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1. 发明专利

JP2003315482A Ventilation facility at top part of reactor pressure vessel 有权
标题翻译：反应堆压力容器顶部的通风设施
公开(公告)号：JP2003315482A
公开(公告)日：2003-11-06
申请号：JP2002118377
申请日：2002-04-19
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMAMOTO YUJI , KURODA MICHITOMO , SHIOIRI AKIO
IPC分类号： G21C13/00 , G21C15/18
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide ventilation facilities at the top part of a reactor pressure vessel capable of efficiently and reliably preventing non-condensable gases from being accumulated in the vicinity of the top part of the reactor pressure vessel and performing highly reliable and stable operation.
SOLUTION: The ventilation facilities 20 at the top part of the reactor pressure vessel (RPV) is provided with both an RPV head spray system 31 for supplying cooling water for an RPV head spray nozzle 36 at the upper part of the RPV 22 and a RPV ventilation system 30 for guiding non-condensable gases which occurs during operation of a reactor to a main steam pipe 37. The RPV head spray system 31 is provided with a branched ventilation system 32 branched from a check valve 39, provided on RPV head spray piping 38, on the side of the RPV 22. The branched ventilation system 32 is constituted in such a way as to guide the non-condensable gases which occur in the RPV 22 to the side of the main steam pipe 27 with the RPV ventilation system 30 during normal operation of the reactor.
COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：在反应堆压力容器的顶部设置通风设备，能够有效且可靠地防止不可冷凝气体积聚在反应堆压力容器的顶部附近并且执行高可靠性稳定运行。解决方案：反应堆压力容器（RPV）顶部的通风设备20设有RPV喷头系统31，用于在RPV 22的上部为RPV喷头喷嘴36供应冷却水以及RPV通风系统30，用于将在反应器操作期间发生的不可冷凝气体引导到主蒸汽管道37.RPV喷头系统31设置有分支式通气系统32，其从设置在RPV上的止回阀39分支头部喷射管道38在RPV 22的一侧。分支通气系统32构成为将RPV 22中发生的不可冷凝气体引导到主蒸汽管27侧的RPV 通风系统30在反应堆的正常运行期间。版权所有（C）2004，JPO

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

JP2004061191A Boiling water reactor 审中-公开
公开(公告)号：JP2004061191A
公开(公告)日：2004-02-26
申请号：JP2002217326
申请日：2002-07-25
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMAMOTO YUJI , NAKAMARU MIKIHIDE , KURODA MICHITOMO , HIOKI HIDEAKI , SHIOIRI AKIO
IPC分类号： G21C5/00 , G21C7/10 , G21C15/16 , G21C15/25
CPC分类号： Y02E30/31 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To provide a boiling water reactor capable of improving the plant safety and economic efficiency by simplifying configuration thereof.
SOLUTION: The boiling water reactor is provided with a cylindrical nuclear reactor pressure vessel 1 which is hermetically sealed, a reactor core 2, a plurality of control rods 16 which can be pulled up from upward, a control rod driving mechanism 9 located at the top of control rod guiding tubes for driving the control rods, a reactor core shroud 4 which surrounds a plurality of fuel assembly composing the reactor core, a dryer 8 which is located at the top or the outside of the nuclear reactor pressure vessel for drying steams generated from the reactor core by passing through the steams, and a jet pump 21 located between the inside of the nuclear reactor pressure vessel and the outside of the reactor core shroud 4 corresponding to the height of the reactor core.
COPYRIGHT: (C)2004,JPO

4. 发明专利

JP2004061190A Purification system for nuclear reactor coolant 审中-公开
标题翻译：核反应堆冷却液净化系统
公开(公告)号：JP2004061190A
公开(公告)日：2004-02-26
申请号：JP2002217325
申请日：2002-07-25
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMAMOTO YUJI , NAKAMARU MIKIHIDE , KURODA MICHITOMO , HIOKI HIDEAKI , SHIOIRI AKIO , KOBAYASHI MINORU
IPC分类号： G21C19/307 , G21D3/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To decrease the manhour and exposure during maintenance inspection and enhance the economical efficiency by eliminating a circulating pump.
SOLUTION: The purification system is made to have a constitution in which the downstream side from a filtration demineralization device 40 of a reactor water suction pipe 33 is connected to a main condenser 42 thereby obtaining power for sucking a reactor water from a nuclear reaction pressure vessel 31 to the reactor water suction pipe 33 corresponding to the differential pressure between the main condenser 42 and the nuclear reaction pressure vessel 31, and in addition, the reactor water purified by the filtration demineralization device 40 is fed to the main condenser through the reactor water suction pipe 33, and the purified reactor water fed to the main condenser 42 is returned to the nuclear reaction pressure vessel 31 through a pipe for a recovering and feeding water system.
COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：在维护检查期间减少工作时间和暴露，并通过消除循环泵来提高经济效益。解决方案：将净化系统制成为将反应器吸水管33的过滤去矿物质装置40的下游侧连接到主冷凝器42，从而获得从核抽吸反应器水的动力对应于主冷凝器42和核反应压力容器31之间的压差的反应器吸水管33的反应压力容器31，另外，由过滤脱盐装置40净化的反应器水，通过反应器吸水管33和供给到主冷凝器42的净化反应器水通过回收供水系统的管路返回到核反应压力容器31。版权所有（C）2004，JPO

5. 发明专利

JP2003329794A Vent device for top of reactor pressure vessel 审中-公开
标题翻译：用于反应器压力容器顶部的通风装置
公开(公告)号：JP2003329794A
公开(公告)日：2003-11-19
申请号：JP2002135838
申请日：2002-05-10
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMAMOTO YUJI , ARATA YUKIJI , SHIOIRI AKIO , KURODA MICHITOMO
IPC分类号： G21C13/00 , G21C19/303 , G21D1/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a vent device for a top of a reactor pressure vessel which enables highly reliable safe operation by effectively and surely preventing accumulation of a non-condensible gas around the top of the reactor pressure vessel.
SOLUTION: The vent device 20 for the top of the reactor pressure vessel comprises a head spray system 31 of the reactor pressure vessel for feeding cooling water to a head spray nozzle 36 of the reactor pressure vessel disposed in an upper part of the reactor pressure vessel 22 and a vent system 30 of the reactor pressure vessel for guiding the non-condensible gas produced during operation of a reactor to a main steam pipe. The head spray system 31 of the reactor pressure vessel is provided with a branch vent system 32 branched from a reactor pressure vessel 22 side of a check valve 39 provided on a head spray pipe 38 of the reactor pressure vessel. The branch vent system 32 is provided with a vent branch pipe 40 branched from the head spray pipe 38 of the reactor pressure vessel. The vent branch pipe 40 has a downstream side thereof connected to a vent pipe 33 of the system 30 and an orifice 41 provided halfway of the vent branch pipe 40.
COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：提供一种用于反应堆压力容器顶部的通风装置，其通过有效地并且可靠地防止不可冷凝气体在反应堆压力容器的顶部积聚而实现高度可靠的安全操作。解决方案：用于反应堆压力容器顶部的排放装置20包括反应堆压力容器的喷头系统31，用于将冷却水供给到设置在反应堆压力容器的上部的反应堆压力容器的喷头喷嘴36 反应堆压力容器22和反应堆压力容器的通风系统30，用于将在反应器操作期间产生的不可冷凝气体引导到主蒸汽管。反应堆压力容器的喷头系统31设置有从设置在反应堆压力容器的喷头管38上的止回阀39的反应堆压力容器22侧分支的分支排气系统32。分支排气系统32设置有从反应堆压力容器的头喷管38分支的排气支管40。排气支管40的下游侧连接到系统30的排气管33和设置在排气支管40的中途的孔41.权利要求（C）2004，JPO

6. 发明专利

JPH09243779A NUCLEAR REACTOR 失效
公开(公告)号：JPH09243779A
公开(公告)日：1997-09-19
申请号：JP5213196
申请日：1996-03-08
申请人： JAPAN ATOMIC POWER , TOSHIBA CORP
发明人： YOSHIOKA YUZURU , KADOTANI MITSUTO , TABATA HIROAKI , SUGANO MINORU , YOSHIHISA YASUMASA , NARABAYASHI SUNAO , ARAI KENJI , YANO TAKASHI , SHIOIRI AKIO , OIKAWA HIROHIDE , MIZUMACHI WATARU , YASUOKA MAKOTO
IPC分类号： G21C15/18
摘要： PROBLEM TO BE SOLVED: To properly cope with a minor rupture accident and improve the safety and economic property of a nuclear reactor by injecting water into a reactor vessel by a steam injector. SOLUTION: When a minor rupture accident occurs, an automatic pressure reducing system 5 or an isolation condenser is operated to reduce the internal pressure of a reactor pressure vessel 2. When the internal pressure of the vessel 2 is lowered to a prescribed value, a low pressure core water injecting system 16 is operated. After several minutes from operation start, combining water from a steam injector 17 is injected into the vessel 2. The internal pressure of the vessel 2 is lowered by water injection of the water injecting system 16, and when the downstream side pressure of a check valve 14 becomes lower than the head pressure of a pool 11, the valve 14 is opened to inject water in the pool 1 into the vessel 2 through a piping 12. Just after the occurrence of the minor rupture accident, the level in the vessel is recovered and kept by water injection of the water injecting systems 16, 10 to ensure the cooling of a core 3. The steam in the vessel 2 is released into the dry well DW of a reactor container 1 to ensure a long-term cooling.

7. 发明专利

JPS6420493A BORIC ACID WATER INJECTING DEVICE 失效
公开(公告)号：JPS6420493A
公开(公告)日：1989-01-24
申请号：JP17583987
申请日：1987-07-16
申请人： TOSHIBA CORP
发明人： SHIOIRI AKIO
IPC分类号： G21C9/02
摘要： PURPOSE:To assure the deflectless characteristic of a fuel rod by connecting a piping to a boric water tank via a sluice valve from the lower part of a pressure suppression chamber installed upper than a nuclear reactor and further connecting a piping from the boric water tank via a water injecting valve to the nuclear reactor. CONSTITUTION:A reducing valve 7 is opened and steam is condensed by a pressure suppression pool 1A to reduce the pressure in the nuclear reactor in the event of the generation of such a state with the nuclear reactor that the control rod cannot be inserted. When the pressure of the nuclear reactor attains the set value indicating that the pressure thereof drops below the static head of the pressure suppression pool 1A, the water injecting valve 4A and the sluice valve 9 are opened by this signal and the signal indicating that the control rod is not yet inserted. The boric acid water in the boric acid water tank 10 is then admitted into the nuclear reactor 5 by the static head of the pressure suppression pool and in succession, the pressure suppression pool water is also admitted therein. The nuclear reactor is thereby shut down and the water level of the nuclear reactor is assured. The defectless characteristic of the nuclear reactor is thus maintained.

8. 发明专利

JP2001074874A COOLING EQUIPMENT FOR NUCLEAR REACTOR OR THE LIKE 失效
公开(公告)号：JP2001074874A
公开(公告)日：2001-03-23
申请号：JP24965099
申请日：1999-09-03
申请人： TOSHIBA CORP
发明人： YAMAMOTO YUJI , SHIOIRI AKIO , YAMAZAKI KOUJI
IPC分类号： G21C15/18
摘要： PROBLEM TO BE SOLVED: To continuously perform cooling work in periodical inspection work without any interruption by changing a conventional seawater cooling water system to an alternative cooling water system for removing decay heat generated when a reactor is stopped. SOLUTION: In the removal of decay heat when a reactor is normally stopped, RPV2 is cooled by an RHR pump 5 and an RHRS pump 7 through RHR heat exchangers 48 and 49. A fuel pool 3 is cooled by allowing fuel pool water circulated by an FPC pump 12 to pass through FPC heat exchangers 33 and 34. An RCW cooling load 20 is cooled by allowing cooling water circulated by an RCW pump 15 to pass through an RCW heat exchanger 16 for carrying out cooling using seawater by an SW pump 17. When a heat removal system other than the seawater system is used during inspection for reducing the period of periodical inspection, a switching valve 46 is opened and closed, and the cooling water to the FPC heat exchangers 33 and 34 for substitution is supplied by the cooling water where an air-cooling-type refrigerator 31 for substitution is used, thus the heat exchanger is cooled.

9. 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.

10. 发明专利

JPH04344494A REACTOR CONTAINER 失效
公开(公告)号：JPH04344494A
公开(公告)日：1992-12-01
申请号：JP11580991
申请日：1991-05-21
申请人： TOSHIBA CORP
发明人： SHIOIRI AKIO
IPC分类号： G21C9/004 , G21C13/00
摘要： PURPOSE:To provide protection of equipment such as a control rod drive device (FMCRD) installed in a lower dry well in a reactor container by preventing water from flowing into the lower dry well. CONSTITUTION:A dry-well communicating tube 8 located in a reactor container 3 is extended to near the upper portion of a pressure suppression pool 6. A vent-pipe communicating hole 18 leading to a vent pipe 9 is provided in a position lower than the upper end of the communicating tube 8 and higher than the normal water level inside the pressure suppression pool 6.

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