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1. 发明专利

JP2008216003A System and method for evaluating integrity of fuel at transition 有权
标题翻译：用于评估燃料在过渡中的完整性的系统和方法
公开(公告)号：JP2008216003A
公开(公告)日：2008-09-18
申请号：JP2007052936
申请日：2007-03-02
申请人： Toshiba Corp , 株式会社東芝
发明人： TAKEUCHI YUTAKA , ABE NOBUAKI , MOTOTANI AKIRA
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To make it possible to conduct the analysis of nuclear thermal hydraulic kinetics rapidly, if any abnormal transient changes occur during the operation of a boiling water reactor and if the evaluation of the integrity of fuel becomes necessary. SOLUTION: A system has a plant kinetics simulator 30 which can evaluate the transient behavior of a plant by simulating nuclear thermal hydraulic kinetics of a core; a core management system 21 which monitors and manages the state of the core; a process management system 22 which monitors and manages process quantities of the plant on the basis of measurement data on it; a transient phenomenon management system 20 which records and manages transient measurement data on the plant; a data linkage management function 31 which links these systems with each other through a network and carries out data transfer and processing required for the linkage; a database management function 32 which manages the measurement data on the plant, data input to the simulator and simulation results and a user interface function 33 which inputs and outputs those data for users. COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：为了有可能快速进行核热液压动力学分析，如果在沸水反应堆运行期间发生任何异常的瞬态变化，并且需要评价燃料的完整性。解决方案：系统具有植物动力学模拟器30，其可以通过模拟核心的核热液压动力学来评估工厂的瞬态特性; 核心管理系统21，其监视和管理核心的状态; 过程管理系统22，其基于其上的测量数据监测和管理工厂的处理量; 瞬时现象管理系统20，其记录和管理工厂上的瞬时测量数据; 数据链接管理功能31，其通过网络将这些系统相互连接并执行链接所需的数据传送和处理; 管理工厂的测量数据，输入到模拟器的数据和仿真结果的数据库管理功能32以及用户输入和输出这些数据的用户界面功能33。版权所有（C）2008，JPO＆INPIT

2. 发明专利

JP2007205799A Coolant temperature measuring instrument for boiling water nuclear reactor and its measurement method 审中-公开
标题翻译：用于锅炉水核反应堆的冷却温度测量仪器及其测量方法
公开(公告)号：JP2007205799A
公开(公告)日：2007-08-16
申请号：JP2006023425
申请日：2006-01-31
申请人： Toshiba Corp , 株式会社東芝
发明人： IMARUOKA HIROMITSU , SATO HISAKI , KANO YOSHIJI , MIYAZAKI TEIJI , HOASHI EIJI , ABE NOBUAKI , SHIMIZU TAKESHI , NAKADA KOTARO
IPC分类号： G21C17/02
摘要： PROBLEM TO BE SOLVED: To rationally and accurately measure coolant temperature and its temperature distribution at a downcomer part or a core inlet part to accurately perform core-portion flow measurement and core performance monitoring with satisfactory precision based on the measured coolant temperature distribution.
SOLUTION: This coolant temperature measuring instrument for a boiling water reactor 10 is made by housing a reactor core 12 in a reactor pressure vessel 11, forming the core inlet part 24 in a lower part of the reactor core 12 while surrounding the reactor core 12 with a core shroud 14, and providing the downcomer part 21 between the core shroud 14 and the pressure vessel 11. The reactor 10 is provided with a plurality of thermometers 31 at radially middle positions from the center of the pressure vessel 11 down to the core shroud 14, and in the inlet part 24 at a circumferential position corresponding to feed water nozzles 30 from a reactor feed water system, and the coolant temperature and its temperature distribution at the inlet part 24 are measured by means of the respective thermometers 31.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：为了合理准确地测量冷却液温度及其在降液管部分或芯入口部分的温度分布，以基于测量的冷却剂温度分布精确地进行核心部分流量测量和核心性能监测，并以令人满意的精度进行测量。解决方案：用于沸水反应器10的这种冷却剂温度测量仪器通过将反应堆芯12容纳在反应堆压力容器11中而形成，在反应堆堆芯12的下部形成核心入口部分24，同时围绕反应堆芯部12具有芯护罩14，并且在芯护罩14和压力容器11之间提供降液管部分21.反应器10在从压力容器11的中心到径向中间位置处设置有多个温度计31，直到压力容器11的中心核心护罩14以及在反应器供水系统中对应于给水喷嘴30的周向位置的入口部分24中，以及通过相应的温度计31测量冷却剂温度及其在入口部分24处的温度分布。版权所有（C）2007，JPO＆INPIT

3. 发明专利

JP2008051650A In-vessel work system 审中-公开
标题翻译： IN-VESSEL工作系统
公开(公告)号：JP2008051650A
公开(公告)日：2008-03-06
申请号：JP2006228213
申请日：2006-08-24
申请人： Toshiba Corp , 株式会社東芝
发明人： ABE NOBUAKI , YOSHII TOSHIHIRO , YUGUCHI YASUHIRO
IPC分类号： G21C17/003 , G21C19/02
摘要： PROBLEM TO BE SOLVED: To ensure the integrity and reliability of an in-vessel work unit.
SOLUTION: An in-vessel work system for the work that uses the in-vessel work unit 15 in a reactor pressure vessel 11, in-vessel work is carried out for a region subject to work by the in-vessel work unit 15, by conducting at least one of the control operation of a reactor cooling system 12 for supplying cooling water into the reactor pressure vessel 11, installs an inlet structure for introducing the cooling water from the reactor cooling system 12 to an annulus section 14 and the installation of an isolation wall which isolates an area above the annulus section 14; and guides the in-vessel work unit 15 to the isolated area and also leads the cooling water from the reactor cooling system 12 to the annulus section 14 in response to the temperature and fluid state of reactor water in the annulus section 14 including the region subject to the work.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：确保船上工作单位的完整性和可靠性。解决方案：在反应堆压力容器11中使用船上工作单元15的工作的船上作业系统，对于由船上工作单元进行工作的区域进行船上作业如图15所示，通过进行反应堆冷却系统12的控制操作中的至少一个，用于将冷却水供应到反应堆压力容器11中，安装用于将来自反应堆冷却系统12的冷却水引入环形部分14的入口结构，隔离隔离壁的安装，其隔开环形部分14上方的区域; 并将容器工作单元15引导到隔离区域，并且响应于包括区域主体的环形部分14中的反应堆水的温度和流体状态，还将冷却水从反应堆冷却系统12引导到环空部分14 到工作。版权所有（C）2008，JPO＆INPIT

4. 发明专利

JP2007263672A Method for starting up natural circulation reactor 有权
标题翻译：启动自然循环反应器的方法
公开(公告)号：JP2007263672A
公开(公告)日：2007-10-11
申请号：JP2006087792
申请日：2006-03-28
申请人： Toshiba Corp , 株式会社東芝
发明人： YOKOBORI SEIICHI , ABE NOBUAKI , MURASE AKIRA
IPC分类号： G21D3/00
CPC分类号： Y02E30/31
摘要： PROBLEM TO BE SOLVED: To generate no geysering flow rate vibration during the start-up of a BWR of a natural circulation type and make flushing flow rate vibration as short and moderate as possible.
SOLUTION: After finishing deaeration operation, a coolant is filled into a reactor pressure vessel 1 till fuel assemblies 3a are completely immersed and a noncondensing gas is supplied to a space in the reactor pressure vessel 1 above the liquid level 27a of the coolant to fill the space. After pressurizing the noncondensing gas to a high pressure of 3 atm. or higher preferably 10 atm. or higher, the pressurization through nuclear heating is started.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：在自然循环型的BWR启动期间不产生喷射流量振动，并使冲洗流量振动尽可能短和中等。解决方案：在完成除气操作之后，将冷却剂填充到反应堆压力容器1中，直到燃料组件3a完全浸没，并且将非冷凝气体供应到反应堆压力容器1中在冷却剂的液面27a上方的空间填补空间。将非冷凝气体加压至3个大气压的高压。或更高，优选10个大气压。以上，通过核加热开始加压。版权所有（C）2008，JPO＆INPIT

5. 发明专利

JP2005283269A Transient boiling transition monitoring system for boiling water nuclear reactor and monitoring method 审中-公开
标题翻译：用于锅炉水核反应堆和监测方法的瞬态沸腾过渡监测系统
公开(公告)号：JP2005283269A
公开(公告)日：2005-10-13
申请号：JP2004096361
申请日：2004-03-29
申请人： Toshiba Corp , 株式会社東芝
发明人： ABE NOBUAKI , TAKEUCHI YUTAKA , KAWAMURA SHINICHIRO
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To provide a transient boiling transition monitoring system for a boiling water nuclear reactor to maintain an optimum thermal margin of a boiling water nuclear reactor plant by realistically and accurately evaluating ΔCPR in transition in each operating state of the nuclear plant.
SOLUTION: This transient boiling transition monitoring system for a boiling water nuclear reactor is characterized by being equipped with an all bundle transient simulator 7, a transient critical power ratio reduction operating device 8, and a transient boiling transition display device 9. The transient simulator 7 is equipped with measuring instruments 1 to 4 for measuring data on the boiling water nuclear reactor plant, calculates flow rates and quality distribution of all bundles based on the measured data by the measuring instruments 1 to 4 to evaluate the initial critical power ratios of all the bundles, and further, three-dimensionally nuclear-thermal-bond analyzes an abnormal transient change in operation to calculate changes in critical power ratios of all the bundles. The operating device 8 calculates reductions in transient critical power ratios of all the bundles based on a calculation result by the transient simulator 7. The display device 9 is capable of displaying a trend image plane of a transient critical power reduction reactor map of all the bundles.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供沸水核反应堆的瞬态沸腾过渡监测系统，以通过在核的每个运行状态下实际和准确地评估转换中的ΔCPR来维持沸水核反应堆的最佳热裕度厂。解决方案：沸腾核反应堆的这种瞬态沸腾过渡监测系统的特征在于配备有全束瞬态模拟器7，瞬态临界功率比减小操作装置8和瞬态沸腾跃迁显示装置9。瞬态模拟器7配备有用于测量沸水核反应堆工厂数据的测量仪器1至4，根据测量仪器1至4的测量数据计算所有束的流量和质量分布，以评估初始临界功率比并且进一步地，三维核热键分析操作中的异常瞬态变化以计算所有束的关键功率比的变化。操作装置8基于瞬态模拟器7的计算结果计算所有束的瞬态临界功率比的降低。显示装置9能够显示所有束的瞬态临界功率降低反应器图的趋势图像平面。版权所有（C）2006，JPO＆NCIPI

6. 发明专利

JP2004271483A Core of boiling water reactor and operation method 审中-公开
公开(公告)号：JP2004271483A
公开(公告)日：2004-09-30
申请号：JP2003066129
申请日：2003-03-12
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMAOKA MITSUAKI , ABE NOBUAKI
IPC分类号： G21C5/00 , G21C3/30 , G21C3/62 , G21C5/18
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To increase thermal power per unit core volume in a boiling water reactor core, by reducing power mismatch of new and old fuel assemblies due to burning.
SOLUTION: The core is constituted by arranging a plurality of fuel assemblies, in which fuel rods containing mixed fuel of fissile plutonium and uranium are tightly arranged into nearly a regular triangle shape. In the core of the boiling water reactor, in which by each part of a plurality of fuel assemblies is replaced by new fuel assemblies at each specific fuel cycle. In the core outer region including the outermost region, fuel assemblies 18 with the highest fissile plutonium enrichment are arranged, and a plurality of kinds of flow resistances for the coolant flow inlet of core support structures are provided in the outer region, where the fuel assemblies are loaded and new fuel assemblies are loaded at a position with relatively small flow resistance.
COPYRIGHT: (C)2004,JPO&NCIPI

7. 发明专利

JP2010261870A Output control system and output control method for boiling-water reactor 审中-公开
标题翻译：锅炉水反应堆输出控制系统及输出控制方法
公开(公告)号：JP2010261870A
公开(公告)日：2010-11-18
申请号：JP2009114014
申请日：2009-05-08
申请人： Toshiba Corp , 株式会社東芝
发明人： TAKEUCHI YUTAKA , ABE NOBUAKI , MATSUMOTO KEIJI
IPC分类号： G21D3/00 , G21C7/08 , G21C7/26 , G21C17/00 , G21C17/10 , G21D3/08
CPC分类号： Y02E30/31 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To provide an output control system and an output control method for boiling-water reactor, generating parameters for reflecting output stability and fuel integrity, by using an output space distribution of a core in process quantities of the reactor, and controlling the reactor output, to secure output stability or fuel integrity of the reactor based on the parameter.
SOLUTION: The output control system of the boiling-water reactor includes: a contraction calculation device provided to input an output space distribution 001, including a plurality of local outputs acquired by an LPRM 101 group provided on the core 2 (as shown in Fig.2) for contracting the output space distribution 001 to reflect output stability or fuel integrity, and generating a contraction parameter; and a control determination device 103 for determining successively whether the contraction parameter lies within a set range, and selecting and operating one or a plurality of output control means from a control rod, a reactor water level and other output control means, when the contraction parameter deviates from the range set.
COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：为了提供沸水反应堆的输出控制系统和输出控制方法，通过使用反应器的处理量中的核的输出空间分布产生用于反映输出稳定性和燃料完整性的参数，并控制反应堆输出，以确保基于该参数的反应器的输出稳定性或燃料完整性。解决方案：沸水反应堆的输出控制系统包括：收缩计算装置，用于输入输出空间分布001，包括由芯2上提供的LPRM 101组获取的多个局部输出（如图所示）在图2中）用于收缩输出空间分布001以反映输出稳定性或燃料完整性，并产生收缩参数; 以及控制确定装置103，用于连续地确定收缩参数是否处于设定范围内，以及当收缩参数时，从控制杆，反应器水位和其它输出控制装置中选择和操作一个或多个输出控制装置偏离范围集。版权所有（C）2011，JPO＆INPIT

8. 发明专利

JP2010243257A Integrity monitoring apparatus of jet pump 审中-公开
标题翻译：喷气机整体监测装置
公开(公告)号：JP2010243257A
公开(公告)日：2010-10-28
申请号：JP2009090337
申请日：2009-04-02
申请人： Toshiba Corp , 株式会社東芝
发明人： ABE NOBUAKI , KOSHI YUJI , MATSUMOTO KEIJI
IPC分类号： G21C17/003 , F04B49/10 , G21C15/25 , G21C17/02 , G21C17/032
CPC分类号： Y02E30/31
摘要： PROBLEM TO BE SOLVED: To provide an integrity monitoring apparatus which monitors operating conditions of jet pumps set up in a recirculation system and immediately detects a jet pump where a malfunction such as a failure occurs.
SOLUTION: The monitor includes a plant data detection unit 202 for detecting the flow rate of each jet pump set up in a reactor recirculation system, an integrity evaluation unit 203 which computes a predetermined given index value of a flow rate on the basis of the flow rate data measured by the plant data detection unit 202 and evaluates the integrity of the jet pumps in the reactor recirculation system by comparing the index value of the flow rate with a prescribed determination parameter, and a jet pump data indication unit 204 which indicates the evaluation results of the integrity evaluation unit 203.
COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：提供一种完整性监视装置，其监视设置在再循环系统中的喷射泵的操作条件，并立即检测出现故障如发生故障的喷射泵。解决方案：监视器包括用于检测在反应堆再循环系统中设置的每个喷射泵的流量的工厂数据检测单元202，完整性评估单元203，其基于该流量计算预定的给定指标值的工厂数据检测单元202测量的流量数据，并通过将流量的指标值与规定的确定参数进行比较来评估反应堆再循环系统中的喷射泵的完整性;以及喷射泵数据指示单元204，表示完整性评估单元203的评价结果。（C）2011年，JPO＆INPIT

9. 发明专利

JP2008128655A Boiling water type natural circulation reactor and operation control method therefore 审中-公开
标题翻译：锅炉水型自然循环反应器及其操作控制方法
公开(公告)号：JP2008128655A
公开(公告)日：2008-06-05
申请号：JP2006310303
申请日：2006-11-16
申请人： Toshiba Corp , 株式会社東芝
发明人： ABE NOBUAKI , NAKAMARU MIKIHIDE
IPC分类号： G21C7/26 , G21C15/02 , G21C15/16 , G21C15/25 , G21C15/26 , G21D3/08
CPC分类号： Y02E30/39
摘要： PROBLEM TO BE SOLVED: To improve power control capability by enabling the control of a core flow rate, without a large cost increase, in a boiling water type natural circulation reactor. SOLUTION: A boiling water type natural circulation reactor comprises a reactor vessel 1; a core 14 installed in the reactor vessel 1; a cylindrical core shroud 10, covering the outer peripheral face of the core 14 and dividing the inner part of the reactor 1 into inside/outside; a core shroud head 26, covering the upper part of the core shroud 10; a cylindrical chimney 15, arranged above the core shroud head 26, having opening parts at the upper and lower end parts; a rear-placed cylindrical shroud 20 arranged so as to cover the outer peripheral face of the upper end of a chimney 15; a rear-placed shroud head 27, covering the upper part of the rear-placed shroud 20 and having a rear-placed shroud head opening part 70 at the upper part; and a steam separator 16, connected to the opening part of the rear-placed shroud head 70, arranged above the rear-placed shroud head 27. COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：通过在沸水型自然循环反应器中实现核心流量的控制，而不会大幅度地增加成本，从而提高功率控制能力。解决方案：沸水型天然循环反应器包括反应器容器1; 安装在反应堆容器1中的核心14; 圆筒形芯护罩10，覆盖芯14的外周面并将反应器1的内部分隔成内/外; 覆盖芯护罩10的上部的芯护罩头26; 设置在芯护罩头26上方的圆柱形烟囱15，在上端部和下端部具有开口部; 布置成覆盖烟囱15的上端的外周面的后置圆柱形护罩20; 一个后置的护罩头部27，覆盖后置护罩20的上部并且在上部具有后置的护罩头部开口部70; 以及连接到后置护罩头70的开口部分的蒸汽分离器16，布置在后置的护罩头27的上方。版权所有（C）2008，JPO＆INPIT

10. 发明专利

JP2007047090A Natural circulation type boiling water reactor 有权
标题翻译：自然循环型锅炉水反应堆
公开(公告)号：JP2007047090A
公开(公告)日：2007-02-22
申请号：JP2005233750
申请日：2005-08-11
申请人： Toshiba Corp , 株式会社東芝
发明人： ABE NOBUAKI , TAKEUCHI YUTAKA , TAKIGAWA YUKIO , NAKAMARU MIKIHIDE
IPC分类号： G21C15/26 , G21C15/02
CPC分类号： G21C1/084 , G21C15/02 , G21C15/26 , G21Y2002/30 , G21Y2004/30 , Y02E30/31
摘要： PROBLEM TO BE SOLVED: To provide a natural circulation type boiling water reactor improving stability by shortening the region of gas-liquid two-phase flow and resolving transport delay in the separate chimneys.
SOLUTION: The natural circulation type boiling water reactor 10 of this invention comprises a plurality of separate chimneys 15 at upper core, and a multitude of fuel assemblies 13 are installed in the core 14. The natural circulation type boiling water reactor 10 is provided with a structure for equalizing the pressure in the separate chimneys 15 in the rectangular cylinder grid plate of the separated chimneys at the core 14 outlet. With this pressure equalizing structure, the pressure in the separated chimney 15 parts is equalized.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种天然循环型沸水反应器，其通过缩短气液两相流的区域并解决分离的烟囱中的运输延迟来提高稳定性。解决方案：本发明的自然循环型沸水反应器10在上部芯部包括多个单独的烟囱15，并且多个燃料组件13安装在核心14中。自然循环型沸水反应器10是设置有用于均衡在核心14出口处分离的烟囱的矩形缸格栅板中的单独烟囱15中的压力的结构。利用该均压结构，分离的烟囱15部分中的压力相等。版权所有（C）2007，JPO＆INPIT

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