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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

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.

4. 发明专利

JP2001280104A ELECTRIC POWER PLANT 失效
公开(公告)号：JP2001280104A
公开(公告)日：2001-10-10
申请号：JP2000097015
申请日：2000-03-31
申请人： TOSHIBA CORP
发明人： ITO ARATA , HIOKI HIDEAKI , KONO SHUNJI , MARUME TAKAYUKI , OGATA TOMOKO
IPC分类号： F01K25/10 , F01K23/02 , F01K25/00
摘要： PROBLEM TO BE SOLVED: To improve power generating efficiency, by operating a mixed medium turbine so that an exhaust temperature of the mixed medium turbine is not more than a sea water temperature or an atmospheric temperature and by heating mixed medium liquid by low temperature exhaust heat such as sea water, atmosphere, or the like. SOLUTION: An electric power plant is provided with: a heating apparatus 8 heating mixed medium including low boiling point medium; a gas-liquid separator 10 separating the mixed medium into high concentration mixed medium steam and low concentration mixed medium steam; the mixed medium turbine 11 driven by the separated high concentration mixed medium steam; a vapor condenser device 14 cooling and returning mixed fluid of the mixed medium turbine exhaust and the low concentration mixed medium; a heat exchanger 18 heat-exchanging the returned mixed medium with the sea water or the atmosphere; a condenser 21 condensing at least part of the high concentration mixed medium steam separated in the gas-liquid separator 10; and a supercooling device 13 supercooling cooling fluid by using coolant formed by adiabatic expansion of the condensed medium. The supercooled fluid supercooled by the supercooling device 13 is supplied to the liquid returning device 14 as cooling medium.

5. 发明专利

JPH0363599A PROCESSING METHOD FOR DISMANTLED BODY SUCH AS RADIO-ACTIVELY CONTAMINATED EQUIPMENT AND ITS TRANSPORTATION CONTAINER 失效
公开(公告)号：JPH0363599A
公开(公告)日：1991-03-19
申请号：JP19929589
申请日：1989-08-02
申请人： TOSHIBA CORP
发明人： FURUMURA SHIRO , HIOKI HIDEAKI
IPC分类号： G21F5/002 , G21F5/005 , G21F9/28 , G21F9/36
摘要： PURPOSE:To decontaminate a metallic material by injecting decontaminating liquid into the transportation container which contains the dismantled body such as the radioactively contaminated equipment and carrying the container in processing facilities,and cleaning the dismantled body in the transportation container after the waste liquid of the decontaminating liquid is discharged. CONSTITUTION:The radioactively dismantled equipment which is removed from atomic power utilizing facilities is processed by cutting, etc., in a dismantling process 1 and stored divisionally in transportation containers by proper quantities in a transportation container storing process 2. Then each transportation container containing the dismantled body is reduced in pressure in a vacuum sucking process 18 and the decontaminating liquid is charged suctionally in a decontaminating liquid injecting process 19. In an in-plant transporting process 4, the container is transported to processing facilities 51 together with the decontaminating liquid and then passed through a decontaminating liquid discharging process 20 and a cleaning process 21 right after reaching the processing facilities 51, and the dismantled body is taken out of the container, which is reused. The dismantled body is stored after a general disposal process 15, reutilization process 16, or radioactivity-level-classified processing process 17 according to the residual radioactivity level of a radioactivity measuring and discriminating process 14.

6. 发明专利

JPH01176996A DEVICE FOR CUTTING AND DISASSEMBLING FUEL ASSEMBLY OR THE LIKE 失效
公开(公告)号：JPH01176996A
公开(公告)日：1989-07-13
申请号：JP4288
申请日：1988-01-04
申请人： TOSHIBA CORP , NIPPON ATOMIC IND GROUP CO
发明人： FURUMURA SHIRO , HIOKI HIDEAKI , KATO HIROAKI
IPC分类号： G21C19/37 , G21C19/36
摘要： PURPOSE:To improve efficiency by providing a gripping mechanism to grip a material to be cut in different two positions and a cutting mechanism to cut said material between the two pinching positions to supporting arms thereby inserting and removing the cutting mechanism between the pinching positions. CONSTITUTION:The gripping mechanism 32 for gripping a fuel assembly 31 and the cutting mechanism 33 for cutting the assembly 31 are provided to the free ends of the supporting arms 34, 35 of the title device 30. The mechanism 33 is constituted by housing a disk-shaped grinding wheel cutter 49 freely rotatably in a cutter bar 48 fixed to the free end of the arm 35. The device 30 is moved between a disassembly working tower 37 and a disassembled waste housing container 38 by a rotational moving mechanism provided to the base part of the arms 34, 35 and the cutter 49 is pressed to the assembly 31 gripped by the gripers 43 of the mechanism 32 while said cutter is kept rotated between the upper and lower gripping positions, by which the assembly is cut. The cutting is, therefore, efficiently executed.

7. 发明专利

JPS6484200A TREATMENT SYSTEM FOR RADIOACTIVE WASTE 失效
公开(公告)号：JPS6484200A
公开(公告)日：1989-03-29
申请号：JP24320487
申请日：1987-09-28
申请人： TOSHIBA CORP , NIPPON ATOMIC IND GROUP CO
发明人： FURUMURA SHIRO , HIOKI HIDEAKI
IPC分类号： G21F9/30 , G21F9/28
摘要： PURPOSE:To reduce the cost of disposition by respectively discriminating and disposing waste of a high radioactivity level, waste of an extremely low level, metal waste decontaminated down to a prescribed level, and concrete waste. CONSTITUTION:The radioactive waste accepted in an acceptance treatment stage 1 is discriminated to the radioactive metals and the concrete waste. The metal waste is subjected to measurement and discrimination of the radioactivity level and the kinds of radioactivity in a measurement processing stage 2. The metal waste discriminated to general waste is disposed 5. Of the waste discriminated as the radioactive metal waste, the decontaminatable waste is sent to a decontamination treatment stage 3 and the nondecontaminatable waste is sent to a container packing stage 6 or simple disposition 8. The waste sent to the stage 3 is subjected to the decontamination treatment and is sent to the measurement processing stage 4 where the radioactivity level thereof is again measured. As a result, the waste decontaminated down to the prescribed radioactivity level is disposed 5. The waste failing to be decontaminated down to the prescribed level is sent to the stage 6 and is disposed 7. The waste of the extremely low level is disposed 8.

8. 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

9. 发明专利

JP2002122686A BOILING WATER TYPE NUCLEAR POWER PLANT, AND CONSTRUCTION METHOD THEREOF 失效
公开(公告)号：JP2002122686A
公开(公告)日：2002-04-26
申请号：JP2000317169
申请日：2000-10-17
申请人： TOSHIBA CORP
发明人： NAKAMARU MIKIHIDE , HIOKI HIDEAKI , SAITO TAKEHIKO , HIRAIWA KOJI , NARABAYASHI SUNAO , OMIZU SATOSHI , SHIMODA TSUYOSHI , ARAI KENJI , MOROOKA SHINICHI , SUZUKI SEIJIRO
IPC分类号： G21C9/004 , G21C1/08 , G21C5/00 , G21C7/08 , G21C9/00 , G21C13/00 , G21C15/18 , G21D1/02
摘要： PROBLEM TO BE SOLVED: To provide a compact amd economical nuclear power plant. SOLUTION: A reactor core 202 comprising a reactor core supporting plate 204, an upper grating plate 205 and a fuel assembly 206 supported by them is provided in an inner bottom part of a reactor pressure vessel 201, a control rod guiding cylinder 213 and a reactor core shroud 203 are arranged on the grating plate, a control rod driving mechanism 211 is provided further thereon, a control rod 212 is allowed thereby to be inserted from an upper pert of the reactor core, and natural circulation in a reactor of cooling water is also allowed by a chimney effect of the control rod guiding cylinder.

10. 发明专利

JP2001235585A REGIONAL COGENERATION SYSTEM 失效
公开(公告)号：JP2001235585A
公开(公告)日：2001-08-31
申请号：JP2000047662
申请日：2000-02-24
申请人： TOSHIBA CORP
发明人： ITO ARATA , YOKOBORI SEIICHI , MIYAZAWA TATSUO , HIOKI HIDEAKI
IPC分类号： G21D5/04 , F25B15/00 , G21D9/00
摘要： PROBLEM TO BE SOLVED: To provide a regional cogeneration system supplying the hot heat and cold heat to the region and enhancing the total heat efficiency of a nuclear power generation plant. SOLUTION: This regional cogeneration system is provided with a nuclear power generating system 1 having a heat exchanger 11 supplied branched steam generated in a nuclear reactor 6 and introduced to a steam turbine 7 for driving a power generator 8, a steam storage tank 13 installed in a place separated from the nuclear power generating system 1 and receiving and storing the steam generated from circulating water for exchanging the heat in the heat exchanger 11 of the nuclear power generating system 1, a storage steam power generating system 2 having a steam turbine 14 for power generation driven using the steam stored in the steam storage tank 13, and a regional heat supply system 3 supplied the circulating water for exchanging the heat with exhaust of the steam turbine 14 of the storage steam power generating system 2.

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