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1. 发明申请

US20170062082A1 PASSIVE NITROGEN INJECTING DEVICE FOR NUCLEAR REACTOR COOLANT PUMP 审中-公开
标题翻译：被动硝态氮喷射装置用于核反应堆冷却泵
公开(公告)号：US20170062082A1
公开(公告)日：2017-03-02
申请号：US15308260
申请日：2014-07-22
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD.
发明人： Ho Rim MOON , Sang Hee KANG , Young Sheop PARK , Han Gon KIM
IPC分类号： G21C15/18 , G21C17/028
CPC分类号： G21C15/18 , G21C9/00 , G21C17/02 , G21C17/028 , G21Y2002/207 , G21Y2002/50 , Y02E30/40
摘要： The present invention relates to a passive nitrogen injecting device for a nuclear reactor coolant pump, the device comprising: a nitrogen supply unit for supplying nitrogen; a pressure control valve for controlling the supply of nitrogen from the nitrogen supply unit according to pressure; an accumulator for filling the nitrogen supplied through the pressure control valve at a set pressure, and supplying the filled nitrogen in the event that an accident involving coolant loss occurs; and an isolation valve for controlling the supply of the nitrogen from the accumulator into a seal housing of a nuclear reactor coolant pump. The present invention uses an accumulator so as to be able to supply nitrogen by using the pressure in the accumulator without the supply of external power in the event of an accident involving coolant loss, and therefore has the effect of being able to improve safety.
摘要翻译：本发明涉及一种用于核反应堆冷却剂泵的无源氮喷射装置，该装置包括：用于供应氮气的氮气供应单元; 压力控制阀，用于控制根据压力从氮气供应单元供应氮气; 蓄压器，用于以设定压力填充通过压力控制阀供给的氮气，并且在发生涉及冷却剂损失的事故的情况下供应填充的氮气; 以及用于控制从蓄能器将氮气供应到核反应堆冷却剂泵的密封壳体中的隔离阀。本发明使用蓄能器，以便在发生涉及冷却剂损失的事故的情况下，通过使用蓄能器中的压力而不提供外部电力来供应氮，因此具有能够提高安全性的效果。

2. 发明公开

US20230268089A1 PASSIVE CONDENSATION TANK COOLING SYSTEM OF PASSIVE AUXILIARY FEEDWATER SYSTEM 审中-公开
公开(公告)号：US20230268089A1
公开(公告)日：2023-08-24
申请号：US18017277
申请日：2021-07-13
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD
发明人： Ho Rim MOON , Sang Hee KANG , Huiun HA
IPC分类号： G21C15/18 , G21C15/243
CPC分类号： G21C15/182 , G21C15/243
摘要： Proposed is a passive condensation tank cooling system of a passive auxiliary feedwater system, the cooling system allowing a passive condensation tank to include an inner wall and an outer wall and a cooling means to be interposed between the inner wall and the outer wall, thereby suppressing the increase in the temperature of the heat exchange water in a condensation process in the passive condensation tank. To this end, proposed is the passive condensation tank cooling system of a passive auxiliary feedwater system, the cooling system including: a passive condensation tank having a water storage space to store heat-exchange water; and a condenser arranged to be immersed in the heat-exchange water in the passive condensation tank, wherein the passive condensation tank includes the outer and inner walls providing the water storage space and a cooling means interposed between the walls for absorbing heat of the heat-exchange water.

3. 发明公开

US20230307150A1 REACTOR COOLING SYSTEM FOR DISASTER ACCIDENT, AND REACTOR COOLING METHOD USING SAME 审中-公开
公开(公告)号：US20230307150A1
公开(公告)日：2023-09-28
申请号：US18016556
申请日：2021-07-12
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD.
发明人： Ho Rim MOON , Sang Hee KANG , Huiun HA
IPC分类号： G21C15/18 , G21C15/243
CPC分类号： G21C15/182 , G21C15/243
摘要： Proposed is a reactor cooling system for cooling down a reactor damaged by a disaster accident and a reactor cooling method using same using contaminated water generated at a nuclear reactor as a cooling water source for cooling the nuclear reactor after the accident, thereby maximally suppressing discharge of the contaminated water into the sea. To this end, the reactor cooling system prosed above includes a nuclear power generation facility, a seawater storage tank, a seawater inflow flow path for introducing the seawater into the seawater storage tank and a seawater discharge flow path for discharging the seawater from the seawater storage tank to the sea, connected to one end and another end of the seawater storage tank, respectively, a heat exchanger installed in a water storage space of the seawater storage tank, a contaminated water supply flow path, and a contaminated water discharge flow path.

4. 发明公开

US20230290529A1 SYSTEM FOR UTILIZING UNUSED HEAT-EXCHANGE WATER OF PASSIVE AUXILIARY FEEDWATER SYSTEM, AND REACTOR COOLING CONTROL METHOD UTILIZING UNUSED HEAT-EXCHANGE WATER OF PASSIVE AUXILIARY FEEDWATER SYSTEM 审中-公开
公开(公告)号：US20230290529A1
公开(公告)日：2023-09-14
申请号：US18017135
申请日：2021-07-12
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD.
发明人： Ho Rim MOON , Sang Hee KANG , Huiun HA
IPC分类号： G21C15/02 , G21C15/18 , G21D3/06
CPC分类号： G21C15/02 , G21C15/18 , G21D3/06
摘要： Proposed is a system for utilizing unused heat-exchange water of a passive auxiliary feedwater system, and a reactor cooling control method utilizing the unused heat-exchange water of the passive auxiliary feedwater system and, more specifically, a system for utilizing unused heat-exchange water of a passive auxiliary feedwater system, and a reactor cooling control method utilizing the unused heat-exchange water of the passive auxiliary feedwater system, which may allow the unused heat exchange water remaining after heat exchange in the passive condensation tank to be used as cooling water, thereby increasing the efficiency of reactor cooling and increasing the efficiency of initial response in an event of a reactor accident. To this end, the proposed system includes a passive condensation tank, a condenser, a steam supply line, and a condensate water recovery line and is characterized by that a residual water discharge flow path is arranged at the inside thereof.

5. 发明申请

US20160042818A1 OUTLET NOZZLE OF NUCLEAR REACTOR 审中-公开
标题翻译：核反应堆出口喷嘴
公开(公告)号：US20160042818A1
公开(公告)日：2016-02-11
申请号：US14779913
申请日：2013-04-23
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD.
发明人： Ho Rim MOON , Young Sheop PARK
IPC分类号： G21C15/24
CPC分类号： G21C15/24 , G21C13/02 , G21C13/036 , G21C17/003 , Y02E30/40
摘要： The present invention relates to an outlet nozzle of a nuclear reactor. More specifically, in the outlet nozzle of a nuclear reactor which is provided to a reactor vessel and into which the coolant discharged from the nozzle of a structure in the reactor is introduced, the outlet nozzle of a nuclear reactor has an inclination part formed at one side of the outlet nozzle such that the inclination part is inclined at a predetermined angle from the outside end to the inside thereof. The present invention has an effect, wherein the one side of the outlet nozzle into which the coolant is introduced from the nozzle of a structure in the nuclear reactor is inclined or rounded such that an inspection robot (ASME Sec XI IWB-3512) for inspecting the presence of a defect in the coupling state of the reactor while moving along the inside surface of the reactor vessel in the reactor can move to the lower side of the reactor, and thus the volumetric inspection of the reactor by the inspection robot can be freely and continuously advanced such that the volumetric inspection can be carried out to 100% without any excluded portion for welded parts. In addition, the stability of the nuclear reactor can be more effectively verified as the volumetric inspection is carried out to 100%.
摘要翻译：本发明涉及核反应堆的出口喷嘴。更具体地说，在提供给反应堆容器的核反应堆的出口喷嘴中，从反应器中的结构的喷嘴排出的冷却剂被引入其中，核反应堆的出口喷嘴具有形成在一个使得倾斜部分从外端到内部倾斜预定的角度。本发明具有这样的效果，其中从核反应堆中的结构的喷嘴引入冷却剂的出口喷嘴的一侧倾斜或倒圆，使得用于检查的检查机器人（ASME Sec XI IWB-3512）在反应器内的反应器容器的内表面移动时，反应器的耦合状态的缺陷的存在可以移动到反应器的下侧，因此检查机器人的反应器的体积检查可以是自由的并持续进行，使得体积检查可以执行到100％，没有任何排除部分的焊接部件。另外，由于体积检测进行到100％，核反应堆的稳定性可以得到更有效的验证。

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