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公开(公告)号：US20240212872A1
公开(公告)日：2024-06-27
申请号：US18538496
申请日：2023-12-13
CPC分类号： G21C15/185 , G21C1/03 , G21C15/28
摘要： A nuclear reactor incorporating a DHR system that simultaneously guarantees removal of decay heat as soon as the reactor is shut down; removal of heat through the primary vessel and then behind the secondary vessel; improved and entirely passive (Seebeck effect) heat removal by thermal conduction through fins distributed around the primary vessel in the guard gap and which, when pivoted into their deployed position, form a kind of thermal bridge between the primary and secondary vessels.
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公开(公告)号：US11894155B2
公开(公告)日：2024-02-06
申请号：US18080595
申请日：2022-12-13
申请人： TerraPower, LLC
IPC分类号： G21C21/00 , G21C13/04 , G21C13/024 , G21C5/10 , G21C15/18 , G21C9/00 , G21C3/33 , G21C1/02 , G21C15/247 , G21C19/04 , H02K44/06 , G21C1/32 , G21C15/12
CPC分类号： G21C21/00 , G21C5/10 , G21C13/024 , G21C13/04 , G21C1/028 , G21C1/326 , G21C3/33 , G21C9/00 , G21C15/12 , G21C15/185 , G21C15/247 , G21C19/04 , H02K44/06
摘要： A nuclear reactor is designed to couple the load path of control elements with the reactor core, thus reducing opportunity for differential movement between the control elements and the reactor core. A core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The core barrel can be mounted to a reactor vessel head. Movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.
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公开(公告)号：US20240025517A1
公开(公告)日：2024-01-25
申请号：US18480559
申请日：2023-10-04
CPC分类号： B63B35/44 , G21D1/00 , G21C11/04 , G21C15/18 , B63B2035/4446
摘要： Disclosed is an offshore energy generation system (OEGS) that eliminates greenhouse gas emissions during operation, mitigating earthquake and tsunami impacts, and nuclear meltdown safety. The OEGS comprises a floating facility configured for dynamic positioning to a target site via a system that is communicably coupled to the floating facility. The floating facility is coupled to seawater collection system; steam generation system; electric power generation system that uses at least one of: steam, nuclear fission, nuclear fusion or hydrogen fuel cells for generating electric power; ammonia, freshwater, nitrogen and hydrogen generation systems, cooling water system, electric power, freshwater, and ammonia export systems, multiple offshore cranes, living quarters and helideck; automation, control and safety system for controlling one or more components. The OEGS is effective, affordable and a reliable solution for climate change as it delivers clean energy in the form of electricity, ammonia and/or freshwater.
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公开(公告)号：US11830631B2
公开(公告)日：2023-11-28
申请号：US17273536
申请日：2019-08-19
发明人： Kyungjun Kang , Jihan Chun , Hanok Kang
IPC分类号： G21C15/18 , G21C15/12 , G21C13/028 , G21C15/16 , G21C15/243
CPC分类号： G21C15/18 , G21C15/12 , G21C13/028 , G21C15/16 , G21C15/243
摘要： A nuclear reactor cooling system comprises a containment area, an In-Containment Refueling Water Storage Tank (IRWST), and a discharge pipe. The containment area is formed to enclose a reactor coolant system. The IRWST is disposed outside the containment area. The discharge pipe discharges steam from the containment area to refueling water in the IRWST when an accident occurs. A steam intake pipe has one end in fluid connection with an upper space of the IRWST, and another end in fluid connection with a radioactive substance reduction tank which stores cooling water. The steam intake pipe allows steam to flow from the upper space of the IRWST into the cooling water in the reduction tank.
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公开(公告)号：US11823804B2
公开(公告)日：2023-11-21
申请号：US17121873
申请日：2020-12-15
发明人： Jin-Ho Song , Kwang Soon Ha , Byeonghee Lee , Sung Il Kim , Yong Mann Song
摘要： A steam generator accident mitigation system is disclosed. A steam generator accident mitigation system to mitigate an accident if the accident occurs in a steam generator installed inside a containment building of a nuclear power plant according to an exemplary embodiment of the present system, the system including: a pressurizing tank which is installed inside the containment building and includes a first cooling water and a non-condensable gas for pressurizing the first cooling water therein; at least one connecting pipe connecting the steam generator and the pressurizing tank; and at least one connecting pipe valve which is installed in the at least one connecting pipe, respectively, and is able to control the amount of opening of the connecting pipe; wherein opening of the at least one connecting pipe valve permits fluid communication between the steam generator and the pressurizing tank.
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公开(公告)号：US20230268089A1
公开(公告)日：2023-08-24
申请号：US18017277
申请日：2021-07-13
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.
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7.发明公开公开(公告)号：US20230144418A1
公开(公告)日：2023-05-11
申请号：US17983021
申请日：2022-11-08
申请人： Korea Advanced Institute of Science and Technology , IUCF-HYU (Industry-University Cooperation Foundation Hanyang University)
发明人： Yong Hee KIM , Jeong Ik Lee , Taesuk Oh , Seongdong Jang , Sung Joong Kim , Doyoung Shin , Jae Hyung Park , Geonhyeong Lee , Joongoo Jeon , Taeseok Kim
IPC分类号： G21C15/12 , G21C11/08 , G21C13/024 , G21C15/18
CPC分类号： G21C15/12 , G21C11/083 , G21C13/024 , G21C15/182
摘要： Disclosed herein is a reactor including a reactor vessel and a containment vessel configured to surround the reactor vessel. The containment vessel includes a thermal radiation shield disposed on an inner wall, and a gap between the reactor vessel and the containment vessel is in an atmospheric pressure and air atmosphere state.
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公开(公告)号：US11646124B2
公开(公告)日：2023-05-09
申请号：US16648769
申请日：2018-08-23
发明人： Youngin Kim , Seungyeob Ryu , Youngmin Bae , Joohyung Moon , Hunsik Han , Soojai Shin , Cheongbong Chang , Seok Kim , Junewoo Kee , Hyunjun Cho , Minkyu Lee , Juhyeon Yoon , Hyungi Yoon
IPC分类号： G21C13/032 , G21C15/02 , F16K15/03 , G21C15/18 , F16K27/02
CPC分类号： G21C15/02 , F16K15/03 , G21C15/18 , F16K27/0209 , F16K27/0227 , G21C13/032
摘要： The present invention relates to a prevention device for loss of coolant accident (LOCA) and a nuclear reactor having the same. The prevention device for LOCA includes a nozzle portion integrally formed in a reactor vessel and having a communication hole communicating with the inside of the reactor vessel, a nozzle finishing portion assembled to the nozzle portion and an injection line for injecting a fluid to the inside of the reactor vessel respectively on both sides thereof in a communicating manner, and a check valve mounting portion installed to be embedded inside the nozzle portion and having at least one check valve opened by flow such that the fluid is injected into the reactor vessel, wherein the check valve blocks outflow of a reactor coolant from the reactor vessel in case of failure of the injection line.
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公开(公告)号：US11569000B2
公开(公告)日：2023-01-31
申请号：US17836443
申请日：2022-06-09
发明人： David H. Hinds
摘要： A nuclear plant includes a nuclear reactor, a containment structure that at least partially defines a containment environment of the nuclear reactor, and a passive containment cooling system that causes coolant fluid to flow downwards from a coolant reservoir to a bottom of a coolant channel coupled to the containment structure and rise through the coolant channel toward the coolant reservoir due to absorbing heat from the nuclear reactor. A check valve assembly, in fluid communication with the coolant reservoir, selectively enables one-way flow of a containment fluid from the containment environment to the coolant reservoir, based on a pressure at an inlet being equal to or greater than a threshold magnitude. A fusible plug, in fluid communication with the coolant reservoir at a bottom vertical depth below the bottom of the coolant reservoir, enables coolant fluid to flow into the containment structure based on at least partially melting.
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公开(公告)号：US11532404B2
公开(公告)日：2022-12-20
申请号：US17630507
申请日：2021-06-07
发明人： Po Hu
IPC分类号： G21C1/02 , G21C15/257 , G21C15/18
摘要： A travelling wave reactor for a space exploration. A reactor core of the travelling wave reactor is dispersed into several modules in a travelling wave direction; a new reactor is sequentially provided with a starting source module and a plurality of new fuel modules at zero burnup; all the modules are coaxially assembled in the travelling wave direction by means of an assembling parts, and each module further includes a heat pipe; the heat pipe in each module positioned at a front part sequentially passes through all the modules positioned at a rear portion thereof and extends out of the module at a rear end; and after a period of time of burn-up, the reactor core of the travelling wave reactor is provided with the starting source module, a spent fuel module, a critical fuel module and the new fuel module sequentially in the travelling wave direction.
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