公开(公告)号：US20210012913A1

公开(公告)日：2021-01-14

申请号：US16883592

申请日：2020-05-26

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

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

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：US20180277264A1

公开(公告)日：2018-09-27

申请号：US15996868

申请日：2018-06-04

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 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 first peripheral sidewall of the fuel pool. At least one spent nuclear fuel rod submerged in the body of water heats the water. The first 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：US20200176137A1

公开(公告)日：2020-06-04

申请号：US16710048

申请日：2019-12-11

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21D1/00 ,  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.

公开(公告)号：US20180277260A1

公开(公告)日：2018-09-27

申请号：US15927284

申请日：2018-03-21

Applicant: SMR Inventec, LLC

Inventor： Thomas Marcille ,  Joseph Rajkumar

IPC: G21C3/18 ,  G21C5/06 ,  G21C11/06 ,  G21C15/10

CPC classification number: G21C3/18 ,  G21C3/324 ,  G21C5/02 ,  G21C5/06 ,  G21C11/06 ,  G21C15/10 ,  Y02E30/40

Abstract: A fuel core for a nuclear reactor in one embodiment includes an upper internals unit and a lower internals unit comprising nuclear fuel assemblies. The assembled fuel core includes an upper core plate, a lower core plate, and a plurality of channel boxes extending therebetween. Each channel box comprises a plurality of outer walls and inner walls collectively defining a longitudinally-extending interior channels or cells having a transverse cross sectional area configured for holding no more than a single nuclear fuel assembly in some embodiments. A cylindrical reflector circumferentially surrounds channel boxes and is engaged at opposing ends by the upper and lower core plates. Adjacent cells within each channel box are formed on opposite sides of inner walls such that the cells are separated from each other by the inner walls alone without any water gaps therebetween which benefits neutronics for some small modular reactor designs.

公开(公告)号：US09916910B2

公开(公告)日：2018-03-13

申请号：US14620465

申请日：2015-02-12

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21C19/07 ,  G21C19/04 ,  G21C13/02 ,  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 comprising: a spent nuclear fuel pool comprising a body of liquid water having a surface level, at least one spent nuclear fuel rod submerged therein that heats the water; a lid covering the spent nuclear fuel pool to create a hermetically sealed vapor space between the surface level and the lid; and a passive heat exchange sub-system including a riser conduit comprising first and second riser inlet sections and a primary riser section that receives water vapor therefrom. Each riser inlet section has a respective inlet positioned in a respective section of the vapor space. A downcomer receives and condenses water vapor from the primary section forming condensed water vapor. A return conduit fluidly coupled to the downcomer and having an outlet located in the body of liquid water returns the condensed water vapor thereto.

公开(公告)号：US20180047469A1

公开(公告)日：2018-02-15

申请号：US15729376

申请日：2017-10-10

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21C9/012 ,  G21C13/02 ,  G21C11/02

CPC classification number: G21C15/12 ,  G21C9/012 ,  G21C11/02 ,  G21C11/088 ,  G21C13/02 ,  G21C15/18 ,  G21C15/26 ,  G21C19/07 ,  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：US20150110236A1

公开(公告)日：2015-04-23

申请号：US14397135

申请日：2013-04-25

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/24

CPC classification number: G21C15/24 ,  G21C15/26 ,  G21D1/006 ,  Y02E30/40

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.

Abstract translation: 一种使用重力驱动的自然循环的初级冷却剂流经流体互连的反应堆容器和蒸汽发生容器的核蒸汽供应系统。 在一个实施例中，蒸汽发生容器包括多个垂直堆叠的热交换器，其可操作以通过利用来自反应堆容器中的核燃料芯的主要冷却剂所获得的热量将二次冷却剂从饱和液体转化为过热蒸汽。 在一些实施例中，二次冷却剂可以是与兰金动力循环涡轮发电机组相关联的工作流体。 蒸汽发生容器和反应堆容器可以各自包括垂直细长的外壳，在一个实施例中，它们以横向相邻的关系排列。 在一个实施例中，反应堆容器和蒸汽发生容器是物理上离散的自支撑结构，其可以物理地位于相同的容纳容器中。

公开(公告)号：US10665354B2

公开(公告)日：2020-05-26

申请号：US15901249

申请日：2018-02-21

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21C13/02 ,  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：US09852820B2

公开(公告)日：2017-12-26

申请号：US14397135

申请日：2013-04-25

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/24 ,  G21C15/26 ,  G21D1/00

CPC classification number: G21C15/24 ,  G21C15/26 ,  G21D1/006 ,  Y02E30/40

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：US20160260508A1

公开(公告)日：2016-09-08

申请号：US14433394

申请日：2013-10-04

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Rajkumar

IPC: G21C15/18 ,  G21D3/14

CPC classification number: G21C15/182 ,  F22B1/023 ,  G21C1/32 ,  G21C15/00 ,  G21C15/18 ,  G21D1/006 ,  G21D1/04 ,  G21D3/14 ,  Y02E30/40

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 hydraulic-ally 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 tun extracts heat from and cools the primary coolant.

Abstract translation: 一种具有用于去除由核燃料芯产生的残余衰减热的关闭系统的核蒸汽供应系统。 蒸汽供应系统可以利用重力驱动的一次冷却剂循环通过液压相互连接的反应器和形成蒸汽供应系统的蒸汽发生容器。 关闭系统可以包括一次和二次冷却剂系统。 主冷却剂冷却系统可以包括喷射泵，其包括设置在蒸汽发生容器内部的喷射喷嘴。循环的一次冷却剂的一部分被提取，加压并返回到蒸汽发生容器，以在反应堆关闭条件下引起冷却剂循环。 在一些操作模式下，提取的一次冷却剂可以进一步冷却回到蒸汽发生容器之前。 二次冷却剂冷却系统包括泵送和冷却的流动回路，其操作以循环和冷却二次冷却剂，二次冷却剂在蒸发器中从一次冷却剂中提取热量并冷却。