公开(公告)号：US11551822B2

公开(公告)日：2023-01-10

申请号：US17473433

申请日：2021-09-13

Applicant: Westinghouse Electric Company LLC

Inventor： Edward J. Lahoda ,  Peng Xu ,  Robert L. Oelrich, Jr. ,  Hemant Shah ,  Jonathan Wright ,  Lu Cai

IPC: G21C3/62 ,  G21C3/04 ,  G21C3/22 ,  G21C21/12 ,  G21C3/20

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：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

IPC: G21C3/62 ,  G21C21/12 ,  G21C3/04 ,  G21C3/22

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：US10350856B2

公开(公告)日：2019-07-16

申请号：US15801398

申请日：2017-11-02

Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC

Inventor： Peng Xu ,  Lu Cai

IPC: B32B15/01 ,  G21C3/07 ,  G21C3/20 ,  G21C17/022

Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.

公开(公告)号：US11488730B2

公开(公告)日：2022-11-01

申请号：US17065374

申请日：2020-10-07

Applicant: Westinghouse Electric Company LLC

Inventor： Edward J. Lahoda ,  Peng Xu ,  Lu Cai

IPC: G21C3/07 ,  G21C3/62 ,  G21C3/04

Abstract: Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material with a water-resistant layer, the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.

公开(公告)号：US10803999B2

公开(公告)日：2020-10-13

申请号：US15898308

申请日：2018-02-16

Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC

Inventor： Edward J. Lahoda ,  Peng Xu ,  Lu Cai

IPC: G21C3/07 ,  G21C21/02 ,  G21C3/20 ,  C01B33/06 ,  G21C3/62 ,  G21C3/04

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 coating the fissile material, such as a pellet of U3Si2 and/or the grain boundaries, to a desired thickness with a suitable coating material, such as atomic layer deposition or a thermal spray process. The coating material may be any non-reactive material with a solubility at least as low as that of UO2. Exemplary coating materials include ZrSiO4, FeCrAl, Cr, Zr, Al—Cr, CrAl, ZrO2, CeO2, TiO2, SiO2, UO2, ZrB2, Na2O—B2O3—SiO2—Al2O3 glass, Al2O3, Cr2O3, carbon, and SiC, and combinations thereof. The water resistant layer may be overlayed with a burnable absorber layer, such as ZrB2 or B2O3—SiO2 glass.

公开(公告)号：US09844923B2

公开(公告)日：2017-12-19

申请号：US14826524

申请日：2015-08-14

Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC

Inventor： Peng Xu ,  Lu Cai

IPC: B32B15/00 ,  B32B15/01 ,  G21C3/07 ,  G21C3/20 ,  G21C17/022

CPC classification number: B32B15/01 ,  G21C3/07 ,  G21C3/20 ,  G21C17/0225 ,  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 composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.