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1. 发明授权

US06408041B2 In-core fixed nuclear instrumentation system and power distribution monitoring system 有权
标题翻译：核心固定核仪表系统和配电监控系统
公开(公告)号：US06408041B2
公开(公告)日：2002-06-18
申请号：US09876029
申请日：2001-06-08
申请人： Koji Hirukawa
发明人： Koji Hirukawa
IPC分类号： G21C1700
CPC分类号： G21C17/108
摘要： In an in-core fixed nuclear instrumentation system for a reactor, each of a plurality of in-core nuclear instrumentation assemblies has a nuclear instrumentation tube. LPRM detectors are housed in the nuclear instrumentation tube for detecting LPRM signal in a core of the reactor. A GT assembly is housed in the tube. The GT assembly has fixed GT detectors for detecting &ggr;-ray heating values and a built-in heater therein for calibrating the fixed GT detectors. The fixed GT detectors are arranged at least close to the fixed LPRM detectors, respectively. GT signals by the detected &ggr;-ray heating values of the fixed GT detectors of each GT assemblies are processed by a GT signal processing unit. The heater in each GT assemblies is electrically energized by a GT heater control unit. Predetermined time intervals are stored in a memory unit. One of the predetermined time intervals for specified &ggr;-ray thermometer assemblies, respectively is selected so that the GT heater control unit controls an electrical energy supplied to the heater by the selected interval so as to heat the heater, thereby executing a heater calibration of output voltage sensitivities of the fixed GT detectors of the GT assembly.
摘要翻译：在用于反应堆的核心固定核仪表系统中，多个核心核仪表组件中的每一个具有核仪器管。 LPRM探测器安装在核仪表管中，用于检测反应堆核心中的LPRM信号。 GT组件安装在管中。 GT组件具有用于检测伽马射线加热值的固定GT检测器和用于校准固定GT检测器的内置加热器。固定的GT检测器分别至少靠近固定的LPRM探测器。通过GT信号处理单元处理每个GT组件的固定GT检测器的检测伽马射线加热值的GT信号。每个GT组件中的加热器由GT加热器控制单元供电。预定时间间隔存储在存储器单元中。分别选择指定的伽马射线温度计组件的预定时间间隔之一，使得GT加热器控制单元以供选择的间隔来控制供给加热器的电能，以加热加热器，由此执行加热器校准输出 GT组件的固定GT检测器的电压灵敏度。

2. 发明授权

US5267286A Fuel assembly and reactor core 失效
标题翻译：燃料组件和反应堆堆芯
公开(公告)号：US5267286A
公开(公告)日：1993-11-30
申请号：US910846
申请日：1992-07-06
申请人： Koji Hirukawa
发明人： Koji Hirukawa
IPC分类号： G21C3/32 , G21C3/322 , G21C3/33 , G21C3/334 , G21C5/00 , G21C5/16 , G21C7/27 , G21C7/32 , G21C1/04
CPC分类号： G21C3/322 , G21C7/113 , G21C7/117 , G21C7/27 , G21Y2002/201 , G21Y2004/302 , G21Y2004/304 , Y02E30/38 , Y02E30/39
摘要： A fuel assembly having a water cross or water rod arranged between the fuel rods, an inside of the water cross or water rod being divided into a coolant rising passage and a coolant lowering passage, and a control guide tube disposed inside the water cross or water rod and extending along an axial direction of the water cross or water rod. The coolant rising passage has a coolant inlet port formed to a portion above or under a portion at which the fuel rods are supported by the lower tie plate. The control element guide tube has a coolant outlet port formed at that portion so that a coolant introduced into the coolant rising passage flows vertically upwardly, then turns and flows downwardly along the control element guide tube, and flows into an inside thereof through the coolant outlet port. A reactor core comprises a plurality of fuel assemblies each having a structure described above, a control rod and a control element operated in association with the control rod.
摘要翻译：一种具有布置在燃料棒之间的水交叉或水杆的燃料组件，水交叉或水杆的内部被分成冷却剂升高通道和冷却剂下降通道，以及设置在水交叉或水中的控制引导管杆并沿着水交叉或水杆的轴向延伸。冷却剂升高通道具有形成在燃料棒由下连接板支撑的部分上方或下方的部分处的冷却剂入口。控制元件引导管具有形成在该部分处的冷却剂出口，使得引入冷却剂升高通道的冷却剂垂直向上流动，然后沿着控制元件引导管向下流动，并通过冷却剂出口流入其内部港口。反应堆堆芯包括多个燃料组件，每个燃料组件均具有上述结构，一个控制棒和一个与该控制棒一起操作的控制元件。

3. 发明授权

US06236698B1 Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system 有权
标题翻译：核反应堆配电监控系统及方法，包括核反应堆仪表系统
公开(公告)号：US06236698B1
公开(公告)日：2001-05-22
申请号：US09271350
申请日：1999-03-17
申请人： Koji Hirukawa , Shungo Sakurai , Takafumi Naka
发明人： Koji Hirukawa , Shungo Sakurai , Takafumi Naka
IPC分类号： G21C1700
CPC分类号： G21C17/108
摘要： A nuclear reactor instrumentation system including a plurality of in core nuclear instrumentation assemblies arranged in a gap between a number of fuel assemblies charged in a reactor core. The income nuclear instrumentation assemblies each include a fixed type neutron detector assembly having a plurality of fixed type neutron detectors dispersively arranged in a core axial direction and a fixed type gamma thermometer assembly having a plurality of fixed type gamma ray heat detectors arranged at least in a same core axial direction as the fixed type neutron detectors. A power range detector signal processing device is operatively connected to the fixed type neutron detector assemblies through signal cables. A gamma thermometer signal processing device is operatively connected to the fixed type gamma thermometer assembly of the in core nuclear instrumentation assembly through a signal cable.
摘要翻译：一种核反应堆仪表系统，包括多个核心核仪表组件，其布置在充电在反应堆堆芯中的多个燃料组件之间的间隙中。收纳核仪表组件各自包括固定型中子探测器组件，其具有分散布置在芯轴方向上的多个固定型中子探测器组件和固定型伽马温度计组件，该组件具有多个固定型伽马射线热检测器，其至少布置在与固定式中子探测器相同的芯轴方向。功率范围检测器信号处理装置通过信号电缆可操作地连接到固定型中子探测器组件。伽马温度计信号处理装置通过信号电缆可操作地连接到核心核仪表组件的固定型γ温度计组件。

4. 发明授权

US5331679A Fuel spacer for fuel assembly 失效
标题翻译：用于燃料组件的燃料间隔件
公开(公告)号：US5331679A
公开(公告)日：1994-07-19
申请号：US987195
申请日：1992-12-08
申请人： Koji Hirukawa
发明人： Koji Hirukawa
IPC分类号： G21C3/344 , G21C3/34
CPC分类号： G21C3/344 , G21Y2002/201 , G21Y2002/207 , G21Y2004/30 , Y02E30/40
摘要： A fuel spacer for a fuel assembly comprises a plurality of tubular ferrules each forming a fuel rod insertion passage, a belt-like support member for supporting the tubular ferrules bundled in a lattice arrangement and a spring member for axially supporting the fuel rods disposed in the ferrules. The adjoining ferrules are joined together horizontally, each of the ferrules has at least one end to which a plurality of cutout portions are formed circumferentially of the end portion and at least one flat portion is formed between adjoining petal portions at which the adjoining ferrules are spot welded. Each of the cutout portions and petal portions of the tubular ferrule has various shapes such as trapezoidal, rectangular, triangular, V or M shape. The cutout portions and petal portions may be formed at both axial ends of the tubular ferrule. The adjoining ferrules are joined together such that an end portion of one ferrule to which the cutout portions are formed is spot welded to an end portion of another ferrule to which any cutout portion is not formed. The petal portions formed on a downstream side with respect to a coolant flow in a fuel assembly is twisted outward to provide revolutional flow and an opened end of the ferrule.
摘要翻译：用于燃料组件的燃料间隔件包括多个管状套管，每个管状套管形成燃料棒插入通道，用于支撑以格子排列为一体的管状套圈的带状支撑构件和用于轴向支撑设置在燃料棒中的燃料棒的弹簧构件套圈。相邻的套圈水平地接合在一起，每个套圈具有至少一个端部，多个切口部分形成在端部的周向上，并且至少一个平坦部分形成在相邻的套圈之间的邻接的花瓣部分之间焊接管状套管的切口部分和花瓣部分中的每一个具有梯形，矩形，三角形，V形或M形的各种形状。切口部分和花瓣部分可以形成在管状套圈的两个轴向端部处。相邻的套圈接合在一起，使得形成有切口部的一个套圈的端部点焊到没有形成任何切口部的另一个套圈的端部。相对于燃料组件中的冷却剂流形成在下游侧的花瓣部分向外扭转以提供旋转流动和套圈的开口端。

5. 发明申请

US20080173052A1 METHOD FOR TREATMENT OF DISTILLATION WASTE FROM STARCHY MATERIALS 失效
标题翻译：用于处理来自淀粉材料的蒸馏废物的方法
公开(公告)号：US20080173052A1
公开(公告)日：2008-07-24
申请号：US12015764
申请日：2008-01-17
申请人： Hiroshi TAKAMIYA , Shoichiro Kajiwara , Koji Hirukawa , Kimihisa Iwashiro
发明人： Hiroshi TAKAMIYA , Shoichiro Kajiwara , Koji Hirukawa , Kimihisa Iwashiro
IPC分类号： C02F1/68 , C05F5/00
CPC分类号： C05F5/006 , C02F1/441 , C02F1/56 , C02F9/00 , C02F2103/325 , Y02A40/211
摘要： There is provided a method for highly treating distillation waste generated in the process of separating a distilled alcoholic material after alcoholic fermentation of starchy materials. The method includes the steps of adding sodium polyacrylate to the distillation waste from the starchy materials, then adding chitosan to treat the distillation waste, and further adding sodium polyacrylate to the waste. Furthermore, solid-liquid separation is then carried out. A liquid material thus separated is brought into contact with a reverse osmosis membrane.
摘要翻译：提供了一种在淀粉质材料酒精发酵后在蒸馏酒精材料分离过程中产生的蒸馏废物进行高度处理的方法。该方法包括以下步骤：从淀粉物质向蒸馏废料中加入聚丙烯酸钠，然后加入壳聚糖以处理蒸馏废物，并进一步向废物中加入聚丙烯酸钠。此外，然后进行固液分离。将这样分离的液体材料与反渗透膜接触。

6. 发明授权

US06310929B1 In-core fixed nuclear instrumentation system and power distribution monitoring system 有权
标题翻译：核心固定核仪表系统和配电监控系统
公开(公告)号：US06310929B1
公开(公告)日：2001-10-30
申请号：US09382597
申请日：1999-08-25
申请人： Koji Hirukawa
发明人： Koji Hirukawa
IPC分类号： G21C1700
CPC分类号： G21C17/108
摘要： In an in-core fixed nuclear instrumentation system for a reactor, each of a plurality of in-core nuclear instrumentation assemblies has a nuclear instrumentation tube. LPRM detectors are housed in the nuclear instrumentation tube for detecting LPRM signal in a core of the reactor. A GT assembly is housed in the tube. The GT assembly has fixed GT detectors for detecting &ggr;-ray heating values and a built-in heater therein for calibrating the fixed GT detectors. The fixed GT detectors are arranged at least close to the fixed LPRM detectors, respectively. GT signals by the detected &ggr;-ray heating values of the fixed GT detectors of each GT assemblies are processed by a GT signal processing unit. The heater in each GT assemblies is electrically energized by a GT heater control unit. Predetermined time intervals are stored in a memory unit. One of the predetermined time intervals for specified &ggr;-ray thermometer assemblies, respectively is selected so that the GT heater control unit controls an electrical energy supplied to the heater by the selected interval so as to heat the heater, thereby executing a heater calibration of output voltage sensitivities of the fixed GT detectors of the GT assembly.
摘要翻译：在用于反应堆的核心固定核仪表系统中，多个核心核仪表组件中的每一个具有核仪器管。 LPRM探测器安装在核仪表管中，用于检测反应堆核心中的LPRM信号。 GT组件安装在管中。 GT组件具有用于检测伽马射线加热值的固定GT检测器和用于校准固定GT检测器的内置加热器。固定的GT检测器分别至少靠近固定的LPRM探测器。通过GT信号处理单元处理每个GT组件的固定GT检测器的检测伽马射线加热值的GT信号。每个GT组件中的加热器由GT加热器控制单元供电。预定时间间隔存储在存储器单元中。分别选择指定的伽马射线温度计组件的预定时间间隔之一，使得GT加热器控制单元以供选择的间隔来控制供给加热器的电能，以加热加热器，由此执行加热器校准输出 GT组件的固定GT检测器的电压灵敏度。

7. 发明授权

US5416813A Moderator rod containing burnable poison and fuel assembly utilizing same 失效
标题翻译：含有可燃毒物和燃料组件的主持杆使用它
公开(公告)号：US5416813A
公开(公告)日：1995-05-16
申请号：US142052
申请日：1993-10-28
申请人： Kouji Hiraiwa , Yoshihira Ando , Koji Hirukawa , Kazuki Hida
发明人： Kouji Hiraiwa , Yoshihira Ando , Koji Hirukawa , Kazuki Hida
IPC分类号： G21C3/326 , G21C3/00
CPC分类号： G21C3/326 , G21Y2002/201 , G21Y2004/30 , Y02E30/38
摘要： A moderator rod provided with a burnable poison and disposed in a fuel assembly of a reactor core comprises an outer tube, an inner tube disposed in the outer tube, the outer and inner tubes constituting a double tube structure between which an annular section is formed, and a burnable poison charged in said annular section. A containing amount of the burnable poison per unit area of the annular section is distributed at least one of peripheral direction and axial direction of the double tube structure of the inner and outer tubes. A fuel assembly of a nuclear reactor comprises an upper tie plate, a lower tie plate, a number of fuel rods supported at their upper ends by the upper tie plate and at their lower ends by the lower tie plate and filled up in their inner spaces with a plurality of fuel pellets, at least one of moderator rods containing burnable poison in various states and a channel box. The moderator has an outer tube and an inner tube disposed coaxially in the outer tube. An area of a metal, ceramics or thermet containing the burnable poison is formed at a portion except for portions having axial length corresponding to 1/24 to 1/12 length of the fuel effective length from the upper and lower ends thereof.
摘要翻译：设置有可燃毒物的调节杆，设置在反应堆堆芯的燃料组件中，包括外管，设置在外管中的内管，外管和内管构成双管结构，在其间形成有环形部，以及在所述环形部分中装入的可燃毒物。环状部的每单位面积的可燃性毒物的含量分布在内管和外管的双管结构的周向和轴向方向中的至少一个上。核反应堆的燃料组件包括上连接板，下连接板，多个燃料棒，其上端由上连接板支撑，其下端由下连接板支撑并填充在其内部空间多个燃料粒子，至少一个包含各种状态的可燃毒物的调节杆和通道箱。调节剂具有外管和同轴地设置在外管中的内管。除了具有与其上端和下端的燃料有效长度的1/24至1/12长度相对应的轴向长度的部分之外的部分，形成含有可燃毒物的金属，陶瓷或热电偶的区域。

8. 发明授权

US07736515B2 Method for treatment of distillation waste from starchy materials 失效
标题翻译：从淀粉材料处理蒸馏废物的方法
公开(公告)号：US07736515B2
公开(公告)日：2010-06-15
申请号：US12015764
申请日：2008-01-17
申请人： Hiroshi Takamiya , Shoichiro Kajiwara , Koji Hirukawa , Kimihisa Iwashiro
发明人： Hiroshi Takamiya , Shoichiro Kajiwara , Koji Hirukawa , Kimihisa Iwashiro
IPC分类号： B01D15/00 , B01D61/02 , B01D61/04 , C05F5/00 , A23L1/09
CPC分类号： C05F5/006 , C02F1/441 , C02F1/56 , C02F9/00 , C02F2103/325 , Y02A40/211
摘要： There is provided a method for highly treating distillation waste generated in the process of separating a distilled alcoholic material after alcoholic fermentation of starchy materials. The method includes the steps of adding sodium polyacrylate to the distillation waste from the starchy materials, then adding chitosan to treat the distillation waste, and further adding sodium polyacrylate to the waste. Furthermore, solid-liquid separation is then carried out. A liquid material thus separated is brought into contact with a reverse osmosis membrane.
摘要翻译：提供了一种在淀粉质材料酒精发酵后在蒸馏酒精材料分离过程中产生的蒸馏废物进行高度处理的方法。该方法包括以下步骤：从淀粉物质向蒸馏废料中加入聚丙烯酸钠，然后加入壳聚糖以处理蒸馏废物，并进一步向废物中加入聚丙烯酸钠。此外，然后进行固液分离。将这样分离的液体材料与反渗透膜接触。

9. 发明授权

US06477219B2 Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system 有权
标题翻译：核反应堆配电监控系统及方法，包括核反应堆仪表系统
公开(公告)号：US06477219B2
公开(公告)日：2002-11-05
申请号：US09810566
申请日：2001-03-19
申请人： Koji Hirukawa , Shungo Sakurai , Takafumi Naka
发明人： Koji Hirukawa , Shungo Sakurai , Takafumi Naka
IPC分类号： G21C1700
CPC分类号： G21C17/108
摘要： A nuclear reactor instrumentation system including a plurality of incore nuclear instrumentation assemblies arranged in a gap between a number of fuel assemblies charged in a reactor core. The incore nuclear instrumentation assemblies each include a fixed type neutron detector having a plurality of fixed type neutron detectors dispersively arranged in a core axial direction and a fixed type gamma thermometer assembly having a plurality of fixed type gamma ray heat detectors arranged at least in a same core axial direction as the fixed type neutron detectors. A power range detector signal processing device operatively connected to the fixed type neutron detector assemblies through signal cables. A gamma thermometer signal processing device is operatively connected to the fixed type gamma thermometer assembly of the incore nuclear instrumentation assembly through a signal cable.
摘要翻译：一种核反应堆仪表系统，包括多个装在核反应堆堆芯中的多个燃料组件之间的间隙中的多个核仪表组件。核武器装置组件包括固定型中子探测器，其具有分散布置在芯轴方向上的多个固定型中子探测器和固定型伽马温度计组件，其具有至少排列在其上的多个固定型γ射线热探测器核心轴向作为固定式中子探测器。功率范围检测器信号处理装置，通过信号电缆可操作地连接到固定型中子探测器组件。伽马温度计信号处理装置通过信号电缆可操作地连接到腋核仪器组件的固定型γ温度计组件。

10. 发明授权

US06456681B1 Neutron flux measuring apparatus 有权
标题翻译：中子通量测量仪
公开(公告)号：US06456681B1
公开(公告)日：2002-09-24
申请号：US09386142
申请日：1999-08-31
申请人： Yasushi Goto , Nobuaki Oono , Yuki Narawa , Teruji Tarumi , Koji Hirukawa
发明人： Yasushi Goto , Nobuaki Oono , Yuki Narawa , Teruji Tarumi , Koji Hirukawa
IPC分类号： C21C17108
CPC分类号： G21C17/108 , G21Y2002/201 , G21Y2002/301 , G21Y2004/30 , G21Y2004/305 , G21Y2004/40
摘要： A neutron flux measuring apparatus, adapted to a boiling-water reactor (BWR) of a nuclear power plant and an advanced boiling-water reactor (ABWR) of a nuclear power plant, for measuring a neutron flux in a reactor pressure vessel, comprises a neutron flux detector assembly incorporating a local power range monitor detector assembly and a start-up range neutron monitor detector, a preamplifier amplifying a detector signal obtained from said start-up range neutron monitor detector, a start-up range neutron monitor operation unit operating, indicating and monitoring the amplified signal of the start-up range neutron monitor detector, and a local power range monitor operation unit operating, indicating and monitoring a signal obtained from the local power range monitor detector.
摘要翻译：适用于核电厂的沸水反应堆（BWR）和用于测量反应堆压力容器中的中子通量的核电站的先进沸水反应堆（ABWR）的中子流量测量装置包括：中子通量检测器组件，其包括局部功率范围监视器检测器组件和启动范围中子监视器检测器，放大从所述启动范围中子监视器检测器获得的检测器信号的前置放大器，启动范围中子监视器操作单元，指示和监视启动范围中子监视器检测器的放大信号;以及本地功率范围监视器操作单元，其操作，指示和监视从本地功率范围监视器检测器获得的信号。

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