公开(公告)号：US20140226778A1

公开(公告)日：2014-08-14

申请号：US14172808

申请日：2014-02-04

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Keung Koo KIM ,  Cheon Tae PARK ,  Seung Yeop YOO ,  Young Min BAE ,  Joo Hyung MOON ,  Soo Jai SHIN ,  Han Ok KANG ,  Jun LEE ,  Won Jae LEE ,  Tae Wan KIM ,  Keun Bae PARK ,  Ju Hyeon YOON

IPC: G21C15/18

CPC classification number: G21C15/18 ,  G21D3/06 ,  Y02E30/40

Abstract: The present disclosure may disclose a multi stage safety injection device and a passive safety injection system having the same, including a safety injection tank formed to contain coolant to be injected into a reactor vessel by a gravitational head of water when an accident occurs in which the pressure or water level of the reactor vessel is decreased, a pressure balance line connected to the reactor vessel and safety injection tank to form a pressure balance state between the reactor vessel and the safety injection tank, a safety injection line connected to a lower end portion of the safety injection tank and the reactor vessel to inject coolant to the reactor vessel in a pressure balance state between the reactor vessel and the safety injection tank, and a flow control line extended from the safety injection line to an inner portion of the safety injection tank, and provided with safety injection ports into which coolant is injected at predetermined heights, respectively, to reduce the flow rate of coolant injected into the reactor vessel step by step according to the water level reduction of the safety injection tank, in order to inject coolant to the reactor vessel at multi stages.

Abstract translation: 本公开可以公开一种多级安全注射装置和具有该多级安全注射装置的被动安全注射系统，包括安全注射罐，该安全注射罐形成为当发生事故时容纳被重力水头注入到反应器容器中的冷却剂， 反应器容器的压力或水位降低，连接到反应堆容器和安全注射罐的压力平衡管线在反应堆容器和安全注射罐之间形成压力平衡状态，连接到下端部分的安全注入管线 的安全注射槽和反应堆容器，以在反应堆容器和安全注射罐之间的压力平衡状态下将冷却剂注入反应器容器，以及从安全注射管线延伸到安全注射器的内部的流量控制管线 并且分别设置有分别以预定高度注入冷却剂的安全注入口，以减少 根据安全注射罐的水位降低逐步注入反应堆容器中的冷却剂的流量，以便将多个阶段的冷却剂喷射到反应堆容器中。

公开(公告)号：US20130343504A1

公开(公告)日：2013-12-26

申请号：US13845531

申请日：2013-03-18

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young Min BAE ,  Young In KIM ,  Keung Koo KIM ,  Seung Yeop YOO

IPC: G21C15/18

CPC classification number: G21C15/18 ,  G21C1/326 ,  Y02E30/40

Abstract: Disclosed is a heat exchanger for a passive residual heat removal system, which improves heat transfer efficiency by expanding a heat transfer area. A heat exchange tube includes a first member connected to a steam pipe through which steam generated from a steam generator of a nuclear reactor circulates, and a second member connected to both of the first member and a feed water pipe used to supply water to the steam generator provided in the nuclear reactor, and the first member has the shape different from that of the second member, thereby expanding the heat transfer area so that the heat transfer efficiency is improved.

Abstract translation: 公开了一种用于被动式余热除热系统的热交换器，其通过扩大传热面积来提高传热效率。 热交换管包括连接到蒸汽管的第一构件，通过其从核反应堆的蒸汽发生器产生的蒸汽循环，以及连接到第一构件和用于向蒸汽供应水的给水管两者的第二构件 并且第一构件具有与第二构件的形状不同的形状，从而扩大传热面积，从而提高了传热效率。

公开(公告)号：US20170148533A1

公开(公告)日：2017-05-25

申请号：US15327355

申请日：2015-07-22

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Keung Koo KIM ,  Ju Hyeon YOON ,  Jae Joo HA ,  Tae Wan KIM ,  Cheon Tae PARK ,  Seung Yeob RYU ,  Han Ok KANG ,  Young Min BAE ,  Joo Hyung MOON ,  Hun Sik HAN ,  Kyung Jun KANG ,  Soo Jai SHIN ,  Seo Yoon JUNG ,  Young Soo KIM

IPC: G21C15/18

CPC classification number: G21C15/18 ,  G21C1/326 ,  G21Y2002/206 ,  G21Y2004/40 ,  Y02E30/40

Abstract: The present invention relates to a passive heat removal system which circulates cooling fluid via a main water supply line, connected to the lower inlet of a steam generator, and a main steam pipe, connected to the top outlet of the steam generator, to the steam generator, in order to remove sensible heat of a reactor coolant system and residual heat of a core, the passive heat removal system comprising: supplementary equipment for receiving surplus cooling fluid or supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range, wherein the supplementary equipment comprises: a supplementary tank, installed at a predetermined height between the lower inlet and the top outlet of the steam generator, for receiving the surplus cooling fluid or supplying the supplementary cooling fluid, passively, depending on the flow rate of the cooling fluid; a first connection pipe, connected to the main steam pipe and the supplementary tank, for forming a flow path to allow the cooling fluid, exhausted to the main steam pipe from the steam generator, to flow to the supplementary tank; and a second connection pipe connected to the supplementary tank and the main water supply pipe for forming a supply flow path of the supplementary cooling fluid supplied from the supplementary tank.

公开(公告)号：US20150221403A1

公开(公告)日：2015-08-06

申请号：US14469499

申请日：2014-08-26

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Kyung Jun KANG ,  Keung Koo KIM ,  Hun Sik HAN ,  Ju Hyeon YOON ,  Jae Joo HA ,  Dae Hyun HWANG ,  Suhn CHOI ,  Joo Hyung MOON ,  Soo Jai SHIN

IPC: G21D3/04 ,  G21D1/02 ,  G21F1/04

CPC classification number: G21D3/04 ,  G21C9/00 ,  G21C9/004 ,  G21C13/02 ,  G21C15/18 ,  G21D1/02 ,  Y02E30/40

Abstract: The present invention provides a facility for reducing radioactive material comprising: a cooling water storage unit installed inside a containment and formed to store cooling water; a boundary unit forming a boundary of radioactive material inside the containment and surrounding a reactor coolant system installed inside the containment to prevent a radioactive material from releasing from the reactor coolant system or a pipe connected with the reactor coolant system to the containment; a connecting pipe connected with an inner space of the boundary unit and the cooling water storage unit to guide a flow of a fluid caused by a pressure difference between the boundary unit and the cooling water storage unit from the boundary unit to the cooling water storage unit; and a sparging unit disposed to be submerged in the cooling water stored in the cooling water storage unit and connected with the connecting pipe to sparge the fluid that has passed through the connecting pipe and the radioactive material contained in the fluid to the cooling water storage unit.

Abstract translation: 本发明提供了一种减少放射性物质的设备，包括：冷却水存储单元，其安装在容纳物内并形成以存储冷却水; 边界单元，形成容纳物内的放射性物质的边界，并围绕安装在安全壳内的反应堆冷却剂系统，以防止放射性物质从反应堆冷却剂系统或与反应堆冷却剂系统连接的管道释放到容纳物; 与边界单元的内部空间连接的连接管和冷却水存储单元，用于将边界单元和冷却水存储单元之间的压力差引起的流体流从边界单元引导到冷却水存储单元 ; 以及喷射单元，其被设置为浸没在存储在冷却水存储单元中的冷却水中并与连接管连接，以将已经通过连接管的流体和流体中包含的放射性物质喷射到冷却水存储单元 。

公开(公告)号：US20180308592A1

公开(公告)日：2018-10-25

申请号：US15520594

申请日：2015-10-05

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Keung Koo KIM ,  Jae Joo HA ,  Tae Wan KIM ,  Hun Sik HAN ,  Kyung Jun KANG

IPC: G21C15/18 ,  G21C1/18 ,  G21C1/09 ,  F22D11/02 ,  F22D5/34

CPC classification number: G21C15/182 ,  F01K13/025 ,  F22B1/162 ,  F22B1/1823 ,  F22B35/108 ,  F22D5/34 ,  F22D11/02 ,  G21C1/09 ,  G21C1/18 ,  G21C1/326 ,  G21C13/024 ,  G21D1/006 ,  G21D3/06 ,  Y02E30/40

Abstract: The present disclosure provides a stopped cooling system including: a steam line connecting portion connected to a steam line so as to receive cooling water through the steam line connected to an outlet of a steam generator; a stopped cooling heat exchanger for receiving cooling water that enters the stopped cooling system through the steam line connecting portion, and discharging same through a passage of the heat exchanger; a stopped cooling pump activated to perform stopped cooling of the nuclear reactor upon normal stoppage of the nuclear reactor after primary cooling of the nuclear reactor cooling system or when an accident occurs, and for forming a circulating flow of cooling water that circulates between the steam generator and the stopped cooling heat exchanger; and a water supplying pipe connecting portion connected to the heat exchanger passage and a water supplying pipe, which is connected to the inlet of the steam generator, so as to supply the cooling water cooled in the stopped cooling heat exchanger to the steam generator through the water supplying pipe.

公开(公告)号：US20170004892A1

公开(公告)日：2017-01-05

申请号：US15100224

申请日：2014-12-02

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Cheon Tae PARK ,  Seung Yeob RYU ,  Young Min BAE ,  Joo Hyung MOON ,  Soo Jai SHIN ,  Hun Sik HAN ,  Kyung Jun KANG ,  Young Soo KIM ,  Tae Wan KIM ,  Ju Hyeon YOON ,  Keung Koo KIM ,  Jae Joo HA

IPC: G21C15/18 ,  G21D1/02 ,  G21C9/004

Abstract: The present invention discloses a passive cooling system of a containment building, to which a plate-type heat exchanger is applied. A passive cooling system of a containment building comprises: a containment building; a plate-type heat exchanger provided to at least one of the inside and the outside of the containment building and comprising channels respectively provided to the both sides of a plate so as to be arranged dividedly from each other such that the plate-type heat exchanger carries out mutual heat exchange between the internal atmosphere of the containment building and a heat exchange fluid while maintaining a pressure boundary; and a pipe connected to the plate-type heat exchanger by penetrating the containment building so as to form the path of the internal atmosphere of the containment building or the heat exchange fluid.

Abstract translation: 本发明公开了一种安全壳建筑物的被动冷却系统，其中应用了板式热交换器。 遏制建筑物的被动冷却系统包括：遏制建筑物; 设置在容纳建筑物的内部和外部的至少一个的板式热交换器，并且包括分别设置在板的两侧的通道，以便彼此分开布置，使得板式热交换器 在保持压力边界的同时，在容纳建筑物的内部气氛与热交换流体之间进行相互热交换; 以及通过穿透容纳建筑​​物而连接到板式热交换器以形成容纳建筑物或热交换流体的内部气氛的路径的管道。

公开(公告)号：US20140050292A1

公开(公告)日：2014-02-20

申请号：US13958487

申请日：2013-08-02

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Young Min BAE ,  Ju Hyeon YOON ,  Keung Koo KIM

IPC: G21C15/18

CPC classification number: G21C15/18 ,  G21C1/32 ,  Y02E30/40

Abstract: A separate type safety injection tank comprises: a coolant injection unit connected to a reactor coolant system by a safety injection pipe such that coolant stored therein is injected into the reactor coolant system by a pressure difference from the reactor coolant system when a loss-of-coolant-accident (LOCA) occurs; a gas injection unit connected to the coolant injection unit, and configured to pressurize the coolant injected into the reactor coolant system, by introducing gas stored therein to an upper part of the coolant injection unit in the loss-of-coolant-accident; and a choking device disposed between the coolant injection unit and the gas injection unit, and configured to contract a flow cross-sectional area of the gas introduced to the coolant injection unit, and configured to maintain a flow velocity and a flow rate of the gas introduced to the coolant injection unit as a critical flow velocity and a critical flow rate when a pressure difference between the coolant injection unit and the gas injection unit is more than a critical value.

Abstract translation: 一种单独类型的安全注射罐包括：冷却剂注入单元，其通过安全注入管连接到反应堆冷却剂系统，使得存储在其中的冷却剂通过与反应堆冷却剂系统的压力差被注入到反应堆冷却剂系统中， 发生冷却剂事故（LOCA）; 连接到冷却剂喷射单元的气体喷射单元，并且被配置为通过在冷却剂损失事故中将存储在其中的气体引入冷却剂喷射单元的上部来对喷射到反应堆冷却剂系统中的冷却剂加压; 以及阻塞装置，其设置在所述冷却剂注入单元和所述气体注入单元之间，并且构造成收缩引入所述冷却剂注入单元的气体的流动横截面积，并且被构造成保持所述气体的流速和流量 当冷却剂注入单元和气体注入单元之间的压差大于临界值时，作为临界流速和临界流量引入冷却剂注入单元。

公开(公告)号：US20180233240A1

公开(公告)日：2018-08-16

申请号：US15513278

申请日：2015-09-09

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Suhn CHOI ,  Keung Koo KIM ,  Young Min BAE ,  Hun Sik HAN

IPC: G21C15/18 ,  G21C15/02 ,  G21D3/04 ,  G21C15/243

CPC classification number: G21C15/182 ,  F02G1/043 ,  G21C1/32 ,  G21C1/326 ,  G21C9/012 ,  G21C15/02 ,  G21C15/185 ,  G21C15/243 ,  G21C15/26 ,  G21D1/02 ,  G21D1/04 ,  G21D3/04 ,  Y02E30/40

Abstract: Disclosed is a nuclear power plant which drives a Stirling engine by means of heat generated in nuclear power plant safety systems during an accident, uses the resulting power directly or generates electric power so as to supply the power to the safety systems, and thus can improve economic efficiency as well as the reliability of safety systems, such as a passive safety system, by operating the safety systems without an emergency diesel generator or external electric power.

公开(公告)号：US20170263340A1

公开(公告)日：2017-09-14

申请号：US15505019

申请日：2015-08-19

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young In KIM ,  Suhn CHOI ,  Keung Koo KIM ,  Young Min BAE ,  Soo Jai SHIN

IPC: G21C15/18

Abstract: The present disclosure relates to a passive safety system which uses a heat exchanger together with a thermoelectric element, and a nuclear power plant comprising the same. Disclosed are a passive safety system and a nuclear power plant comprising the same, the passive safety system comprising: a heat exchanger; a thermoelectric element; and a fan unit. The heat exchanger is formed at a space inside or outside a sealed housing, and in the heat exchanger, atmosphere is introduced and heat exchange is carried out in order to lower the pressure or temperature of the atmosphere inside the housing if an accident occurs in a reactor coolant system or a secondary system disposed inside the housing. The thermoelectric element is disposed in the heat exchanger, and when a cooling fluid, for performing heat exchange with the atmosphere, performs heat exchange with the atmosphere, the thermoelectric element is configured to generate electricity due to a temperature difference between the atmosphere and the cooling fluid. The fan unit is connected to the thermoelectric element via an electricity path so as to receive electricity generated by the thermoelectric element, and is configured to increase the flow rate of the atmosphere or the cooling fluid which passes through the heat exchanger such that the heat exchange of the atmosphere and the cooling fluid can be smoothly carried out.

公开(公告)号：US20160260509A1

公开(公告)日：2016-09-08

申请号：US15030578

申请日：2014-11-25

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Young Soo KIM ,  Young In KIM ,  Cheon Tae PARK ,  Ju Hyeon YOON ,  Tae Wan KIM ,  Keung Koo KIM ,  Jae Joo HA

IPC: G21C15/24 ,  G21C15/18 ,  G21D1/04

CPC classification number: G21C15/24 ,  G21C1/322 ,  G21C1/324 ,  G21C1/326 ,  G21C1/328 ,  G21C15/182 ,  G21C15/243 ,  G21C15/247 ,  G21C15/28 ,  G21C2015/185 ,  G21D1/04 ,  G21Y2002/50 ,  G21Y2004/30 ,  Y02E30/40

Abstract: The present invention discloses a nuclear reactor coolant pump that does not rely on an electric motor, but is operated by means of driving force generated inside a nuclear power plant, so a to be capable of maintaining the safety of the nuclear reactor when the nuclear reactor is operating normally and also in the event of an accident in the nuclear reactor. The nuclear reactor coolant pump comprises: a pump impeller rotatably installed in a first fluid passage of a nuclear reactor coolant system to circulate a first fluid inside the nuclear reactor coolant system; a drive unit receiving steam from a steam generator to generate driving force to rotate the pump impeller, and rotating about the same rotating shaft as the pump impeller to transfer the generated driving force to the pump impeller; and a steam supplying unit forming a passage between the steam generator and the drive unit to supply at least a portion of the steam released from the steam generator to the drive unit.

Abstract translation: 本发明公开了一种核反应堆冷却剂泵，其不依赖于电动机，而是通过在核电厂内产生的驱动力来操作，因此当核反应堆能够保持核反应堆的安全性时 正常运行，并且在核反应堆发生事故时也是如此。 核反应堆冷却剂泵包括：可旋转地安装在核反应堆冷却剂系统的第一流体通道中的泵叶轮，以使核反应堆冷却剂系统内的第一流体循环; 驱动单元，其接收来自蒸汽发生器的蒸汽，以产生用于使所述泵叶轮旋转的驱动力，并且围绕与所述泵叶轮相同的旋转轴旋转以将所产生的驱动力传递到所述泵叶轮; 以及蒸汽供给单元，其形成在所述蒸汽发生器和所述驱动单元之间的通道，以将从所述蒸汽发生器释放的蒸汽的至少一部分供给到所述驱动单元。