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公开(公告)号：US11081247B2
公开(公告)日：2021-08-03
申请号：US15999076
申请日：2018-08-17
摘要： A method of determining a core design parameter of a nuclear reactor, includes: calibrating an isolated voltage output from a NIS cabinet associated with the nuclear reactor using a calibrated signal source as an input to the NIS cabinet; recording values of the calibrated signal source used in the calibrating and corresponding values of the output voltage from the calibrating in an as-left cabinet calibration data table; using a computing device connected to the isolated voltage output from the NIS cabinet, converting the voltage output signal to a converted detector signal using at least some of the values in the as-left cabinet calibration data table in an improved signal conversion equation; and using the computing device, employing the converted detector signal to determine the core design parameter.
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公开(公告)号：US11043308B2
公开(公告)日：2021-06-22
申请号：US15722167
申请日：2017-10-02
发明人： Edward J. Lahoda , Peng Xu , Robert Oelrich , Kumar Sridharan , Benjamin Maier , Greg Johnson
摘要： A method is described for forming duplex layers including an interlayer and a corrosion resistant boundary layer on a nuclear fuel rod cladding tube for use in a water cooled nuclear reactor. The method includes forming, by thermal deposition or physical vapor deposition, on the exterior of a substrate, an inner interlayer with Mo, Ta, W or Nb or other particles, and forming, by thermal deposition or physical vapor deposition, on the interlayer, an outer corrosion resistant layer with particles selected from the group consisting of Cr, a Cr alloy, and combinations thereof. The interlayer prevents eutectic formation between the corrosion resistant layer and the substrate.
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公开(公告)号：US20210158980A1
公开(公告)日：2021-05-27
申请号：US17047319
申请日：2019-01-30
IPC分类号： G21C13/067 , G21C13/032 , G21C15/12 , G21C7/12
摘要： A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.
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公开(公告)号：US20210074440A1
公开(公告)日：2021-03-11
申请号：US16561472
申请日：2019-09-05
发明人： MICHAEL D. HEIBEL
IPC分类号： G21C17/032 , G01F1/712 , G21C17/10
摘要： A detection apparatus is a flow and temperature measuring device in the form of a tube having a channel positioned parallel to a coolant flow stream and contains a drogue that is firmly attached to a mount within the channel. The mount has a load detection apparatus firmly imbedded near the flow inlet to the tube. The drogue has at least neutral buoyancy in the fluid at the minimum fluid temperature of interest. A change in the buoyancy of the drogue as a function of temperature and a corresponding change in the strain detection apparatus output in the fluid is determined by a combination of simple physics and calibration measurements. The relationship between changes in strain detection apparatus signal output and flow-rate-induced forces applied to the drogue surface are also determined using a combination of simple physics and calibration measurements. A system and method are also described.
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公开(公告)号：US10902961B2
公开(公告)日：2021-01-26
申请号：US16861073
申请日：2020-04-28
发明人： Kevin J. Foley , Andrew J. Gotliffe
IPC分类号： G21C17/01 , G21C17/013 , G21C19/20
摘要： A tool is receivable into an interior region of a core shroud of a Boiling Water Reactor. The tool includes an elongated frame, an elevator apparatus situated on the frame, and a manipulator apparatus situated on the elevator apparatus. The tool further includes a reciprocation apparatus that is situated on the manipulator apparatus and that has a mount that is structured to carry a device thereon. The reciprocation apparatus includes an elongated rack of an arcuate profile. The elevator apparatus is operable to move the reciprocation apparatus along the longitudinal extent of the frame. The tool further includes a foot apparatus that is situated at an end of the frame and that is receivable on a core plate to enable the frame to be pivoted about an axis of elongation of the frame with respect to the core plate.
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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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公开(公告)号：US10818402B2
公开(公告)日：2020-10-27
申请号：US15475186
申请日：2017-03-31
发明人： Joonhyung Choi , Zeses Karoutas , Paul M. Evans
摘要： A spacer grid specifically designed for accident tolerant fuel utilizing fuel rods with SiC cladding for implementation in pressurized water reactors. The spacer grid has a generally square design that allows for ease of SiC fuel rod insertion during the fuel assembly fabrication process by providing a smooth contact geometry. The co-planar support allows the fuel rods to be rotated axially more freely at the grid location than a conventional six-point contact geometry used in existing fuel assembly designs.
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公开(公告)号：US10818401B2
公开(公告)日：2020-10-27
申请号：US15013073
申请日：2016-02-02
发明人： Joonhyung Choi , Yuriy Aleshin
IPC分类号： G21C3/33
摘要： A spring apparatus in accordance with the disclosed and claimed concept is usable in a nuclear installation. In one embodiment, the spring apparatus includes a plurality of springs that are in a compressed state and that are compressively engaged with an upper core plate of a nuclear reactor when the reactor is in a cold condition. However, when the reactor is in a hot condition, a spring of the plurality of springs is in a free state wherein a free end of the spring is in an uncompressed state and is disengaged from the upper core plate. In another embodiment, the spring apparatus employs a support apparatus that is also in accordance with the disclosed and claimed concept and that includes one or more bumpers that engage the springs of a spring pack from the underside.
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公开(公告)号：US10746697B2
公开(公告)日：2020-08-18
申请号：US15810333
申请日：2017-11-13
摘要： A method of employing an eddy current sensor to perform an inspection of a tube of a steam generator involves accelerating and decelerating the eddy current sensor in a predetermined fashion that substantially reduces the likelihood of damage to the eddy current sensor. The reduction of probe stresses reduces radiological waste and reduces radiation exposure to workers involved in changing damaged probes The recording of an eddy current signal at each of a plurality of equally spaced apart locations along the tube permits the velocity of the eddy current sensor to be varied without compromising the validity of the data that has been recorded. The inspection system employs an encoder that outputs a series of signals as the probe is advanced incremental distances within the tube of the steam generator, and eddy current sensor signals are recorded responsive to at least some of the signals from the encoder.
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公开(公告)号：US10726964B2
公开(公告)日：2020-07-28
申请号：US16275640
申请日：2019-02-14
摘要： A system usable in a nuclear environment provides a reservoir of liquefied breathable gas in fluid communication with a deployment system. The deployment system uses a stream of the breathable gas from the reservoir to operate a gas turbine which runs an electrical generator that is mechanically connected therewith to generate electrical power that is stored in a battery bank. The stream of breathable gas then flows from the turbine and is split between a heat exchanger that is situated in heat exchange relation with the interior region of the main control room and an outlet that provides breathable gas to the control room. The portion of the stream that flows through the heat exchanger cools the main control room. The other portion of the stream that provides breathable gas to the main control room also recirculates the atmosphere in the control room.
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