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公开(公告)号：US10468143B2
公开(公告)日：2019-11-05
申请号：US14466744
申请日：2014-08-22
Applicant: Korea Atomic Energy Research Institute
Inventor： Seo Yoon Jung , Young In Kim , Jae Seon Lee , Keung Koo Kim , Tae Wan Kim , Jong Wook Kim
Abstract: Disclosed are an in-vessel control rod drive mechanism and a nuclear reactor with the same. The in-vessel control rod drive mechanism includes a control rod drive mechanism for regulating and a control rod drive mechanism for shutdown provided at an upper or lower space of a reactor core to insert or withdraw a regulating rod and a shutdown rod into/from the reactor core based on an operation state of the nuclear reactor, wherein the control rod drive mechanism for regulating and the control rod drive mechanism for shutdown are alternately arranged in the vertical direction. Therefore, a space of containment can be minimized due to the installation of the in-vessel control rod drive mechanism, and thus a rod ejection accident can be prevented, and a loss-of-coolant accident can be reduced.
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公开(公告)号：US10229762B2
公开(公告)日：2019-03-12
申请号：US14271316
申请日：2014-05-06
Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
Inventor： Young In Kim , Keung Koo Kim , Young Min Bae , Ju Hyeon Yoon , Jae Joo Ha , Won Jae Lee , Tae Wan Kim
Abstract: The present disclosure provides a cooling system of an emergency cooling tank, which enables long-term cooling without refilling cooling water, in case of the change in a quantity of heat transferred to the emergency cooling tank according to a lapse of time upon an occurrence of an accident of a nuclear reactor, and a nuclear power plant having the same. The emergency cooling tank cooling system includes an emergency cooling tank, a heat exchanging device installed to be exposed to an outside of the emergency cooling tank to operate in air, and configured to externally emit such that the operation of the emergency cooling tank is continued even without refilling the cooling water, and an opening and closing unit installed at an upper portion of the emergency cooling tank to be located higher than a water level of the cooling water.
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公开(公告)号：US10762995B2
公开(公告)日：2020-09-01
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 , G21C1/32 , G21D1/00 , F22D5/34 , F22D11/02 , G21C1/09 , G21C1/18 , F01K13/02 , F22B1/16 , F22B1/18 , F22B35/10 , G21C13/024 , G21D3/06
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.
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公开(公告)号：US10706974B2
公开(公告)日：2020-07-07
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
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.
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公开(公告)号：US10276270B2
公开(公告)日：2019-04-30
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: G21D3/10 , G21C17/00 , G21C17/01 , G21C17/02 , G21C17/06 , G21C19/20 , G21C17/003 , G21C17/007 , G21C17/013 , G21C17/022 , G21C17/104 , G21C17/108 , G21C17/112 , G21C19/07 , G21C19/40 , G21C19/34 , G21C15/24 , G21C1/32 , G21C15/243 , G21C15/18 , G21D1/04 , G21C15/247 , G21C15/28
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.
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Patent Agency Ranking
公开(公告)号：US10811147B2
公开(公告)日：2020-10-20
申请号：US15108767
申请日：2014-12-29
Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
Inventor： Young In Kim , Keung Koo Kim , Jae Joo Ha , Ju Hyeon Yoon , Young Min Bae , Soo Jai Shin , Hun Sik Han , Kyung Jun Kang , Tae Wan Kim
Abstract: The present invention provides a passive residual heat removal system and an atomic power plant comprising the same, the passive heat removal system comprising: a plate-type heat exchanger for causing heat exchange between a primary system fluid or a secondary system fluid which, in order to remove sensible heat from an atomic reactor cooling material system and residual heat from a reactor core, has received the sensible heat and the residual heat, and a cooling fluid which has been introduced from outside of a containment unit; and circulation piping for connecting the atomic reactor cooling material system to the plate-type heat exchanger, thereby forming a circulation channel of the primary system fluid, or connecting a steam generator, which is arranged at the boundary between the primary and secondary systems, to the plate-type heat exchanger, thereby forming a circulation channel of the secondary system fluid.
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公开(公告)号：US09761334B2
公开(公告)日：2017-09-12
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
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.
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公开(公告)号：US09111651B2
公开(公告)日：2015-08-18
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
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。
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公开(公告)号：US10665355B2
公开(公告)日：2020-05-26
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: G21C9/00 , G21C15/18 , G21C1/32 , G21C15/26 , G21C9/012 , G21D1/02 , G21D1/04 , G21C15/02 , G21C15/243 , G21D3/04 , F02G1/043
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.
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公开(公告)号：US10541058B2
公开(公告)日：2020-01-21
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
Abstract: A passive safety system comprises a heat exchanger, a thermoelectric element, and a fan unit. The heat exchanger is located inside a containment. The heat exchanger allows for temperature of atmosphere in the containment to be reduced. The thermoelectric element is disposed within the heat exchanger. The thermoelectric element is configured to generate electricity due to a temperature difference. The fan unit receives electricity generated by the thermoelectric element. The fan unit is configured to increase flow rate of fluid inside the containment. A nuclear power plant can include the passive safety system.
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