公开(公告)号：US20240266081A1

公开(公告)日：2024-08-08

申请号：US18596693

申请日：2024-03-06

Applicant: SMR Inventec, LLC

Inventor： Krishna P. SINGH ,  P. Stefan Anton ,  Peter Stefanovic ,  Patrick Ingravallo ,  Leyland Vann ,  Joseph Gerald Leo Rajkumar ,  Indresh Rampall

IPC: G21C7/12 ,  G21C7/10 ,  G21C7/117 ,  G21C9/004 ,  G21C13/02 ,  G21C15/12 ,  G21C15/18 ,  G21C19/10 ,  G21D1/00

CPC classification number: G21C7/12 ,  G21C7/10 ,  G21C7/117 ,  G21C9/004 ,  G21C13/02 ,  G21C15/12 ,  G21C15/18 ,  G21C19/10 ,  G21D1/00 ,  G21D1/006 ,  Y02E30/30

Abstract: Portable nuclear fuel cartridge comprising a unitary support structure and plurality of nuclear fuel assemblies that collectively form a nuclear fuel core. Control rod drive system for a nuclear reactor. A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. A nuclear reactor including a cylindrical body having an internal cavity, nuclear fuel core, and a shroud disposed in the cavity. A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power.

公开(公告)号：US20230170103A1

公开(公告)日：2023-06-01

申请号：US18096008

申请日：2023-01-11

Applicant: Framatome Inc.

Inventor： Wade Markham ,  Ryan Melcher

IPC: G21C17/017 ,  G21C7/10 ,  G21C13/036 ,  G21C19/20

CPC classification number: G21C17/017 ,  G21C7/10 ,  G21C13/036 ,  G21C19/207

Abstract: 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.

公开(公告)号：US11545273B2

公开(公告)日：2023-01-03

申请号：US17022866

申请日：2020-09-16

Applicant: COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES

Inventor： Frédéric Schuster ,  Fernando Lomello ,  Francis Maury ,  Alexandre Michau ,  Raphaël Boichot ,  Michel Pons

IPC: G21C3/20 ,  G21C3/34 ,  G21C5/18 ,  G21C7/10 ,  G21C3/07 ,  C23C16/02 ,  C23C16/04 ,  C23C16/34 ,  C23C16/448 ,  C23C16/56 ,  G21C3/326 ,  G21C3/36

Abstract: A composite nuclear reactor component comprises a support and a protective layer (2). The support contains a substrate (1) based on a metal. The substrate is coated with an interposed layer (3) positioned between the substrate (1) and the protective layer (2). The protective layer (2) is composed of a material which comprises amorphous chromium carbide. The nuclear reactor component provides for improved resistance to oxidation, hydriding, and/or migration of undesired material.

公开(公告)号：US11380447B2

公开(公告)日：2022-07-05

申请号：US16883339

申请日：2020-05-26

Applicant: Westinghouse Electric Company LLC

Inventor： Anthony J. Mastopietro ,  Eric M. Benacquista

IPC: G21C7/10 ,  G21C3/326 ,  G21C19/20 ,  G21C3/32

Abstract: Arrangements and devices for reducing and/or preventing wear of a thermal sleeve in a nuclear reactor are disclosed. Arrangements include a first structure provided on or in one the thermal sleeve and a second structure provided on or in the head penetration adapter. At least a portion of the first structure and at least another portion of the second structure interact to resist, reduce, and/or prevent rotation of the thermal sleeve about its central axis relative to the head penetration adapter. Devices include a base for coupling to a guide tube of the reactor and a plurality of protruding members extending upward from the base. Each member having a portion for engaging a corresponding portion of a guide funnel of the thermal sleeve.

公开(公告)号：US20220108808A1

公开(公告)日：2022-04-07

申请号：US17454196

申请日：2021-11-09

Applicant: Westinghouse Electric Company LLC

Inventor： Edward J. LAHODA ,  Frank A. BOYLAN ,  Ho Q. LAM ,  Mitchell E. NISSLEY ,  Raymond E. SCHNEIDER ,  Robert L. OELRICH ,  Sumit RAY ,  Radu POMIRLEANU ,  Zeses KAROUTAS ,  Michael J. HONE

IPC: G21C7/24 ,  G21C7/10

Abstract: A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.

公开(公告)号：US10991468B2

公开(公告)日：2021-04-27

申请号：US16096228

申请日：2017-04-25

Applicant: Clear Inc.

Inventor： Osao Sumita ,  Isao Ueno ,  Takehiko Yokomine

IPC: G21C7/28 ,  G21C1/02 ,  G21C3/02 ,  G21C7/02 ,  G21C7/30 ,  G21C11/06 ,  G21C7/10 ,  G21D3/16 ,  G21D3/12

Abstract: Provided is a nuclear reactor having a load following control system in which a nuclear reaction therein is naturally controlled by the generated heat, the nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a-liquid or a gas having a thermal expansion coefficient greater than that of the neutron reflector, and converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.

公开(公告)号：US20200373028A1

公开(公告)日：2020-11-26

申请号：US16880364

申请日：2020-05-21

Applicant: BWXT Advanced Technologies, LLC

Inventor： James Brian Inman ,  Gary W. Neeley

IPC: G21C7/16 ,  G21C1/08 ,  G21C7/10

Abstract: A control rod assembly for a nuclear reactor having a reactor core and a pressurized fluid source, including a control rod disposed within a control rod sleeve, a lead screw that is selectively secured to the control rod, a trip latch that is secured to a bottom end of the lead screw, the trip latch being selectively securable to a top end of the control rod, a control rod drive motor that is operably connected to the lead screw, and a valve that is in fluid communication with the pressurized fluid source of the nuclear reactor and is movable between a first position and a second position, wherein in the second position of the gas valve the trip latch is in an open position.

公开(公告)号：US10811146B2

公开(公告)日：2020-10-20

申请号：US16337647

申请日：2017-09-28

Applicant: COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES

Inventor： Frédéric Schuster ,  Fernando Lomello ,  Francis Maury ,  Alexandre Michau ,  Raphaël Boichot ,  Michel Pons

IPC: G21C5/18 ,  C23C16/02 ,  C23C16/04 ,  C23C16/34 ,  C23C16/448 ,  C23C16/56 ,  G21C3/20 ,  G21C3/326 ,  G21C3/34 ,  G21C7/10

Abstract: Process for manufacturing a nuclear component comprising i) a support containing a substrate based on a metal (1), the substrate (1) being coated or not coated with an interposed layer (3) positioned between the substrate (1) and at least one protective layer (2) and ii) the protective layer (2) composed of a protective material comprising amorphous chromium carbide; the process comprising a step a) of vaporizing a mother solution followed by a step b) of depositing the protective layer (2) onto the support via a process of chemical vapor deposition of an organometallic compound by direct liquid injection (DLI-MOCVD).

公开(公告)号：US20180075931A1

公开(公告)日：2018-03-15

申请号：US15701477

申请日：2017-09-12

Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC

Inventor： YASIR ARAFAT ,  JURIE VAN WYK ,  EDWARD J. LAHODA

IPC: G21C7/10 ,  G21C9/02 ,  G21C15/257 ,  G21C1/02 ,  G21C11/06 ,  G21C3/54

Abstract: 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.

公开(公告)号：US20170167005A1

公开(公告)日：2017-06-15

申请号：US15324047

申请日：2015-03-18

Applicant: HITACHI, LTD.

Inventor： Takahiro ISHIZAKI ,  Junya KANEDA

IPC: C22C38/50 ,  B22F3/24 ,  B22F1/00 ,  G21C7/10 ,  C22C38/04 ,  C22C38/02 ,  C22C38/00 ,  B22F3/15 ,  C22C38/48

CPC classification number: C22C38/50 ,  B22F1/00 ,  B22F1/0011 ,  B22F3/15 ,  B22F3/24 ,  B22F2003/247 ,  C22C38/00 ,  C22C38/001 ,  C22C38/002 ,  C22C38/02 ,  C22C38/04 ,  C22C38/48 ,  G21C7/10 ,  G21D1/00

Abstract: An object of the present invention is to provide austenitic stainless steel having a high strength and high corrosion resistance while improving resistance to irradiation and reducing irradiation-induced stress corrosion cracking. A solution is as follows. Austenitic stainless steel of the present invention contains Cr: 16 to 26%, Ni: 8 to 22%, O: 0.02 to 0.4%, C: 0.08% or less, and N: 0.1% or less by weight, and further contains at least one kind of Zr: 0.2 to 2.8%, Ta: 0.4 to 5. 0%, and Ti: 0.2 to 2.6%, the balance being Fe and unavoidable impurities, wherein Zr, Ta, and Ti are precipitated as precipitates of one or more kinds of oxide particles, carbide particles, nitride particles, and composite particles thereof.