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11. 发明授权

US10102930B2 Nuclear fuel rod cladding including a metal nanomaterial layer 有权
公开(公告)号：US10102930B2
公开(公告)日：2018-10-16
申请号：US14079221
申请日：2013-11-13
申请人： AREVA NP Inc.
发明人： Mihai G. M. Pop , Laurence Lamanna , Garry Garner , Brian Lockamon
IPC分类号： G21C21/14 , G21C3/07 , G21C3/06 , G21C21/02
摘要： A nuclear fuel cladding is provided. The nuclear fuel cladding includes a base cladding; and at least one nanomaterial layer deposited on a surface of the base cladding, the nanomaterial layer having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding is also provided. The method includes depositing nanoparticles on a base cladding to form at least one nanomaterial layer, the nanoparticles having an average grain size of between 5 to 400 nanometers.

12. 发明授权

US11594343B2 Method and device for replacing sleeves lining nuclear reactor pressure vessel tubes 有权
公开(公告)号：US11594343B2
公开(公告)日：2023-02-28
申请号：US17046607
申请日：2018-04-13
申请人： Framatome Inc.
发明人： Wade Markham , Ryan Melcher
IPC分类号： G21C17/017 , G21C7/10 , G21C13/036 , G21C19/20
摘要： A method for restraining a sleeve lining a tube passing through a nuclear reactor pressure vessel is provided. The method includes attaching in situ a radial protrusion on an external surface of the sleeve; and attaching a collar to an end of the tube and coupling the radial protrusion with the collar to retain the thermal sleeve in position.

13. 发明授权

US11289222B2 Method and device for unlatching control rod drive shafts in pressurized water reactors 有权
公开(公告)号：US11289222B2
公开(公告)日：2022-03-29
申请号：US15923764
申请日：2018-03-16
申请人： Framatome Inc.
发明人： Alex Boutin
IPC分类号： G21C19/115 , G21C19/105 , G21C19/11 , G21C7/117
摘要： An unlatching tool configured for actuating a movable section of a control rod drive shaft in a pressurized water reactor includes a base; a gripper assembly configured for gripping the movable section of the control rod drive shaft; a rod movably connecting the gripper assembly to the base; and a mechanical actuator fixed to the base and configured for rotating the rod to raise and lower the gripper assembly. A method for actuating a movable section of a control rod drive shaft includes installing an unlatching tool on the control rod drive shaft; latching the unlatching tool to a stationary section of the control rod drive shaft; and raising a rod connected to a gripper assembly to cause the gripper assembly to grip the movable section and move the movable section upward.

14. 发明授权

US10062460B2 Control rod device mechanism inner diameter annulus ultra high pressure cavitation peening 有权
公开(公告)号：US10062460B2
公开(公告)日：2018-08-28
申请号：US14554517
申请日：2014-11-26
申请人： AREVA Inc.
发明人： Gary R. Poling , Doug M. Lawrence , Bradley H. Graham , David J. Peckham
IPC分类号： G21C19/00 , C21D7/04 , G21C19/20 , G21C17/022
CPC分类号： G21C19/00 , C21D7/04 , G21C17/0225 , G21C19/207
摘要： A sealing member is provided to create a sealed region about an annulus formed between an inner body, such as a thermal sleeve, and an outer body, such as a control rod drive housing nozzle. Liquid is introduced into the sealed region to create a flooded region, which is pressurized to a desired level. A nozzle is provided into the flooded region, the nozzle being configured to fit within the annulus. Pressurized fluid is ejected from the nozzle, causing the formation of cavitation bubbles. The nozzle flow causes the cavitation bubbles to settle on the surfaces forming the annulus. The collapsing impact of the cavitation bubbles imparts compressive stress in the materials of the surfaces forming the annulus.

15. 发明授权

US10020078B2 Composite fuel rod cladding 有权
公开(公告)号：US10020078B2
公开(公告)日：2018-07-10
申请号：US14250270
申请日：2014-04-10
申请人： AREVA Inc.
发明人： Mihai G. M. Pop
IPC分类号： G21C3/30 , G21C3/07 , B32B18/00
CPC分类号： G21C3/07 , B32B18/00 , C04B2235/5244 , C04B2237/365 , C04B2237/38 , Y02E30/40
摘要： A fuel rod for a nuclear fission reactor is disclosed and claimed. The fuel rod includes an elongate hollow cladding configured to retain a nuclear fuel therein. The cladding includes an elongate hollow tube. Fiber layers are positioned around the outside surface of the tube or within the tube forming an integral part thereof. Both the tube and the fibers are formed of a ceramic material. A fuel assembly including a plurality of such fuel rods is also disclosed and claimed.

16. 发明授权

US11227697B2 Self-powered in-core detector arrangement for measuring flux in a nuclear reactor core 有权
公开(公告)号：US11227697B2
公开(公告)日：2022-01-18
申请号：US16173893
申请日：2018-10-29
申请人： Framatome Inc.
发明人： Ian McKeag Johnson
IPC分类号： G21C17/108 , G01T3/00 , G21C17/04
摘要： An detector-assembly for measuring flux in a nuclear reactor core includes self-powered in-core detector arrangements each for measuring flux at a different one of a plurality of axial locations in the core, and an assembly connector configured to be connected to a power plant connector. The assembly connector includes a plurality flux signal terminals each connected to one of self-powered in-core detector arrangements. At least one of the self-powered in-core detector arrangements comprises a set of at least two self-powered in-core detectors for measuring flux at a same one of the axial locations in the nuclear reactor core. Each of the at least two self-powered in-core detectors includes a sheath, a detector material section inside the sheath, an insulator between the sheath and the detector material, and a flux signal output line. The flux signal output lines of the at least two self-powered in-core detectors are joined together.

17. 发明授权

US11009485B2 Method of identifying and removing surface irregularities before ultrasonic inspection and device for identifying surface irregularities 有权
公开(公告)号：US11009485B2
公开(公告)日：2021-05-18
申请号：US16129734
申请日：2018-09-12
申请人： Framatome Inc.
发明人： Mark W. Lowry , Nghiep K. Du
IPC分类号： G01N27/90 , G01N27/9013 , G01N27/904
摘要： A distance sensor unit is also provided. The distance sensor unit includes an array of distance sensors configured to identify surface irregularities deviating from an expected nominal geometry of a surface as the distance sensor unit is moved along the surface and a handheld housing configured for being gripped by an operator. The array of distance sensors is connected to the handheld housing. The distance sensor unit also includes at least one surface irregularity indicator configured for providing an alert to the operator as the distance sensor unit moves over one of the surface irregularities deviating from the expected nominal geometry of the surface.

18. 发明授权

US10563808B2 Tube leak repair clamp sealing apparatus for use in a nuclear power plant 有权
公开(公告)号：US10563808B2
公开(公告)日：2020-02-18
申请号：US15456547
申请日：2017-03-12
申请人： Framatome Inc.
发明人： David Lee Mancier , Stephan Mark Hunter
IPC分类号： F16L55/17 , F16L55/178
摘要： A clamp sealing apparatus configured for preventing leakage from a defective region of a tube is provided. The clamp sealing apparatus includes a first clamping section and second clamping section tangentially connected to each other; and a seal held by the first and second clamping sections. Each of the first and second clamping sections includes a segment of a clamp body and a segment of a compression section. The clamp body and the compression section is configured for axially compressing the seal between the clamp body and the compression section such that the seal is pressed radially against an outer diameter surface of the tube onto the defective region by the axial compression to seal the defective region. A method of sealing a defective region of a tube to prevent fluid leakage through the defective region is also provided.

19. 发明授权

US10437939B2 Probabilistic evaluation of fastener degradation in nuclear power plants 有权
公开(公告)号：US10437939B2
公开(公告)日：2019-10-08
申请号：US15158851
申请日：2016-05-19
申请人： Framatome Inc.
发明人： Greg Troyer , Brian Haibach , Tim Wiger
IPC分类号： G06N7/00 , G06F17/50
摘要： A probabilistic method for determining an operability interval for fasteners in a nuclear power plant assembly is provided. The probabilistic method includes determining or assuming a geometric distribution of a given initial condition of fasteners in the nuclear power plant assembly at an initial time T0; determining a future fastener failure probability model of the geometric distribution over time; generating a plurality of random future fastener failure patterns by applying the fastener failure model to the geometric distribution at a given time T1>T0; postulating fastener spacing rules designed to evaluate the acceptability of fastener failure patterns for the fasteners in the nuclear power plant assembly; applying the fastener spacing rules to a plurality of randomly generated fastener failure patterns for the given time T1 to determine the probability of the randomly generated fastener failure patterns passing the fastener spacing rules at the given time T1; iterating, by a processor of a computer, the applying step for a given range of time values T2, T3, . . . , Tx>T0 and determining a maximum future time Tmax at which a predetermined acceptable probability of the fastener failure patterns passing the fastener spacing rules is met, thereby justifying the acceptability of the fasteners for continued operation of the nuclear power plant assembly; and determining the operability interval as being Tmax-T0.

20. 发明授权

US10436227B2 Sealing device for jet pump slip joints 有权
公开(公告)号：US10436227B2
公开(公告)日：2019-10-08
申请号：US14885109
申请日：2015-10-16
申请人： Framatome Inc.
发明人： Kenneth Wade Markham , Charles Allen Graves
IPC分类号： F04F5/44 , F04F5/46 , F04F5/10 , G21C15/25
摘要： A sealing device for a jet pump of a boiling water reactor is provided. The jet pump includes an inlet mixer and a diffuser receiving the inlet mixer at a slip joint such that an outer circumferential surface of the inlet mixer is received in an inner circumferential surface of the diffuser at the slip joint. The diffuser includes a plurality of guiding fins, each guiding fin including a radially inner surface, a radially outer surface and lateral surfaces extending radially between the inner and outer surfaces. The sealing device includes a seal configured for sealingly contacting the outer circumferential surface of the inlet mixer and a collar configured for holding the seal against the outer circumferential surface of the inlet mixer. The collar includes portions configured for being received radially between the radially inner surfaces of the guiding fins and the outer circumferential surface of the inlet mixer. The sealing device further includes a clamp configured for contacting the radially outer surfaces of the guiding fins to axially clamp the guiding fins. A method of mounting a sealing device onto a slip joint of a jet pump of a boiling water reactor is also provided.

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