sridharan , Benjamin Maier , Greg Johnson
Abstract: A method is provided for coating the substrate of a component, such as a zirconium alloy cladding tube, for use in a water cooled nuclear reactor under normal operating conditions and under high temperature oxidation conditions. The method includes heating a pressurized carrier gas to a temperature between 200° C. and 1200° C., adding chromium or chromium-based alloy particles having an average diameter of 20 microns or less to the heated carrier gas, and spraying the carrier gas and particles onto the substrate at a velocity, preferably from 800 to 4000 ft./sec. (about 243.84 to 1219.20 meters/sec.), to form a chromium and/or chromium-based alloy coating on the substrate to a desired thickness.
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公开(公告)号：US09721676B2
公开(公告)日：2017-08-01
申请号：US14287435
申请日：2014-05-27
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： Jason P. Mazzoccoli , Peng Xu , Sumit Ray , Carroll J. Long, Jr. , Grant L. Eddy
IPC: B32B15/01 , G21C3/07 , C23C4/08 , C23C16/06 , C23C16/455 , C23C16/48 , C23C16/515 , C23C18/54 , C23C28/02 , G21C21/14 , G21C21/16 , C23C4/134 , G21C21/02 , C23C14/16 , C25D5/10 , C25D5/12 , C23C18/16
CPC classification number: G21C3/07 , C23C4/08 , C23C4/134 , C23C14/16 , C23C16/06 , C23C16/45525 , C23C16/487 , C23C16/515 , C23C18/1651 , C23C18/54 , C23C28/021 , C23C28/023 , C25D5/10 , C25D5/12 , G21C21/02 , G21C21/14 , G21C21/16 , Y02E30/40
Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The coating includes a first tier or layer and a second tier or layer. The first layer includes an elemental metal and the second layer is an oxidation-resistant layer that includes elemental chromium. The first layer serves as an intermediate layer between the zirconium alloy substrate and the second layer. This intermediate layer can be effective to improve adhesion of the second layer to the zirconium alloy substrate. The multilayer coating forms a protective layer which provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear reactor.
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公开(公告)号：US12183474B2
公开(公告)日：2024-12-31
申请号：US17454196
申请日：2021-11-09
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 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.
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公开(公告)号：US11289213B2
公开(公告)日：2022-03-29
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 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.
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6.发明授权公开(公告)号：US10685754B2
公开(公告)日：2020-06-16
申请号：US15451643
申请日：2017-03-07
Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
Inventor： Edward J. Lahoda , Sumit Ray
Abstract: An improved testing and data gathering method is described herein with reference to testing a new fuel, as an exemplary component to be tested for licensure purposes. The method includes generally: generating models for the new system; making samples and getting them accepted for a reactor; and testing the samples in a test or commercial reactor until the exposure time is reached for the expected cycle length of the fuel at final use. The method is preferably done concurrent to submitting a license application for commercial use of the new component to the relevant government body to expedite license testing review.
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