公开(公告)号：US20170263340A1

公开(公告)日：2017-09-14

申请号：US15505019

申请日：2015-08-19

申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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

IPC分类号： G21C15/18

摘要： 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：US20170200515A1

公开(公告)日：2017-07-13

申请号：US15419227

申请日：2017-01-30

申请人： SMR Inventec, LLC

发明人： Krishna P. Singh ,  Joseph Rajkumar

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

摘要： 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：US09646726B2

公开(公告)日：2017-05-09

申请号：US13760263

申请日：2013-02-06

申请人： WESTINGHOUSE ELECTRIC COMPANY LLC

发明人： Jeffrey T. Dederer ,  William L. Brown ,  Frank Vereb

IPC分类号： G21C19/00 ,  G21C15/18 ,  G21D3/06 ,  G21C19/07

CPC分类号： G21C15/18 ,  G21C19/07 ,  G21C19/40 ,  G21D3/06 ,  G21Y2002/207 ,  Y02E30/40

摘要： The present invention relates to passive cooling systems and methods for cooling a spent fuel pool in a nuclear power plant in the absence of onsite and offsite power, e.g., in a station blackout event. The systems include a gap formed along the periphery of the spent fuel pool, a heat sink, one or more thermal conductive members, a water supply system for delivering water to at least partially fill the gap and conduct heat generated from the spent fuel pool through the gap to at least one thermal conductive member for transporting heat to the heat sink, and a thermal switch mechanism for activating and deactivating the water supply system. In particular, the passive spent fuel pool cooling systems and methods of the invention are useful when the active spent fuel pool cooling system is unavailable or inoperable.

公开(公告)号：US09640286B2

公开(公告)日：2017-05-02

申请号：US13593115

申请日：2012-08-23

申请人： Sang Jong Lee ,  Geol Woo Lee ,  Young Baek Kim ,  Jae Don Choi ,  Jae Il Lee ,  Sung Ju Cho ,  Jung Seon An ,  Dong Kyu Lee ,  Hye Jin Kim ,  Dong Uk Choi

发明人： Sang Jong Lee ,  Geol Woo Lee ,  Young Baek Kim ,  Jae Don Choi ,  Jae Il Lee ,  Sung Ju Cho ,  Jung Seon An ,  Dong Kyu Lee ,  Hye Jin Kim ,  Dong Uk Choi

IPC分类号： G21C19/07 ,  G21C15/18 ,  G21D1/04 ,  G21D3/04 ,  G21C15/24

CPC分类号： G21C19/07 ,  G21C15/18 ,  G21C15/24 ,  G21D1/04 ,  G21D3/04 ,  Y02E30/40

摘要： An apparatus for cooling a spent fuel pool having a heat exchanger includes a cooling water pool positioned above the spent fuel pool; a floating device configured to be elevated according to a water level of a cooling water in the spent fuel pool; and an emergency cooling water supply pipe configured to form a path through which the cooling water of the cooling water pool is moved to the spent fuel pool and configured to include a floating valve that opens or closes a flow passage of the cooling water in connection with the elevation of the floating device.

公开(公告)号：US09595357B2

公开(公告)日：2017-03-14

申请号：US13606413

申请日：2012-09-07

申请人： Sang Jong Lee ,  Young Baek Kim ,  Byung Chan Baek ,  Hae Nam Yang ,  Dae Jin Lee ,  Young Jae Choi ,  Jae Kyu Lee ,  Kyun Heo ,  Kyung Woo Shim ,  Seoung Eun Chun

发明人： Sang Jong Lee ,  Young Baek Kim ,  Byung Chan Baek ,  Hae Nam Yang ,  Dae Jin Lee ,  Young Jae Choi ,  Jae Kyu Lee ,  Kyun Heo ,  Kyung Woo Shim ,  Seoung Eun Chun

IPC分类号： G21C15/18 ,  G21D3/06

CPC分类号： G21D3/06 ,  G21C15/18 ,  Y02E30/40

摘要： A passive cooling system of a nuclear power plant includes a steam generator, a cooling water storage tank, a water cooling heat exchanger, an air cooling heat exchanger, a divergence valve, and a cooling tower. The steam generator generates steam by heat exchange with a primary coolant system, and the cooling water storage tank stores cooling water therein. The water cooling heat exchanger is disposed in the cooling water storage tank, and the air cooling heat exchanger is connected to the steam generator. The divergence valve is controllable to divert steam from the steam generator into both the water cooling heat exchanger and the air cooling heat exchanger. Each of the cooling water storage tank, the water cooling heat exchanger, and the air cooling heat exchanger are located in the cooling tower.

摘要翻译： 核电站的被动冷却系统包括蒸汽发生器，冷却水储存箱，水冷式热交换器，空气冷却热交换器，发散阀和冷却塔。 蒸汽发生器通过与主冷却剂系统的热交换产生蒸汽，并且冷却水储存罐在其中存储冷却水。 水冷式热交换器配置在冷却水储存箱内，空气冷却用热交换器与蒸汽发生器连接。 分流阀是可控制的，以将来自蒸汽发生器的蒸汽转移到水冷却热交换器和空气冷却热交换器中。 冷却水存储箱，水冷式热交换器和空气冷却热交换器各自位于冷却塔中。

公开(公告)号：US20170025194A1

公开(公告)日：2017-01-26

申请号：US14804488

申请日：2015-07-21

申请人： Eric Paul LOEWEN ,  Seth Ryan Paul STREGE ,  Nicholas Francis O'NEILL ,  Levon Pierre KEUSSEYAN

发明人： Eric Paul LOEWEN ,  Seth Ryan Paul STREGE ,  Nicholas Francis O'NEILL ,  Levon Pierre KEUSSEYAN

IPC分类号： G21C15/18 ,  G21C15/24 ,  H01L35/30

CPC分类号： G21C15/18 ,  G21C15/182 ,  G21C15/24 ,  H01L35/30 ,  Y02E30/40

摘要： A passive safety system for removing decay heat from a nuclear power system may comprise a shroud structure and a heat generator that is within the shroud structure. A thermoelectric device may be disposed in thermal contact with the heat generator. The thermoelectric device is configured to generate a voltage based on a temperature difference between opposite parts of the thermoelectric device. A fan arrangement is disposed above the heat generator and in electrical connection with the thermoelectric device. The fan arrangement is configured to increase a coolant flow through the coolant passage to the outlet opening based on the voltage from the thermoelectric device.

摘要翻译： 用于从核动力系统去除腐蚀热的被动安全系统可以包括护罩结构和位于护罩结构内的热发生器。 可以将热电装置设置成与发热体热接触。 热电装置被配置为基于热电装置的相对部分之间的温度差产生电压。 风扇布置设置在热发生器上方并与热电装置电连接。 风扇装置构造成基于来自热电装置的电压增加通过冷却剂通道的冷却剂流到出口开口。

公开(公告)号：US09502143B2

公开(公告)日：2016-11-22

申请号：US14109072

申请日：2013-12-17

申请人： Palvannanathan Ganesan

发明人： Palvannanathan Ganesan

IPC分类号： G21C15/18 ,  G21C11/04 ,  G21C13/024 ,  G21C17/112 ,  G21D5/02

CPC分类号： G21C15/18 ,  G21C11/04 ,  G21C13/024 ,  G21C17/112 ,  G21D5/02 ,  G21Y2002/207 ,  G21Y2004/30 ,  Y02E30/40

摘要： A floating nuclear power reactor including one or two nuclear power reactors positioned in a floating vessel such as a barge or the like. Means is disclosed for flooding the containment structure of the nuclear reactor and for flooding the reactor vessels to cool the same.

摘要翻译： 包括一个或两个核动力反应堆的浮式核动力反应堆，其位于诸如驳船等的浮动容器中。 公开了用于淹没核反应堆的容纳结构并用于淹没反应器容器以冷却其的装置。

公开(公告)号：US09443620B2

公开(公告)日：2016-09-13

申请号：US13351691

申请日：2012-01-17

申请人： Takashi Sato ,  Makoto Akinaga ,  Yoshihiro Kojima

发明人： Takashi Sato ,  Makoto Akinaga ,  Yoshihiro Kojima

IPC分类号： G21C9/00 ,  G21C9/004 ,  G21C13/10 ,  G21C9/016 ,  G21C15/18

CPC分类号： G21C9/004 ,  G21C9/016 ,  G21C13/10 ,  G21C15/18 ,  Y02E30/40

摘要： According to an embodiment, a nuclear reactor containment vessel has: a primary reactor containment vessel which contains a nuclear pressure vessel; a secondary reactor containment vessel and which is disposed outside the primary reactor containment vessel which has the pressure resistant properties and the leak-tightness which are equivalent to those of the primary reactor containment vessel; an air bag which is disposed within the secondary reactor containment vessel and which, when a failure occurs in primary reactor containment vessel, expands while receiving and encapsulating a high pressure gas discharged from the inside of the primary reactor containment vessel; and a gas phase vent pipe which connects the primary reactor containment vessel and the air bag.

摘要翻译： 根据实施例，核反应堆安全壳具有：包含核压力容器的主反应堆容纳容器; 第二反应堆安全壳，并且设置在主反应堆容纳容器的外部，其具有与初级反应堆安全壳相同的耐压性和密封性; 设置在二次反应堆容纳容器内的气囊，当在一次反应堆安全壳中发生故障时，在接收并封装从一次反应堆安全壳内部排出的高压气体的同时膨胀; 以及连接主反应堆安全壳和气囊的气相通气管。

公开(公告)号：US20160260509A1

公开(公告)日：2016-09-08

申请号：US15030578

申请日：2014-11-25

申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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

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

CPC分类号： 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

摘要： 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.

摘要翻译： 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。

公开(公告)号：US09396820B2

公开(公告)日：2016-07-19

申请号：US13824917

申请日：2013-01-18

申请人： DCNS

发明人： Geoffrey Haratyk

IPC分类号： G21C15/18 ,  G21C1/32 ,  B63B35/00 ,  B63G8/00 ,  G21C9/004 ,  G21C9/016 ,  G21D3/06 ,  G21C11/04 ,  B63B35/44

CPC分类号： G21C1/32 ,  B63B35/00 ,  B63B2035/4446 ,  B63G8/001 ,  G21C9/004 ,  G21C9/016 ,  G21C11/04 ,  G21C15/18 ,  G21D3/06 ,  Y02E30/40

摘要： The underwater electricity production module according to the invention includes means in the form of an elongated cylindrical box (12) in which means are integrated forming an electricity production unit including means forming a nuclear boiler (30), associated with electricity production means (37) connected to an external electricity distribution station (7) by electrical cables (6), is characterized in that the nuclear boiler-forming means (30) include a secondary circuit (36) associated with the electricity production means (37) and a secondary backup circuit (60) in parallel on that secondary circuit and including at least one secondary passive heat exchanger (61) placed outside the underwater module (12) in the marine environment.

摘要翻译： 根据本发明的水下电力生产模块包括细长圆柱形箱体（12）的形式的装置，其中装置整合形成一个电力生产单元，包括与电力生产装置（37）相关联的形成核燃料锅炉（30）的装置， 通过电缆（6）连接到外部配电站（7），其特征在于，所述核燃烧器形成装置（30）包括与所述发电装置（37）相关联的次级回路（36）和辅助备用 电路（60）并联，并且包括放置在海洋环境中的水下模块（12）外部的至少一个次级被动热交换器（61）。