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公开(公告)号：US20180268946A1
公开(公告)日：2018-09-20
申请号：US15898308
申请日：2018-02-16
发明人： EDWARD J. LAHODA , PENG XU , LU CAI
摘要： 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.
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公开(公告)号：US20190074095A1
公开(公告)日：2019-03-07
申请号：US15695323
申请日：2017-09-05
发明人： EDWARD J. LAHODA , HEMANT SHAH , PENG XU , LU CAI
摘要： An improved nuclear fuel that has enhanced oxidation resistance and a process for making it are disclosed. The fuel comprises a composite of U235 enriched U3Si2 particles and an amount less than 30% by weight of UO2 particles positioned along the surface of the U3Si2 particles. The composite may be compressed into a pellet form. The process comprises forming a layer of UO2 on the surface of U3Si2 particles, either by exposing U3Si2 particles to an atmosphere of up to 15% oxygen by volume dispersed in an inert gas for a period of time and at a temperature sufficient to form UO2 at the U3Si2 particle surface, or by mixing U3Si2 particles with an amount up to 30% by weight of UO2 particles.
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公开(公告)号：US20200258642A1
公开(公告)日：2020-08-13
申请号：US16273591
申请日：2019-02-12
发明人： PENG XU , LU CAI , SYLVESTER F. OGUNJI , EDWARD J. LAHODA , LARS HALLSTADIUS
摘要： 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.
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公开(公告)号：US20190237206A1
公开(公告)日：2019-08-01
申请号：US16260889
申请日：2019-01-29
发明人： EDWARD J. LAHODA , PENG XU , ROBERT L. OELRICH, JR. , HEMANT SHAH , JONATHAN WRIGHT , LU CAI
摘要： 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：US20180056628A1
公开(公告)日：2018-03-01
申请号：US15801398
申请日：2017-11-02
IPC分类号： B32B15/01 , G21C17/022 , G21C3/20 , G21C3/07
CPC分类号： B32B15/01 , G21C3/07 , G21C3/20 , G21C17/0225 , Y02E30/40
摘要： 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.
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