公开(公告)号：US10102936B2

公开(公告)日：2018-10-16

申请号：US14620390

申请日：2015-02-12

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21D1/00 ,  G21D1/04 ,  G21C15/24 ,  G21C15/00 ,  G21C1/32 ,  F22B1/02 ,  F01K5/02

Abstract: A nuclear steam supply system having a start-up sub-system for heating a primary coolant. In one embodiment, the invention can be a nuclear steam supply system comprising: a reactor vessel having an internal cavity, a reactor core comprising nuclear fuel disposed within the internal cavity; a steam generating vessel fluidly coupled to the reactor vessel; a primary coolant loop formed within the reactor vessel and the steam generating vessel, a primary coolant in the primary coolant loop; and a start-up sub-system fluidly coupled to the primary coolant loop, the start-up sub-system configured to: (1) receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant into the primary coolant loop.

公开(公告)号：US20180254113A1

公开(公告)日：2018-09-06

申请号：US15901249

申请日：2018-02-21

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21D1/00 ,  G21C13/02

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：US10008296B2

公开(公告)日：2018-06-26

申请号：US14713093

申请日：2015-05-15

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21C19/07 ,  G21C13/02 ,  G21C19/04 ,  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 in one embodiment includes a containment vessel comprising a thermally conductive shell and an annular reservoir surrounding the shell that holds a liquid coolant forming a heat sink. A spent fuel pool is disposed inside the containment vessel and includes a body of water in contact with a peripheral sidewall of the fuel pool. At least one spent nuclear fuel rod submerged in the body of water heats the water. The peripheral sidewall of the spent fuel pool is formed by a portion of the shell of the containment vessel adjacent to the fuel pool, thereby defining a shared common heat transfer wall. The heat transfer wall operates to transfer heat from the body of water in the spent fuel pool to the heat sink to cool the body of water. The heat transfer wall comprises metal in one embodiment.

公开(公告)号：US20180144838A1

公开(公告)日：2018-05-24

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

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.

公开(公告)号：US09786394B2

公开(公告)日：2017-10-10

申请号：US14423149

申请日：2013-08-21

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21C15/12 ,  G21C15/26 ,  G21C11/08 ,  G21D1/04 ,  G21C9/012 ,  G21C11/02 ,  G21C13/02 ,  G21C19/07

CPC classification number: G21C15/18 ,  G21C9/012 ,  G21C11/02 ,  G21C11/088 ,  G21C13/02 ,  G21C15/12 ,  G21C15/26 ,  G21C19/07 ,  G21D1/04 ,  Y02E30/40

Abstract: A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped.

公开(公告)号：US20170200515A1

公开(公告)日：2017-07-13

申请号：US15419227

申请日：2017-01-30

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21C15/12 ,  G21C13/02

Abstract: A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger.