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1. 发明专利

JP2009031079A Emergency core cooling system 有权
标题翻译：应急核心冷却系统
公开(公告)号：JP2009031079A
公开(公告)日：2009-02-12
申请号：JP2007194220
申请日：2007-07-26
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMAZAKI KOUJI , SUZUKI YUKA , SHIMIZU TAKEO
IPC分类号： G21C15/18 , G21C9/00
CPC分类号： G21C15/18 , G21C15/182 , G21Y2002/304 , G21Y2002/50 , G21Y2004/304 , Y02E30/31
摘要： PROBLEM TO BE SOLVED: To provide an emergency core cooling system wherein an injection system has redundancy so as to inject the reactor coolant into a reactor pressure vessel even when single failure occurs on another emergency power, and two divisions out of three divisions of the emergency core cooling systems can not be used, and furthermore, when rupture occurs on a part of a connection piping in one usable division of the emergency core cooling system while performing on-line maintenance of the emergency power of an arbitrary system.
SOLUTION: An emergency core cooling system 1 includes: three systems of low-pressure injection system 19 having a low-pressure injection pump 18 for electric drive; three systems of high-pressure core injection system 22 having a high-pressure core injection pump 21 for electric drive; and an automatic pressure reducing system 26.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：提供一种应急芯冷却系统，其中注射系统具有冗余性，以便即使在另一应急电源发生单次故障时也将反应堆冷却剂注入反应堆压力容器中，并且三个部门中的两个部分的应急核心冷却系统不能使用，此外，当在任意系统的应急电力进行在线维护时，在应急核心冷却系统的一个可用部分中的连接管道的一部分发生破裂。解决方案：应急芯冷却系统1包括：具有用于电驱动的低压喷射泵18的三个低压喷射系统19系统; 具有用于电力驱动的高压铁心注射泵21的高压铁心注射系统22的三个系统; 和自动减压系统26.版权所有（C）2009，JPO＆INPIT

2. 发明专利

JP2004061192A Nuclear power generation facilities 审中-公开
公开(公告)号：JP2004061192A
公开(公告)日：2004-02-26
申请号：JP2002217343
申请日：2002-07-25
申请人： Toshiba Corp , 株式会社東芝
发明人： KURODA MICHITOMO , NAKAMARU MIKIHIDE , YAMAMOTO YUJI , SUZUKI SEIJIRO , HIOKI HIDEAKI , SHIOIRI AKIO , SHIMIZU TAKEO
IPC分类号： G21C9/00 , G21C15/18 , G21D3/04
CPC分类号： Y02E30/31
摘要： PROBLEM TO BE SOLVED: To provide nuclear power generation facilities enhanced in an aspect of economy, by simplifying a system constitution of engineering safety equipment around a nuclear reactor, without impairing plant safety and reliability. SOLUTION: The nuclear power generation facilities 20 are provided with engineering safety equipment 30 having measures 34 against a severe accident, while the vicinity of the nuclear reactor is divided into two safety divisions I and II, and a safety system 35 having a residual heat removal system 44 and an automatic pressure reducing system 37 and a low pressure water injection system 36, corresponding to design assumption events, are provided in the safety divisions I and II. The measures 34 against severe accidents are provided with a pressure-reducing valve 50, capable of reducing reactor pressure, a pressure-balanced core cooling system 51 or a dry-well pressure-balanced core cooling system, and a static containment vessel cooling system 52. COPYRIGHT: (C)2004,JPO

3. 发明专利

JP2010237070A Leakage water collector, nuclear power plant and leakage monitoring method 审中-公开
标题翻译：泄漏水收集器，核电厂和泄漏监测方法
公开(公告)号：JP2010237070A
公开(公告)日：2010-10-21
申请号：JP2009086030
申请日：2009-03-31
申请人： Toshiba Corp , 株式会社東芝
发明人： SHIMIZU TAKEO , TAWARA MIKA , ARIMA YUKI , HAMAZAKI RYOICHI , MIYAGAWA TAKUYA
IPC分类号： G21C9/016 , G21C17/02 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To reduce risks on the breakdown of a core catcher due to a delay in water injection in case of a core damage accident and those on steam explosion in case of a drop of a molten core.
SOLUTION: A nuclear power plant includes a corium holding vessel 62 which is placed below a reactor vessel 1 inside a containment vessel 2 and opens upward, structures such as pedestal walls 14 forming a cooling flow channel 50 extending along outside faces to exit below the rim of the opening of the vessel, feedwater piping 12 for supplying cooling water to the cooling flow channel 50, feedwater valves 8 mounted on the feedwater piping 12, and a drain accumulation lid 5 for covering the opening. The use of the cooling flow channel 50 as a drain waste liquid sump brings the full-time existence of the cooling water in the cooling flow channel 50.
COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：为了减少由于核心损坏事故造成的注水延迟引起的核心捕集器故障的风险，以及在熔融芯的下降时蒸汽爆炸的风险。解决方案：核电站包括一个放置在容器2内的反应容器1的下面并向上开放的ium保持容器62，诸如底座壁14的结构形成一个沿着外表面延伸的冷却流道50 在容器的开口的边缘下方，用于向冷却流路50供给冷却水的给水管道12，安装在给水管12上的给水阀8，以及用于覆盖开口的排水积存盖5。使用冷却流路50作为排水废液池，在冷却流路50中全部存在冷却水。版权所有（C）2011，JPO＆INPIT

4. 发明专利

JPH03170095A COOLANT CLEANING SYSTEM FOR NUCLEAR REACTOR 失效
公开(公告)号：JPH03170095A
公开(公告)日：1991-07-23
申请号：JP30766289
申请日：1989-11-29
申请人： TOSHIBA CORP
发明人： SHIMIZU TAKEO , FUJIKI YASUNOBU
IPC分类号： G21C19/307
摘要： PURPOSE:To shorten the inspection and maintenance (shutdown) period of a residual heat removing system and to improve the working rate of a power plant by providing stop valves for the circulation of a reactor coolant and cooling water, respectively, between plural units of non-regeneration heat exchangers which are connected in series. CONSTITUTION:The system constitution similar to the system constitution of the conventional reactor coolant 2 is obtd. when the non-regeneration heat exchangers 6a and 6b, 6c and 6d are connected in series to each other. The reactor coolant is circulated at the rate sufficient for cleaning the coolant during the operation of a reactor 2 and the function to clean the reactor coolant is, therefore, exhibited if a non-heat exchange valve 9 is opened. On the other hand, the non-regeneration heat exchangers 6a and 6b, 6c and 6d are connected in parallel to each other at the time of inspection and maintenance of the reactor 2. The flow rates of the reactor coolant and the cooling water increase to twice the flow rates of the conventional system. The heat removing capacity of about 1.5 times the heat removing capacity of the conventional reactor coolant cleaning system is, therefore, obtd. in the reactor coolant cleaning system 20.

5. 发明专利

JPS6214095A CONTROLLER FOR PRESSURE AND WATER LEVEL OF NUCLEAR REACTOR 失效
公开(公告)号：JPS6214095A
公开(公告)日：1987-01-22
申请号：JP15236285
申请日：1985-07-12
申请人： TOSHIBA CORP
发明人： SHIMIZU TAKEO
IPC分类号： G21D3/08

6. 发明专利

JP2001188094A COOLING FACILITY FOR REACTOR AND THE LIKE 失效
公开(公告)号：JP2001188094A
公开(公告)日：2001-07-10
申请号：JP2000183017
申请日：2000-06-19
申请人： TOSHIBA CORP
发明人： KUWANO ITARU , SHIMIZU TAKEO , SHIOIRI AKIO , YAMAMOTO YUJI , MATSUKI HIROSHI
IPC分类号： G21C15/18 , G21C19/07 , G21D1/00
摘要： PROBLEM TO BE SOLVED: To provide a cooling facility for reactor and the like capable of continuously cooling the heat of reactor vesel and fuel pool for periodic inspection time and reducing the mass of cooling water piping. SOLUTION: A cool water supply pipe 25 and a cool water ruturn pipe 27 are connected to a secondary cooling water supply pipe 22 and a cooling water return pipe 26 of FPC a heat exchanger 13 connected to the fuel pool 3. The cool water supply pipe 25 and the cool water return pipe 27 are connected to an air refrigirator 23. To the secondary pipe 22 and 26, switch valves 28 are respectively provided, to the cool water supply pipe 25, a temperature control valve 38 is provided, and to the coolant return pipe 37, a cool water return valve 40 is provided and so heat removal of RPV and fuel pool can be continuously attained for the most period of ordinary periodic inspection by using other heat removal system than ordinary sea water system. Simultaneously, the cooling systems of the reactor auxiliary cooling system and the turbine auxiliary cooling system can be continuously cooled.

7. 发明专利

JPH0990091A AUXILIARY COOLING SYSTEM FOR REACTOR POWER PLANT 失效
公开(公告)号：JPH0990091A
公开(公告)日：1997-04-04
申请号：JP24735395
申请日：1995-09-26
申请人： TOSHIBA CORP , TOSHIBA ENGINEERING CO
发明人： SATO TAKASHI , SHIOIRI AKIO , NAGASE TATSUO , TANABE AKIRA , SHIMIZU TAKEO , TSUTAGAWA MASAHIRO
IPC分类号： G21D1/00
摘要： PROBLEM TO BE SOLVED: To enable performing maintenance and inspection of a heat exchanger in operation in neighboring two reactor power plants. SOLUTION: In an auxiliary component cooling system of a reactor power station, consisting of three trains in accordance with the safety separation divisions I, II, III of reactor power plant, connection pipes 13 and 14 connecting between cooling water supply pipes 1 and cooling water returning pipes 2 of two neighboring reactor power plants for each same division are placed. By this, mutual backup becomes possible, the heat exchanger in the supplied side can be isolated and even if an event occurs in the supplied side plant, reactor cooling is made possible with remaining systems and the cooling capability of the supplying side plant. The isolated heat exchanger in the supplied side including sea water pumps and sea water pipes is made possible to perform maintenance during normal operation.

8. 发明专利

JPH08248166A REACTOR CONTAINER COOLING FACILITY 失效
公开(公告)号：JPH08248166A
公开(公告)日：1996-09-27
申请号：JP5216395
申请日：1995-03-13
申请人： TOSHIBA CORP
发明人： SATO TAKASHI , TSUDA MASAHIKO , TANABE AKIRA , MIZUMACHI WATARU , SHIMIZU TAKEO
IPC分类号： G21C9/00 , G21C13/00 , G21C15/18
摘要： PURPOSE: To ease influence on earthquake-proof design and disposition design as well as restriction on device disposition. CONSTITUTION: Condensed water return piping 6 and steam suction piping 9 communicating with a dry well 4 penetrate the upper end face of a nuclear reactor container 2 and are connected. The steam suction piping 9 is connected to the upper end of a condenser 13 in a cooling tank 12 through a isolation valve 10a, and the condensed water return piping 6 is connected to the lower end of the condenser 13 through another separation valve 10b. The condenser 13 is connected to a water source 16 through cooling water supply piping 17. The cooling water supply piping 17 is connected to a water injection pump 18 and a valve 19 which are independent of emergency alternating current. An atmosphere vent pipe 15 is connected to a cooling tank 12. Thereby, the cooling tank 12 is miniaturized and restriction on disposition can be eased.

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