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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：US10453576B2
公开(公告)日：2019-10-22
申请号：US14812051
申请日：2015-07-29
Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
Inventor： Rachel L. Devito , Jason P. Mazzoccoli , Edward J. Silva , Deborah J. Buckley , Richard J. Jacko , William A. Byers
IPC: G21C17/022 , G21C21/00 , C23F11/18
Abstract: The present invention relates to a pre-core hot functional testing (HFT) preconditioning process, which includes the introduction of chemical additives, e.g., zinc, into coolant water that circulates through the primary system of a new nuclear power plant, at various temperatures. The chemical additives contact the primary system surfaces, which results in the formation of a protective zinc-containing oxide film on the fresh surfaces to control corrosion release and deposition during subsequent normal operation of the nuclear power plant. The method includes a series of three chemistry phases to optimize the passivation process: 1) an alkaline-reducing phase, 2) an acid-reducing phase and 3) an acid-oxidizing phase.
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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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4.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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公开(公告)号：US20180179624A1
公开(公告)日：2018-06-28
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: C23C4/11 , C04B35/48 , C04B35/622
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
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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Patent Agency Ranking
6.发明授权公开(公告)号：US09336909B2
公开(公告)日：2016-05-10
申请号：US14548630
申请日：2014-11-20
Applicant: Westinghouse Electric Company LLC
Inventor： Jason P. Mazzoccoli , Edward J. Lahoda , Peng Xu
IPC: G21C3/07 , G21C3/324 , G21C21/02 , C23C24/04 , C23C28/00 , C23C4/10 , C23C4/06 , C23C4/02 , C23C4/12 , C23C4/00
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
Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22) consisting of Zr—Al, 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.
Abstract translation: 锆合金核反应堆圆柱形包层具有内部Zr衬底表面（10），由Zr-Al组成的外部体积保护材料（22）和一体化中间体积（20）的氧化锆，锆和保护材料，其中 通过以大于340米/秒的速度的冲击施加保护材料以提供集成的中间体积（20），从而导致包层的结构完整性。
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7.发明申请DEPOSITION OF INTEGRATED PROTECTIVE MATERIAL INTO ZIRCONIUM CLADDING FOR NUCLEAR REACTORS BY HIGH-VELOCITY THERMAL APPLICATION 有权通过高温热应用将集成保护材料沉积到核反应堆的ZIRCONIUM封装中公开(公告)号：US20140126683A1
公开(公告)日：2014-05-08
申请号：US13670808
申请日：2012-11-07
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
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.
Abstract translation: 锆合金核反应堆圆柱形包层具有内部Zr衬底表面（10），外部体积的保护材料（22）和一体化中间体积（20）的氧化锆，锆和保护材料，其中施加保护材料 通过以大于340米/秒的速度冲击以提供集成的中间容积（20），从而导致包层的结构完整性。
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公开(公告)号：US10290383B2
公开(公告)日：2019-05-14
申请号：US15084577
申请日：2016-03-30
Applicant: Westinghouse Electric Company LLC
Inventor： Jason P. Mazzoccoli , Edward J. Lahoda , Peng Xu
IPC: G21C21/02 , G21C3/07 , G21C3/324 , C23C24/04 , C23C28/00 , C23C4/10 , C23C4/06 , C23C4/02 , C23C4/12 , C23C4/129 , C23C4/00
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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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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10.发明申请公开(公告)号：US20150098545A1
公开(公告)日：2015-04-09
申请号：US14548630
申请日：2014-11-20
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
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.
Abstract translation: 锆合金核反应堆圆柱形包层具有内部Zr衬底表面（10），外部体积的保护材料（22）和一体化中间体积（20）的氧化锆，锆和保护材料，其中施加保护材料 通过以大于340米/秒的速度冲击以提供集成的中间容积（20），从而导致包层的结构完整性。
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