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1. 发明授权

US12051514B2 Reactor and safety method for a reactor for the event of a meltdown of the core 有权
公开(公告)号：US12051514B2
公开(公告)日：2024-07-30
申请号：US17443991
申请日：2021-07-29
申请人： COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
发明人： Franck Morin , Gilles Avakian
IPC分类号： G21C15/18 , G21C9/00 , G21C15/12
CPC分类号： G21C15/18 , G21C15/12 , G21C9/00
摘要： A safety method for a reactor including a primary circuit and a secondary circuit fluidly isolated from the primary circuit, and a steam generator, and in the event of a meltdown of the core of the reactor with the formation of a corium bath in a bottom of the vessel and the formation of a liquid metallic layer at the surface of the corium bath, the method includes: a break-up by explosion of the fluidic insulation to set the secondary circuit in fluidic communication with the primary circuit so that the secondary fluid follows the primary circuit to flow inside the vessel over the liquid metallic layer of the corium bath.

2. 发明授权

US11783954B2 Injectable sacrificial material systems and methods to contain molten corium in nuclear accidents 有权
公开(公告)号：US11783954B2
公开(公告)日：2023-10-10
申请号：US17665719
申请日：2022-02-07
申请人： National Technology & Engineering Solutions of Sandia, LLC
发明人： Yifeng Wang , David Louie , Rekha R. Rao , Jeremy A. Templeton
IPC分类号： G21C9/016 , G21C15/18 , G21C9/00 , G21C19/48
CPC分类号： G21C9/016 , G21C9/00 , G21C15/18 , G21C19/48
摘要： Systems and methods for injecting a carbonate-based sacrificial material into a nuclear reactor containment for containment of molten corium in severe nuclear reactor accidents are disclosed. Molten corium can be quickly cooled and solidified by the endothermic decomposition of the sacrificial material.

3. 发明授权

US11728051B2 Nuclear reactor protection systems and methods 有权
公开(公告)号：US11728051B2
公开(公告)日：2023-08-15
申请号：US17077979
申请日：2020-10-22
申请人： NuScale Power, LLC , Rock Creek Innovations, LLC
发明人： Gregory Wayne Clarkson , Rufino Ayala , Jason Pottorf
IPC分类号： G21C7/36 , G21C9/00 , G05B9/02 , G06F1/28 , G21C17/00 , G21D3/04 , G21D3/06 , H02H3/05
CPC分类号： G21C9/00 , G21C7/36 , G05B9/02 , G06F1/28 , G21C17/00 , G21D3/04 , G21D3/06 , H02H3/05
摘要： A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs; and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

4. 发明申请

US20180190404A1 RADIOACTIVE IODINE ADSORBENT, AND METHOD FOR TREATING RADIOACTIVE IODINE 审中-公开
公开(公告)号：US20180190404A1
公开(公告)日：2018-07-05
申请号：US15860900
申请日：2018-01-03
申请人： Rasa Industries, Ltd.
发明人： Toshiki KOBAYASHI , Koji ENDO
IPC分类号： G21F9/02 , G21C9/00 , B01D53/82 , B01J20/18 , B01J20/28 , B01D53/68 , G21D3/06
CPC分类号： G21F9/02 , B01D53/685 , B01D53/82 , B01D2253/108 , B01D2257/202 , B01J20/186 , B01J20/28004 , B01J20/28011 , G21C9/00 , G21D3/06 , Y02E30/40
摘要： Provided is a method for treating radioactive iodine contained in steam discharged from a nuclear power facility, including a filling step of filling an air-permeable container with a granulated radioactive iodine adsorbent of zeolite X, wherein ion exchange sites of the zeolite X are substituted with silver so that a size of minute pores of the zeolite X is suited to a size of a hydrogen molecule, and the radioactive iodine adsorbent has a silver content of 36 wt % or more when dried, a particle size of 10×20 mesh, a hardness of 94% or more, and a water content of 12 wt % or less when dried at 150° C. for 3 h and thereby reduced in weight; and a flow passing step of passing a flow of the steam discharged from the nuclear power facility, through the container filled with the radioactive iodine adsorbent.

5. 发明授权

US09916908B2 Gas supply apparatus and air or nitrogen supply apparatus of nuclear plant 有权
公开(公告)号：US09916908B2
公开(公告)日：2018-03-13
申请号：US14528522
申请日：2014-10-30
申请人： Hitachi-GE Nuclear Energy, Ltd.
发明人： Ryo Kubota , Kenji Onodera , Yoshihisa Kiyotoki
IPC分类号： G21C9/00 , F15B13/043 , F16K31/02 , G21C9/004 , G21D1/02 , G21D3/06
CPC分类号： G21C9/00 , F15B13/043 , F16K31/02 , G21C9/004 , G21D1/02 , G21D3/06 , Y02E30/40 , Y10T137/87209
摘要： A gas supply apparatus of the present invention includes a gas discharge line of a first electromagnetic valve having s a switching valve placed therein, and a second electromagnetic valve placed between the switching valve and a gas supply source. The switching valve switches between a gas discharge from the first electromagnetic valve and a gas supply to the first electromagnetic valve. At the time of a normal operation, the second electromagnetic valve opens a gas discharge line side and closes a switching valve side, and when the power source is lost, the second electromagnetic valve opens the switching valve side and closes the gas discharge line side. In this way, even when the power source is lost, an operating valve can not only be operated remotely but also be operated safely by a remote operator.

6. 发明授权

US09881703B2 Seismic attenuation system for a nuclear reactor 有权
公开(公告)号：US09881703B2
公开(公告)日：2018-01-30
申请号：US14528123
申请日：2014-10-30
申请人： NuScale Power, LLC
发明人： Tamas Liszkai , Seth Cadell
IPC分类号： G21C9/04 , G21C5/10 , G21C13/024 , G21C1/32
CPC分类号： G21C9/04 , G21C1/32 , G21C1/322 , G21C5/10 , G21C9/00 , G21C13/024 , G21C13/032 , G21C13/04 , G21D1/00 , G21D3/04 , Y02E30/40
摘要： A system for attenuating seismic forces includes a reactor pressure vessel containing nuclear fuel and a containment vessel that houses the reactor pressure vessel. Both the reactor pressure vessel and the containment vessel include a bottom head. Additionally, the system includes a base support to contact a support surface on which the containment vessel is positioned in a substantially vertical orientation. An attenuation device is located between the bottom head of the reactor pressure vessel and the bottom head of the containment vessel. Seismic forces that travel from the base support to the reactor pressure vessel via the containment vessel are attenuated by the attenuation device in a direction that is substantially lateral to the vertical orientation of the containment vessel.

7. 发明申请

US20170370491A1 Butterfly Valve 审中-公开
公开(公告)号：US20170370491A1
公开(公告)日：2017-12-28
申请号：US15539449
申请日：2015-12-14
申请人： Hitachi-GE Nuclear Energy, Ltd. , Okano Valve Mfg. Co. Ltd.
发明人： Yoshiharu KAWAHARA , Yoshihisa KIYOTOKI , Takayoshi NAKASHIMA , Keisuke SAKEMURA , Yoshitomo KANEMURA , Yukio IMOTO
IPC分类号： F16K25/00 , F16K1/22
CPC分类号： F16K25/005 , F16K1/22 , F16K1/222 , F16K1/226 , F16K1/24 , F16K1/32 , F16K31/05 , G21C9/00
摘要： Provided is a butterfly valve configured so that the sealing performance of the butterfly valve is ensured even if the butterfly valve is exposed to high-temperature fluid and is installed in a high radiation environment. A butterfly valve has: a valve body-side valve seat section which is formed on the outer periphery of a valve body; a valve box-side valve seat section which is formed on a valve box; and a valve movement mechanism which, as a valve shaft pivots, moves the valve body in the direction of extension of a flow passage, between a blocking position at which the valve body-side valve seat section and the valve box-side valve seat section are in contact with each other to close a flow passage, and an open position at which the valve body-side valve seat section and the valve box-side valve seat section are separated from each other to open the flow passage. The valve body-side valve seat section is formed from a laminated material comprising a stainless steel plate and a plate-shaped body which consists of expanded graphite.

8. 发明授权

US09620252B2 Island mode for nuclear power plant 有权
公开(公告)号：US09620252B2
公开(公告)日：2017-04-11
申请号：US13861085
申请日：2013-04-11
申请人： Babcock & Wilcox mPower, Inc.
发明人： Thomas G Graham
IPC分类号： G21C9/00 , G21D1/02 , G21D3/04
CPC分类号： G21C9/00 , G21D1/02 , G21D3/04 , Y02E30/40
摘要： A nuclear power plant comprises a pressurized water reactor (PWR) and a steam generator driving a turbine driving an electric generator. A condenser condenses steam after flowing through the turbine. Responsive to a station blackout, the nuclear power plant is electrically isolated and a bypass valve is opened to convey bypass steam flow from the steam generator to the condenser without flowing through the turbine. The thermal power output of the PWR is gradually reduced over the transition time interval. After opening, the bypass valve is gradually closed over the transition time interval. A supplemental bypass valve may also be opened responsive to the station blackout to convey supplemental bypass steam flow from the steam generator to a feedwater system supplying secondary coolant feedwater to the steam generator. The supplemental bypass steam flow does not flow through the turbine and does not flow through the condenser.

9. 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。

10. 发明授权

US09390820B2 Electricity production module 有权
标题翻译：电力生产模块
公开(公告)号：US09390820B2
公开(公告)日：2016-07-12
申请号：US13824876
申请日：2013-01-18
申请人： DCNS
发明人： Geoffrey Haratyk
IPC分类号： G21C15/18 , G21C9/00 , G21C11/04 , G21C13/00 , G21D1/00
CPC分类号： G21C15/18 , G21C9/00 , G21C11/04 , G21C13/00 , G21D1/00 , Y02E30/40
摘要： An underwater electricity production module includes an elongated cylindrical box, which includes a reactor compartment, which further includes a reservoir chamber and a dry chamber; an electricity production unit including a reactor container, the reactor container being placed in the dry chamber in a reactor pit having a first lower portion; and a circumferential wall including a first part delimiting the reservoir chamber, the first part being in a direct heat exchange relationship with water of the marine environment surrounding the elongated cylindrical box. The reservoir chamber has a second lower portion connected to the first lower portion through a water inlet duct placed along the circumferential wall. The reactor pit has a first upper portion connected to a corresponding portion of the reservoir chamber through a water return duct.
摘要翻译：水下电力生产模块包括细长的圆柱形箱，其包括反应室，其还包括储存室和干燥室; 包括反应堆容器的电力生产单元，所述反应堆容器被放置在具有第一下部的反应器坑中的所述干燥室中; 以及周壁，其包括限定储存室的第一部分，第一部分与围绕细长圆柱形箱的海洋环境的水直接热交换。储存室具有通过沿着周向壁放置的进水管连接到第一下部的第二下部。反应器坑具有通过回水管连接到储存室的对应部分的第一上部。

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