公开(公告)号：US10665357B2

公开(公告)日：2020-05-26

申请号：US15859934

申请日：2018-01-02

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21D1/00 ,  G21C15/243 ,  G21C13/073

Abstract: A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity. The flanges have a space saving design which are configured to minimize outward extension from the cavity while still providing desired leak protection at the interface between the shell and the head.

公开(公告)号：US20200152341A1

公开(公告)日：2020-05-14

申请号：US16744144

申请日：2020-01-15

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Patrick Ingravallo ,  Leyland Vann

IPC: G21C7/14 ,  G21C7/12 ,  G21C9/02

Abstract: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

公开(公告)号：US10573418B2

公开(公告)日：2020-02-25

申请号：US16406852

申请日：2019-05-08

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Patrick Ingravallo ,  Leyland Vann

IPC: G21C7/12 ,  G21C9/02 ,  G21C7/14

Abstract: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

公开(公告)号：US10510452B2

公开(公告)日：2019-12-17

申请号：US16507637

申请日：2019-07-10

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Gearald Leo Rajkumar

IPC: G21C15/14 ,  G21C15/22 ,  G21C13/04 ,  F22B1/02 ,  G21D1/00 ,  G21C15/26 ,  G21C15/257 ,  G21C13/032 ,  G21C15/18

Abstract: A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.

公开(公告)号：US20190019588A1

公开(公告)日：2019-01-17

申请号：US16139043

申请日：2018-09-23

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21D1/04 ,  G21D1/00 ,  G21C15/00 ,  G21C1/32 ,  G21D3/14 ,  F22B1/02

Abstract: A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulically interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel. A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in turn extracts heat from and cools the primary coolant.

公开(公告)号：US10096389B2

公开(公告)日：2018-10-09

申请号：US14289545

申请日：2014-05-28

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C13/02 ,  G21C15/18 ,  G21C15/12 ,  G21D1/00 ,  G21C9/004

Abstract: A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink.

公开(公告)号：US20180190398A1

公开(公告)日：2018-07-05

申请号：US15883612

申请日：2018-01-30

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21C19/04 ,  G21C13/02 ,  G21C19/07 ,  G21C11/00

CPC classification number: G21C15/18 ,  G21C11/00 ,  G21C13/02 ,  G21C19/04 ,  G21C19/07 ,  Y02E30/40

Abstract: A passively-cooled spent nuclear fuel pool system and method therefor. In one embodiment, the invention can be a passively-cooled spent nuclear fuel pool system comprising: a spent nuclear fuel pool comprising a body of liquid water having a surface level, at least one spent nuclear fuel rod submerged in the body of liquid water that heats the body of liquid water; a lid covering the spent nuclear fuel pool to create a hermetically sealed vapor space between the surface level of the body of liquid water and the lid; and a passive heat exchange sub-system fluidly coupled to the vapor space, the passive heat exchange sub-system configured to: (1) receive water vapor from the vapor space; (2) remove thermal energy from the received water vapor, thereby condensing the water vapor to form a condensed water vapor; and (3) return the condensed water vapor to the body of liquid water.

公开(公告)号：US09922740B2

公开(公告)日：2018-03-20

申请号：US14437897

申请日：2013-10-25

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21D5/14 ,  G21D1/00 ,  G21C15/26 ,  G21C13/10 ,  G21D5/16

CPC classification number: G21D1/006 ,  G21C13/10 ,  G21C15/26 ,  G21D5/14 ,  G21D5/16 ,  Y02E30/40

Abstract: A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop. This creates a temperature differential between the primary and secondary coolant sufficient to create natural thermally induced convective circulation of the primary coolant.

公开(公告)号：US09892806B2

公开(公告)日：2018-02-13

申请号：US14398946

申请日：2013-05-06

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21D1/00 ,  G21C15/243

CPC classification number: G21D1/006 ,  G21C15/243 ,  G21Y2002/40 ,  G21Y2002/501 ,  Y02E30/40

Abstract: A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity. Primary coolant flow between the steam generating vessel and reactor vessel occurs via a fluid coupling comprising direct welding between forged outer nozzles of each vessel and welded inner nozzles between each vessel inside the outer nozzles.

公开(公告)号：US09865363B2

公开(公告)日：2018-01-09

申请号：US14413807

申请日：2013-07-09

Applicant: SMR INVENTEC, LLC

Inventor： Krishna P. Singh ,  P. Stefan Anton ,  Peter Stefanovic

IPC: G21C3/30 ,  G21C5/06 ,  G21C1/06 ,  G21C3/32 ,  G21C5/14 ,  G21C11/06 ,  G21C19/32 ,  G21F5/008 ,  G21F5/12 ,  G21C19/18 ,  G21C19/07

CPC classification number: G21C3/30 ,  G21C1/06 ,  G21C3/32 ,  G21C5/06 ,  G21C5/14 ,  G21C11/06 ,  G21C19/07 ,  G21C19/18 ,  G21C19/32 ,  G21F5/008 ,  G21F5/12 ,  Y02E30/40 ,  Y10T29/49947

Abstract: A portable nuclear fuel cartridge comprising a unitary support structure and a plurality of nuclear fuel assemblies that collectively form a nuclear fuel core. The nuclear fuel core is integrated into the unitary support structure to collectively form a self-supporting assemblage than can be lifted as a single unit. In another aspect, the invention is a method of fueling and/or defueling a nuclear reactor utilizing a nuclear fuel cartridge that is loaded and/or unloaded from the nuclear reactor as a single unit. In another aspect, a nuclear reactor core is provided that comprises a nuclear fuel core comprising; a plurality of first nuclear fuel assemblies, each of the plurality of first nuclear fuel assemblies having a first transverse cross-sectional configuration; and a plurality of second nuclear fuel assemblies, each of the plurality of second nuclear fuel assemblies having a second transverse cross-sectional configuration that is different than the first transverse cross-sectional configuration.