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1. 发明专利

JP2010064074A Method and apparatus for treating ammonia-containing regeneration waste liquid from condensate demineralizer 审中-公开
标题翻译：用于处理含有氨的再生废液的方法和装置
公开(公告)号：JP2010064074A
公开(公告)日：2010-03-25
申请号：JP2009277428
申请日：2009-12-07
申请人： Hitachi-Ge Nuclear Energy Ltd , Japan Atom Power Co Ltd:The , 日本原子力発電株式会社 , 日立Geニュークリア・エナジー株式会社
发明人： AIZAWA MOTOHIRO , FUSE MOTOMASA , WADA YOICHI , ISHIDA KAZUNARI , KADOI HIDEKAZU , NAGATA NOBUAKI , SHIMADA KEIJI
IPC分类号： C02F9/00 , B01D19/00 , B01D53/86 , B01D61/44 , C02F1/04 , C02F1/20 , C02F1/469 , G21C19/307 , G21D1/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide equipment for separating and decomposing ammonia formed from a reductive nitrogen compound in a plant where the reductive nitrogen compound is injected to inhibit corrosion of structural materials in a nuclear reactor. SOLUTION: There is provided a method for treating an ammonia-containing regeneration waste liquid discharged when a condensate demineralizer in a nuclear power plant is regenerated, which includes the steps of: adding an alkali to the ammonia-containing regeneration waste liquid discharged; separating ammonia in the vapor phase by aeration under heating; and decomposing the formed ammonia gas with a catalyst. COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：提供在还原氮化合物被注入的工厂中由还原性氮化合物形成的氨分离和分解设备，以抑制核反应堆中结构材料的腐蚀。解决方案：提供了一种在再生核电站中的冷凝水脱盐装置时，处理排出的含氨的再生废液的方法，包括以下步骤：向含有氨的再生废液中排出碱 ; 通过加热曝气在气相中分离氨; 并用催化剂分解形成的氨气。版权所有（C）2010，JPO＆INPIT

2. 发明专利

JP2008070207A Stress corrosion crack mitigation method of reactor structure material, and boiling water type nuclear power plant 有权
标题翻译：反应器结构材料应力腐蚀裂缝减缓方法和锅炉水型核电厂
公开(公告)号：JP2008070207A
公开(公告)日：2008-03-27
申请号：JP2006248505
申请日：2006-09-13
申请人： Hitachi-Ge Nuclear Energy Ltd , Japan Atom Power Co Ltd:The , 日本原子力発電株式会社 , 日立Geニュークリア・エナジー株式会社
发明人： ISHIDA KAZUNARI , WADA YOICHI , TACHIBANA MASAHIKO , NAGASE MAKOTO , AIZAWA MOTOHIRO , TAKIGUCHI HIDEKI , KADOI HIDEKAZU , NAGATA NOBUAKI , OHIRA HIROSHI
IPC分类号： G21D1/00 , G21C19/307 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a stress corrosion crack mitigation method of a reactor structure material capable of suppressing increase of a dose rate by N-16, and suppressing easily increase of an electric conductivity generated by by-products.
SOLUTION: Hydrazine or hydrazine and hydrogen are injected into reactor water of a boiling water type nuclear power plant until ammonia is generated, and the injection quantity into the reactor water of a compound discharging anions and oxonium ions by action of heat or a radiation is adjusted based on the ammonia concentration. Hereby, the electric conductivity which is one factor for accelerating a stress corrosion crack can be reduced, and the stress corrosion crack of the reactor structure material can be suppressed, and the operation rate of the nuclear power plant can be improved.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：提供能够抑制N-16剂量率增加的反应器结构材料的应力腐蚀裂纹缓解方法，并且抑制由副产物产生的电导率的容易增加。解决方案：将肼或肼和氢气注入沸水型核动力装置的反应器水中，直至产生氨，并且通过加热或a的作用将化合物排出阴离子和氧鎓离子的化合物的反应器水中的注入量基于氨浓度调节辐射。由此，可以降低作为加速应力腐蚀开裂的一个因素的电导率，可以抑制反应堆结构材料的应力腐蚀裂纹，提高核电厂的运行率。版权所有（C）2008，JPO＆INPIT

3. 发明专利

JP2007147453A Method and device for processing ammonia-containing regenerated waste solution from condensate demineralizer 审中-公开
标题翻译：用于处理含有氨的再生废物溶液的方法和装置
公开(公告)号：JP2007147453A
公开(公告)日：2007-06-14
申请号：JP2005342452
申请日：2005-11-28
申请人： Hitachi Ltd , Japan Atom Power Co Ltd:The , 日本原子力発電株式会社 , 株式会社日立製作所
发明人： AIZAWA MOTOHIRO , FUSE MOTOMASA , WADA YOICHI , ISHIDA KAZUNARI , KADOI HIDEKAZU , NAGATA NOBUAKI , SHIMADA KEIJI
IPC分类号： G21C19/307 , B01D19/00 , B01J23/42 , B01J23/86 , C02F1/04 , C02F1/20 , C02F1/44 , C02F1/469 , G21D1/02
CPC分类号： Y02A20/128 , Y02A20/131 , Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method for reducing the quantity of radioactive waste produced, by effectively removing ammonia in a regenerated waste solution, in processing the regenerated waste solution coming from a demineralizer of a nuclear power plant.
SOLUTION: The processing method for the ammonia-containing regenerated waste solution discharged when a condensate demineralizer of the nuclear power plant is regenerated comprises the steps of alkalizing the used ammonia-containing regenerated waste solution discharged, blowing air under a heating condition to separate ammonia in vapor phase and decomposing the ammonia gas obtained in the previous step by using a catalyst.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种通过有效地除去再生废液中的氨来减少产生的放射性废物的量的方法，用于处理来自核电站的脱盐装置的再生废液。解决方案：在再生核电站的冷凝水脱盐装置时排出的含氨废水再生废液的处理方法包括将排出的废氨水再生废液碱化，在加热条件下吹入空气的步骤为分离出气相中的氨，并通过使用催化剂分解前一步中得到的氨气。版权所有（C）2007，JPO＆INPIT

4. 发明专利

JP2012073118A Laundry waste liquid processing method 有权
标题翻译：洗衣液废液处理方法
公开(公告)号：JP2012073118A
公开(公告)日：2012-04-12
申请号：JP2010218200
申请日：2010-09-29
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： MATSUBARA HIROFUMI , AIZAWA MOTOHIRO , FUJITA KAZUHIRO , KAWASAKI TORU , INOUE HITOSHI
IPC分类号： G21F9/08 , C02F1/04 , C02F1/42 , C02F1/469 , G21F9/06 , G21F9/12
摘要： PROBLEM TO BE SOLVED: To provide a laundry waste liquid processing method capable of preventing foam formation caused by evaporative concentration of laundry waste liquid containing nonionic surface active agent.SOLUTION: An ion exchange resin tower 26 filled with a cation exchange resin receives a laundry waste liquid discharged from a laundry waste liquid collecting tank 2 and containing nonionic surface active agent and higher fatty acid, higher alcohol, and sweats (salt content) eluted from clothing during laundry. The cation exchange resin eliminates cationic components (Na ion, for example) contained in the laundry waste liquid, and the pH of the laundry waste liquid drops. When the laundry waste liquid pH falls within the range of 3.0 to 7.5 as a result of having the laundry waste liquid circulated between the laundry waste liquid collecting tank 2 and the ion exchange resin tower 26, a supply of the laundry waste liquid to the ion exchange resin tower 26 is stopped, and the laundry waste liquid is supplied from the laundry waste liquid collecting tank 2 to a heater 7, and is heated in the heater 7 before being supplied to a concentration can 5. When the laundry waste liquid pH indicates 6.0 for example, the laundry waste liquid with pH 6.0 is evaporatively concentrated in the concentration can 5.
摘要翻译：解决的问题：提供一种能够防止由含有非离子表面活性剂的衣物废液的蒸发浓缩引起的泡沫形成的洗衣废液处理方法。解决方案：填充有阳离子交换树脂的离子交换树脂塔26接收从衣物废液收集罐2排出并含有非离子表面活性剂和高级脂肪酸，高级醇和汗液的洗衣废液（盐含量）在衣物洗脱时洗脱。阳离子交换树脂消除了洗衣废液中含有的阳离子成分（例如Na离子），衣物废液的pH下降。当衣物废液在洗涤废液收集罐2和离子交换树脂塔26之间循环时，洗涤废液pH落在3.0〜7.5的范围内时，洗衣废液向离子的供给交换树脂塔26停止，衣物废液从洗涤废液收集箱2供给到加热器7，并在加热器7中加热至浓缩罐5.当洗衣废液pH值表示 6.0，例如，pH 6.0的洗衣废液在浓缩罐5中蒸发浓缩。版权所有（C）2012，JPO＆INPIT

5. 发明专利

JP2011047960A Method for reducing radiation exposure in nuclear power plant, nuclear power plant and fuel assembly 有权
标题翻译：核电厂，核电厂和燃料装置减少辐射暴露的方法
公开(公告)号：JP2011047960A
公开(公告)日：2011-03-10
申请号：JP2010271384
申请日：2010-12-06
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： ISHIDA KAZUNARI , HOSOKAWA HIDEYUKI , WADA YOICHI , AIZAWA MOTOHIRO , NAGASE MAKOTO , FUSE MOTOMASA , USUI NAOSHI
IPC分类号： G21C3/06 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method for reducing radiation exposure in a nuclear power plant which can further reduce radiation exposure, even when the degree of burnup of fuel assemblies is further increased. SOLUTION: A BWR plant 1 includes a core 4 loaded with fuel assemblies 5, and feed-water pipes 9 which are connected to a condenser 8 and a reactor pressure vessel (RPV)3 and where a hollow filter 10 is placed. The placement of the hollow filter 10 restrains the concentration of iron oxide in the feed-water supplied into the RPV 3 to 1×10 -9 mol/kg or less. A ferrite coating is formed on the outside face of a clad tube used for each fuel rod included in the fuel assemblies 5, before the core 4 is loaded with the fuel assemblies. Cobalt oxide in reactor water adhered to the ferrite coating is exfoliated from the outside face of the cladding tube by the electrostatic repulsive force generated between the cobalt oxide and triiron tetraoxide contained in the ferrite coating. For this reason, nonradioactive cobalt is restrained from activation on the outside face of the clad tube and reduces the concentration of radioactive cobalt in the reactor water. COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：即使当燃料组件的燃耗程度进一步提高时，提供一种可以进一步减少辐射暴露的减少核电站辐射暴露的方法。解决方案：BWR设备1包括装载有燃料组件5的核心4和连接到冷凝器8和反应堆压力容器（RPV）3并且其中放置中空过滤器10的给水管9。中空过滤器10的放置将供给到RPV 3的供给水中的氧化铁的浓度抑制到1×10 -6 SPO / kg以下。在核心4装载燃料组件之前，在包括在燃料组件5中的每个燃料棒的包覆管的外表面上形成铁氧体涂层。在铁氧体涂层中包含的钴氧化物和四氧化三铁之间产生的静电排斥力使附着在铁素体涂层上的反应器水中的氧化钴从包覆管的外表面剥离。因此，在放电管的外表面抑制非放射性钴的活化，降低反应器水中的放射性钴的浓度。版权所有（C）2011，JPO＆INPIT

6. 发明专利

JP2012108059A Performance evaluation method of recombiner and performance evaluation device thereof 审中-公开
标题翻译：重组器性能评估方法及其性能评估装置
公开(公告)号：JP2012108059A
公开(公告)日：2012-06-07
申请号：JP2010258443
申请日：2010-11-19
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： IIZUKA HIDEHIRO , AIZAWA MOTOHIRO , KAWASAKI TORU , MATSUBARA HIROFUMI , NISHI TAKASHI , SUGANO SHUICHI , YOSHII YASUO , KUMAGAI NAOKI
IPC分类号： G21C17/003
摘要： PROBLEM TO BE SOLVED: To provide a performance evaluation method of a recombiner capable of accurately evaluating performance degradation of a recombined catalyst where silicon is accumulated.SOLUTION: A performance evaluation method includes: a step (S1) for inserting an X-ray fluorescence spectrometer into a recombiner provided at offgas system piping to measure a fluorescent X-ray emitted from an upper end face of a catalyst layer in the recombiner, and using the fluorescence X-ray to determine each weight of silicon and Pt in D5 attached to a catalyst; a step (S2) for calculating a Si/Pt weight ratio α; a step (S3) for using a correlation between the Si/Pt weight ratio and a performance degradation ratio of the recombiner to obtain the performance degradation ratio β of the recombiner to the calculated Si/Pt weight ratio α; a step for determining whether or not β is less than β0 (β0 is a value set for the performance degradation ratio); a step for, when β is less than β0, continuing using the catalyst in the recombiner; and a step for, when β is not less than β0, replacing the catalyst in the recombiner.
摘要翻译：要解决的问题：提供能够精确评估聚集硅的重组催化剂的性能劣化的重组器的性能评价方法。解决方案：性能评估方法包括：步骤（S1），用于将X射线荧光光谱仪插入到在废气系统管线处提供的重组器中，以测量从催化剂层的上端面发射的荧光X射线重组器，并使用荧光X射线来确定连接到催化剂的D5中硅和Pt的每个重量; 用于计算Si / Pt重量比α的步骤（S2）; 使用Si / Pt重量比与重组器的性能降低率之间的相关性以获得重组器的性能降解率β与计算的Si / Pt重量比α的步骤（S3）; 确定β是否小于β0的步骤（β0是针对性能降低率设定的值）; 当β小于β0时，在重组器中继续使用催化剂的步骤; 并且当β不小于β0时，代替重组器中的催化剂。版权所有（C）2012，JPO＆INPIT

7. 发明专利

JP2012052807A Method for monitoring catalytic performance of recombiner 有权
标题翻译：监测重组蛋白催化性能的方法
公开(公告)号：JP2012052807A
公开(公告)日：2012-03-15
申请号：JP2010193065
申请日：2010-08-31
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： KUMAGAI NAOKI , IIZUKA HIDEHIRO , AIZAWA MOTOHIRO , KAWASAKI TORU , MATSUBARA HIROFUMI
IPC分类号： G21F9/02 , B01D53/86 , C01B5/00
摘要： PROBLEM TO BE SOLVED: To know performance deterioration of a recombining catalyst before a hydrogen concentration rises at the outflow port of an exhaust gas recombiner to predict the timing required for the replacement of the recombining catalyst.SOLUTION: A method includes: disposing a temperature sensor inside a recombining catalyst contained in an exhaust gas recombiner; comparing temperature measured by the sensor with a temperature predicted from the flow-rate and hydrogen concentration of an exhaust gas flowing in the recombiner or with an exhaust gas temperature measured at an outflow port; monitoring an indication of deterioration of a catalytic performance before the performance of the entire recombining catalyst is deteriorated and the hydrogen flows downstream; and predicting timing required for the replacement of the recombining catalyst and using a time elapsed until detecting an indication of the deterioration of the catalytic performance.
摘要翻译：要解决的问题：为了了解在废气重组器的流出口处的氢浓度升高之前的重组催化剂的性能劣化，以预测重组催化剂的替换所需的时间。解决方案：一种方法包括：将温度传感器置于包含在废气重组器中的重组催化剂内; 将由传感器测量的温度与从重组器中流动的废气的流量和氢浓度预测的温度或在流出口处测量的废气温度进行比较; 监测在整个重组催化剂的性能恶化之前催化性能恶化的指示，并且氢气流向下游; 并预测更换重组催化剂所需的时间，并且使用经过一段时间直到检测到催化性能劣化的指示。版权所有（C）2012，JPO＆INPIT

8. 发明专利

JP2011203035A Nuclear power plant with boiling water reactor 有权
标题翻译：核电厂与锅炉水反应堆
公开(公告)号：JP2011203035A
公开(公告)日：2011-10-13
申请号：JP2010069278
申请日：2010-03-25
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： AIZAWA MOTOHIRO , IIZUKA HIDEHIRO , YOSHII YASUO , NISHI TAKASHI , SUGANO SHUICHI , KAWASAKI TORU , MATSUBARA HIROFUMI
IPC分类号： G21D1/02 , G21C19/303 , G21F9/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear power plant with a boiling water reactor, capable of improving the performance of a catalyst in a recombiner placed on an off-gas system, even when a gas exhausted from a capacitor contains organic compounds containing silicon atoms.SOLUTION: The recombiner 9 is placed in a pipe on the off-gas system connected to the capacitor. As to the recombiner 9, a catalyst layer 11 filled with a Pt catalyst and a γ alumina layer 12 filled with granular γ alumina are set up in a container 10. The γ alumina layer 12 is located upstream from the catalyst layer 11. A gas containing hydrogen, oxygen and siloxane flows into the catalyst layer 11 from the capacitor to the pipe on the off-gas system. The hydrogen and oxygen contained in the gas are recombined into water by the Pt catalyst in the catalyst layer 11. This recombination decreases the hydrogen concentration in the gas exhausted from the recombiner 9 to an allowable value or lower.
摘要翻译：要解决的问题：即使当从电容器排出的气体含有含有硅原子的有机化合物时，为了提供具有沸水反应器的核电厂，能够提高放置在废气系统上的重组器中的催化剂的性能解决方案：将重组器9放置在连接到电容器的废气系统的管道中。对于重组器9，将装有Pt催化剂的催化剂层11和填充有粒状γ氧化铝的γ氧化铝层12设置在容器10中.γ氧化铝层12位于催化剂层11的上游。气体含有氢，氧和硅氧烷的液体从电容器流到催化剂层11至废气系统中的管道。气体中所含的氢和氧通过催化剂层11中的Pt催化剂重新结合在水中。该复合将从重组器9排出的气体中的氢浓度降低到允许值以下。

9. 发明专利

JP2010175416A Corrosion potential sensor 有权
标题翻译：腐蚀潜在传感器
公开(公告)号：JP2010175416A
公开(公告)日：2010-08-12
申请号：JP2009018947
申请日：2009-01-30
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： ISHIDA KAZUNARI , WADA YOICHI , TACHIBANA MASAHIKO , FUSE MOTOMASA , USUI NAOSHI , AIZAWA MOTOHIRO , OTA NOBUYUKI
IPC分类号： G01N17/04 , G01N27/26 , G21C17/02
CPC分类号： G21C17/022 , G01N17/04
摘要： PROBLEM TO BE SOLVED: To provide a corrosion potential sensor for extending a lifetime.
SOLUTION: The corrosion potential sensor 10 is provided with an electrode cap 11, an electrode fixing element 12, a pipe insulator 15, a pipe metal housing 18, and a conductor 19. The electrode fixing element 12 and the pipe metal housing 18 are connected to both ends of the pipe insulator 15, respectively. The conductor 19 passes though the pipe insulator 15 and the pipe metal housing 18, and is connected to the inner surface of the electrode fixing element 12. The electrode cap 11 is installed so as to cover a liquid contact surface of the electrode fixing element 12. By this, the problem can be solved.
COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：提供一种延长使用寿命的腐蚀电位传感器。腐蚀电位传感器10设置有电极帽11，电极固定元件12，管绝缘体15，管金属壳体18和导体19.电极固定元件12和管金属壳体 18分别连接到管道绝缘子15的两端。导体19穿过管绝缘体15和管金属壳体18，并连接到电极固定元件12的内表面。电极帽11被安装成覆盖电极固定元件12的液体接触表面由此可以解决问题。版权所有（C）2010，JPO＆INPIT

10. 发明专利

JP2014044190A Method for adhering noble metal to component member of nuclear power plant 有权
标题翻译：将金属焊接到核电厂组件成员的方法
公开(公告)号：JP2014044190A
公开(公告)日：2014-03-13
申请号：JP2012249031
申请日：2012-11-13
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： ITO TAKESHI , HOSOKAWA HIDEYUKI , NAGASE MAKOTO , WADA YOICHI , ISHIDA KAZUNARI , AIZAWA MOTOHIRO
IPC分类号： G21D1/00 , G21F9/28
CPC分类号： G21C19/32 , G21C17/0225 , G21D1/00 , G21F9/06 , G21F9/12 , G21F9/30 , Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method for suppressing adhesion of radionuclide to the component member of a nuclear power plant which can shortens a time required for chemical decontamination of the surface of the component member of the nuclear power plant and the construction of noble metal adhesion on the surface.SOLUTION: When a nuclear power plant is stopped before activating the nuclear power plant, a noble metal injection device is connected to a piping system of the nuclear power plant (S1). Oxidization decontamination, oxidization decontamination agent decomposition, and reduction decontamination of the internal surface of this piping system are executed (S2). After the completion of the reduction decontamination, a part of oxalic acid contained in a reduction decontamination liquid is decomposed, and platinum is injected into the reduction decontamination liquid with a pH of 3.5 or more (S4). When platinum density reaches a set density, a reduction agent is injected, and the reduction decontamination liquid including platinum and the reduction agent is made contact with the internal surface of the piping system (S6). Platinum is adhered to the internal surface of the piping system. The injection of platinum and the reduction agent is stopped (S7), and platinum and the reduction agent are decomposed (S8). After the purification and the waste liquid processing, the nuclear power plant is activated.
摘要翻译：要解决的问题：提供一种抑制放射性核素与核电站的部件的粘附的方法，其能够缩短核电站的部件的表面的化学去污所需的时间和贵金属的构造表面上的附着力。解决方案：核电厂在启动核电厂前停机，将贵金属注入装置连接到核电厂的管道系统（S1）。执行氧化去污，氧化去污剂分解和该管道系统内表面的还原净化（S2）。在还原去污完成后，还原去污液中含有的草酸的一部分被分解，并将铂注入pH为3.5以上的还原去污液中（S4）。当铂密度达到设定密度时，注入还原剂，并且将包含铂和还原剂的还原性去污液与管道系统的内表面接触（S6）。白金附着在管道系统的内表面。停止注入铂和还原剂（S7），并将铂和还原剂分解（S8）。经过净化和废液处理，核电站被激活。

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