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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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2.发明申请公开(公告)号：US20190088376A1
公开(公告)日：2019-03-21
申请号：US15706972
申请日：2017-09-18
发明人： EDWARD J. LAHODA , FRANK A. BOYLAN
IPC分类号： G21C3/62
摘要： An improved, accident tolerant fuel for use in light water and lead fast reactors is described. The fuel includes a ceramic cladding, such as a multi-layered silicon carbide cladding, and fuel pellets formed from U15N and from 100 to 10000 ppm of a boron-containing integral fuel burnable absorber, such as UB2 or ZrB2.
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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：US20180075931A1
公开(公告)日：2018-03-15
申请号：US15701477
申请日：2017-09-12
发明人： YASIR ARAFAT , JURIE VAN WYK , EDWARD J. LAHODA
摘要： A molten salt reactor is described that includes a containment vessel, a reactor core housed within the containment vessel, a neutron reflector spaced from the containment vessel and positioned between the core and the containment vessel, a liquid fuel comprised of a nuclear fission material dissolved in a molten salt enclosed within the core, a plurality of heat transfer pipes, each pipe having a first and a second end, wherein the first end is positioned within the reactor core for absorbing heat from the fuel, a heat exchanger external to the containment vessel for receiving the second end of each heat transfer pipe for transferring heat from the core to the heat exchanger, and at least one and preferably two or more reactor shut down systems, where at least one may be a passive system and at least one or both may be an active or a manually operated system. The liquid fuel in the core is kept within the core and heat pipes are used to carry only the heat from the liquid core to the heat exchanger.
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公开(公告)号：US20210005334A1
公开(公告)日：2021-01-07
申请号：US16459764
申请日：2019-07-02
发明人： YUN LONG , PENG XU , EDWARD J. LAHODA
摘要： An elongate fuel element is described that has a silicon carbide cladding enclosing a fuel, such as UO2, wherein the fuel is dimensioned relative to the cladding to define gaps at each lateral end of the enclosure sufficiently large such that upon swelling in use, the fuel does not increase the strain on the cladding beyond the limits of the claddings strain tolerance. The lateral gaps at the ends of the fuel allow lateral expansion during swelling that reduces the strain on the cladding.
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6.发明申请公开(公告)号：US20200048766A1
公开(公告)日：2020-02-13
申请号：US14205967
申请日：2014-03-12
发明人： EDWARD J. LAHODA
IPC分类号： C23C16/455 , C23C16/40 , C23C16/32 , G21C3/20 , G21C3/07
摘要： The invention relates to compositions and methods for coating a zirconium alloy, e.g., ceramic-containing, cladding tube for use with fuel rods in a nuclear water reactor. The coating includes an intermediate oxidation resistant layer and a SiC containing layer at least partially deposited on the intermediate oxidation resistant layer. The SiC containing layer can include a plurality of fibers. The invention provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear water reactor.
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公开(公告)号：US20200020455A1
公开(公告)日：2020-01-16
申请号：US16502235
申请日：2019-07-03
发明人： EDWARD J. LAHODA
摘要： A method for making an improved nuclear fuel cladding tube includes reinforcing a Zr alloy tube by first winding or braiding ceramic yarn directly around the tube to form a ceramic covering, then physically bonding the ceramic covering to the tube by applying a first coating selected from the group consisting of Nb, Nb alloy, Nb oxide, Cr, Cr oxide, Cr alloy, or combinations thereof, by one of a thermal deposition process or a physical deposition process to provide structural support member for the Zr tube, and optionally applying a second coating and optionally applying a third coating by one of a thermal deposition process or a physical deposition process. If the tube softens at 800° C.-1000° C., the structural support tube will reinforce the Zr alloy tube against ballooning and bursting, thereby preventing the release of fission products to the reactor coolant.
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公开(公告)号：US20180371601A1
公开(公告)日：2018-12-27
申请号：US16008439
申请日：2018-06-14
发明人： EDWARD J. LAHODA , JASON P. MAZZOCCOLI , PENG XU
摘要： 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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9.发明申请公开(公告)号：US20180174695A1
公开(公告)日：2018-06-21
申请号：US15451643
申请日：2017-03-07
发明人： EDWARD J. LAHODA , SUMIT RAY
摘要： 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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公开(公告)号：US20180025793A1
公开(公告)日：2018-01-25
申请号：US15284076
申请日：2016-10-03
发明人： EDWARD J. LAHODA , PENG XU , ZESES KAROUTAS , SUMIT RAY , KUMAR SRIDHARAN , BENJAMIN MAIER , GREG JOHNSON
摘要： 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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