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1. 发明专利

JP2015040732A 原子炉圧力容器及び原子炉圧力容器の冷却方法有权
标题翻译：核反应堆压力容器和核反应堆压力容器冷却方法
公开(公告)号：JP2015040732A
公开(公告)日：2015-03-02
申请号：JP2013171061
申请日：2013-08-21
申请人：株式会社東芝 , Toshiba Corp
发明人： AOKI KAZUYOSHI , HIOKI HIDEAKI , SAITO NOBORU , NAKAMARU MIKIHIDE , MIHASHI TADAHIRO , TOBIMATSU TOSHIMI , KOMURO MITSUO , KAMEI NAOYA
IPC分类号： G21C9/016 , G21C9/00 , G21C13/00
CPC分类号： Y02E30/31
摘要：【課題】通常運転時における断熱性能を確保しつつ、シビアアクシデント時において容器本体の底部を良好に冷却可能な原子炉圧力容器を提供する。【解決手段】実施形態によれば、原子炉圧力容器10の容器本体12は、炉心を収容し、当該炉心の鉛直下側に底部16を有する。原子炉圧力容器10は、容器本体12の外側に間隔をあけて設けられており、底部16との間に内部空間22が形成される外壁20と、シビアアクシデント時において底部16の外側から底部16に向けて水を噴射する噴射ノズル30とを有する。外壁20には、シビアアクシデント時において内部空間22の水蒸気を排出する蒸気排出口26が形成されている。原子炉圧力容器10は、通常運転時において蒸気排出口26を閉じる閉止部材をさらに有する。【選択図】図3
摘要翻译：要解决的问题：提供一种能够在严重事故发生时适当地冷却容器主体的底部的核反应堆压力容器，同时确保正常运转时的隔热性能。解决方案根据实施例，容器主体 12的核反应堆容器10中包含反应堆芯，并且包括恰好在反应堆芯下方的底部16。核反应堆10包括：设置在容器主体12的外侧的距离容器主体12一定距离的外壁20，形成在底部16和外壁20之间的内部空间22; 喷射喷嘴30在严重事故发生时从底部16的外部向底部16喷射水。在外壁20上形成有从严格事故发生时从内部空间22排出蒸气的蒸汽排气口26.核反应堆压力容器10还包括在正常操作期间关闭蒸汽排气口26的关闭构件。

2. 发明专利

JP2013246099A Hydrogen treatment device and method 审中-公开
标题翻译：氢处理装置和方法
公开(公告)号：JP2013246099A
公开(公告)日：2013-12-09
申请号：JP2012121261
申请日：2012-05-28
申请人： Toshiba Corp , 株式会社東芝
发明人： TAWARA MIKA , AOKI KAZUYOSHI , HIOKI HIDEAKI , NAKAMARU MIKIHIDE , MURAKAMI KAZUO , MIYAGAWA TAKUYA , MISHIN SHIGEHIRO , TANABE MASASHI , OSAWA YASUO
IPC分类号： G21D3/08 , G21C9/00 , G21C9/04
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a technology for treating hydrogen locally accumulated in a nuclear reactor container.SOLUTION: A hydrogen treatment device 10 includes: a gas tank 14 which press-fits inert gas inside a nuclear reactor container 13 in which a nuclear reactor pressure vessel 12 for accommodating a reactor core 11 to which nuclear fuel is loaded is stored; and on-off valves 15 (15a, 15b) which make a pipeline communicating with the inside of the nuclear reactor container 13 from a closed state to an opened state by being synchronized with press-fit of the inert gas.
摘要翻译：要解决的问题：提供一种用于处理在核反应堆容器中局部积聚的氢的技术。解决方案：氢处理装置10包括：气体箱14，其将惰性气体压入核反应堆容器13内，其中核反应堆存储装载有核燃料的反应堆堆芯11的压力容器12; 以及通过与惰性气体的压入同步而使与核反应堆容器13的内部连通的管路的开关阀15（15a，15b）从关闭状态到打开状态。

3. 发明专利

JP2007205923A Nuclear power generation plant with boiling water reactor 有权
标题翻译：具有锅炉水反应堆的核能发电厂
公开(公告)号：JP2007205923A
公开(公告)日：2007-08-16
申请号：JP2006025717
申请日：2006-02-02
申请人： Japan Atom Power Co Ltd:The , Toshiba Corp , 日本原子力発電株式会社 , 株式会社東芝
发明人： NAKAMARU MIKIHIDE , KOJIMA YOSHIHIRO , ARAI KENJI , KUROKI MASAHIKO , HOSHINO KATSUYUKI , HOSHI TAKASHI , OTAKA KAZUHIRO , HIOKI HIDEAKI
IPC分类号： G21C15/18 , G21C9/004 , G21D3/04
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide an installation which attains the cooling of a reactor core and a reactor containment vessel over a long period during a piping rupture accident in a nuclear power generation plant with a boiling water reactor which has a reactor containment vessel of a highly pressure-resistant type.
SOLUTION: The installation is equipped with an emergency condensate system 19 for condensing the steam from a reactor containment vessel 2 and returning it to a reactor pressure vessel 3 again and an outside storage system 20 for storing the condensate from the emergency condensate system 19. The outside storage system 20 has an outside tank 34, a make-up water pipe 35 for cooling a reactor which pours water into the reactor pressure vessel 3 and a pipe 36 for submerging the reactor containment vessel 2 by pouring water into it. The height where the make-up water pipe 35 for cooling the reactor is connected to the reactor pressure vessel 3 and the outside tank 34 is set at the one different from the height where the pipe 36 for submerging the reactor containment vessel 2 is connected to the reactor containment vessel 2 and the outside tank 34. Force of gravitation drives and controls the amount of the water poured into the reactor pressure vessel 3, the timing of the start of the water pouring into the vessel 3, the amount of the water poured into the reactor containment vessel 2 and the timing of the start of the water pouring into vessel 2 respectively.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种在具有反应堆容纳的沸水反应堆的核发电厂中在管道破裂事故期间长时间冷却反应堆堆芯和反应堆容器的装置高耐压型容器。
解决方案：该装置配备有应急冷凝系统19，用于冷凝来自反应堆容纳容器2的蒸汽并将其再次返回到反应堆压力容器3，以及用于存储来自紧急冷凝系统的冷凝物的外部储存系统20 外部储存系统20具有外部罐34，用于冷却向反应堆压力容器3倒入水的反应器的补充水管35和通过向其中倒入水而将反应堆容纳容器2浸没的管36。将用于冷却反应器的补充水管35连接到反应堆压力容器3和外部箱34的高度被设定为与用于浸没反应堆容器2的管36连接的高度不同的高度反应堆容纳容器2和外部罐34.重力驱动并控制浇入反应堆压力容器3的水量，浇注到容器3中的水的开始时间，浇注的水量进入反应堆安全壳2以及分别开始注入容器2的水的时间。版权所有（C）2007，JPO＆INPIT

4. 发明专利

JP2013246100A Hydrogen treating system and hydrogen treating method 审中-公开
标题翻译：氢处理系统和氢处理方法
公开(公告)号：JP2013246100A
公开(公告)日：2013-12-09
申请号：JP2012121262
申请日：2012-05-28
申请人： Toshiba Corp , 株式会社東芝
发明人： TAWARA MIKA , HIOKI HIDEAKI , NAKAMARU MIKIHIDE , AOKI KAZUYOSHI , MURAKAMI KAZUO , MIYAGAWA TAKUYA , MISHIN SHIGEHIRO , TANABE MASASHI , OSAWA YASUO
IPC分类号： G21D3/08 , G21C9/00 , G21C9/04 , G21F9/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a system and a method that can quickly perform hydrogen treatment even when events in each of which a large quantity of hydrogen is generated simultaneously occur at a plurality of plants, while suppressing a maintenance and management load at normal time to a minimum.SOLUTION: A first hydrogen treating system 20A comprises: a blower 22 for sucking an atmosphere gas via taking-out piping 23a (23b) for taking out the atmosphere gas from a containment vessel 1 surrounding a reactor pressure vessel 3 accommodating a reactor core therein and an isolation valves 21a (21b) installed in the taking-out piping 23a (23b); an emergency power source 24A for supplying power to the blower 22; and portable containers 32 for guiding the gas introduced from an introduction port to a derivation port via hydrogen removal treating materials filled therein. The first hydrogen treating system 20A is provided with a flow passage that guides the atmosphere gas sucked by the blower 22 via connection piping 27 to the portable containers 32 and returns the atmosphere gas from which hydrogen is removed in the portable containers 32 to an inside of the containment vessel 1 via return piping 33 and isolation valves 34 installed in the return piping 33.
摘要翻译：要解决的问题：提供即使在多个工厂同时发生大量氢的事件的同时发生的事件也能够快速进行氢处理的系统和方法，同时抑制正常时的维护和管理负荷第一氢处理系统20A包括：鼓风机22，用于通过取出管道23a（23b）吸取气氛气体，用于从围绕反应堆压力容器3收容的容纳容器1取出气氛气体，反应堆核心和安装在取出管道23a（23b）中的隔离阀21a（21b）。用于向鼓风机22供电的应急电源24A; 以及便携式容器32，用于将从引入口引入的气体经由其中填充的除氢处理材料引导至衍生端口。第一氢处理系统20A设置有将通过连接管道27将鼓风机22吸入的气氛气体引导到便携式容器32的流路，并将从便携式容器32中的氢被除去的气氛气体返回到安全壳1通过返回管路33和安装在返回管路33中的隔离阀34。

5. 发明专利

JP2013246098A Combustible gas processing system and method of nuclear reactor building 审中-公开
标题翻译：可燃气体加工系统和核反应堆建筑方法
公开(公告)号：JP2013246098A
公开(公告)日：2013-12-09
申请号：JP2012121260
申请日：2012-05-28
申请人： Toshiba Corp , 株式会社東芝
发明人： TAWARA MIKA , KITAJIMA YASUKI , AOKI KAZUYOSHI , HIOKI HIDEAKI , NAKAMARU MIKIHIDE , MURAKAMI KAZUO , MIYAGAWA TAKUYA , MISHIN SHIGEHIRO , TANABE MASASHI , OSAWA YASUO , KOJIMA YOSHIHIRO
IPC分类号： G21D3/08 , G21C9/04 , G21C13/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a combustible gas processing technology by which soundness of a nuclear reactor building is secured even when hydrogen leaks in accordance with a nuclear plant accident.SOLUTION: A combustible gas processing system 10 of a nuclear reactor building includes: a nuclear reactor building 14 which surrounds a nuclear reactor container 13 in which a nuclear reactor pressure vessel 12 for accommodating a reactor core 11 to which nuclear fuel is loaded is stored; and a gas processing part 20 which is provided in a communication hole 17 communicating with vertical hierarchies of a section 16 obtained by partitioning an internal space of the nuclear reactor building 14 by a partition body 15 to make combustible gas incombustible.
摘要翻译：要解决的问题：提供可靠的气体处理技术，即使在核反应堆建筑物的氢气泄漏的情况下也能确保核反应堆建筑物的健全性。解决方案：核反应堆建筑物的可燃气体处理系统10包括：核反应堆建筑物14，其围绕核反应堆容器13，其中存储有用于容纳装载有核燃料的反应堆堆芯11的核反应堆压力容器12; 以及气体处理部20，其设置在与通过分隔体15分隔核反应堆14的内部空间而获得的部分16的垂直层次连通的连通孔17中，以使可燃气体不可燃。

6. 发明专利

JP2003270383A Atomic power using heat supply system 审中-公开
标题翻译：使用热源系统的原子力
公开(公告)号：JP2003270383A
公开(公告)日：2003-09-25
申请号：JP2002072521
申请日：2002-03-15
申请人： Toshiba Corp , 株式会社東芝
发明人： ITO ARATA , MIYAZAWA TATSUO , YOKOBORI SEIICHI , HIOKI HIDEAKI
IPC分类号： G21D9/00 , F24D3/00 , F24H1/00 , F24H1/18 , F28D20/00 , F28D20/02
CPC分类号： Y02E60/142 , Y02E60/145 , Y02E70/30
摘要： PROBLEM TO BE SOLVED: To provide a safe atomic power using heat supply system having high heat efficiency capable of supplying heat demand and cold demand in a large city. SOLUTION: This supply system is equipped with an atomic power system 5 for generating steam, a cold system 10 for generating a cold medium by using the steam, a thermal system 11 for generating a thermal medium by using the steam, and a heat supply sub-center 12 for receiving and storing the cold medium and the thermal medium, and supplying a city building 3 therewith. The supply system is constituted so that the atomic power system 5, the cold system 10 and the thermal system 11 are provided in a cavity bored in a rock mass 1 in the underground of the city, and that the heat supply sub-center 12 is provided under the ground surface. COPYRIGHT: (C)2003,JPO
摘要翻译：要解决的问题：使用具有高热效率的供热系统来提供安全的原子能，能够在大城市中提供热量需求和冷需求。解决方案：该供应系统配备有用于产生蒸汽的原子动力系统5，用于使用蒸汽产生冷介质的冷系统10，通过使用蒸汽产生热介质的热系统11和供热中心12，用于接收和存储冷媒和热介质，并向其提供城市建筑3。供给系统构成为使得原子能系统5，冷系统10和热系统11设置在钻孔在城市地下岩体1中的空腔中，供热中心12为提供在地面下。版权所有（C）2003，JPO

7. 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

8. 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

9. 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

10. 发明专利

JP2002080858A RADIATION-IRRADIATED COAL LIQUEFACTION PLANT 失效
公开(公告)号：JP2002080858A
公开(公告)日：2002-03-22
申请号：JP2000274256
申请日：2000-09-11
申请人： TOSHIBA CORP
发明人： ITO ARATA , HIRONO HIDEJI , TAKEUCHI YUTAKA , SUMIYAMA SHIGEAKI , HIOKI HIDEAKI , MIYAZAWA TATSUO
IPC分类号： G21C1/00 , C10G1/00 , C10G1/02 , G21G1/02 , G21H5/00
摘要： PROBLEM TO BE SOLVED: To provide a radiation-irradiated coal liquefaction plant which can efficiently liquefy coal at a high safeness while using excess thermal neutron produced in a nuclear reactor as a heat source and can accomplish the load leveling of a nuclear power generation system. SOLUTION: This plant is equipped with a nuclear power generation system 1 having a thermal neutron irradiation apparatus 8 which is arranged in a pressure container or a screening body of a nuclear reactor 5 generating steam for driving a power generation turbine or a high-temperature high-pressure gas and which forms an artificial radioactive isotope from a radioactive isotope- forming material by the irradiation with thermal neutron; a coal slurry preparation section 2 for preparing a coal slurry by mixing the above-formed artificial radioactive isotope with a coal powder, a solvent, and a catalyst; and a coal liquefaction system 3 for heating, liquefying, and decomposing the coal slurry prepared by the coal slurry preparation section and for separating the resultant decomposition product.

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