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1. 发明专利

JP2013217857A Method for estimating distribution of neutron irradiation amount 审中-公开
标题翻译：估计中性辐射量分布的方法
公开(公告)号：JP2013217857A
公开(公告)日：2013-10-24
申请号：JP2012090509
申请日：2012-04-11
申请人： Toshiba Corp , 株式会社東芝
发明人： MATSUSHITA KAORU , KUROSAWA MASAHIKO , KAWANO SHOHEI , SAEKI RYOICHI , TAKAHASHI HIDENORI , MIYAMURA SATOSHI
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To accurately estimate a circumferential distribution of a neutron irradiation amount of a reactor pressure vessel, etc.SOLUTION: A method for estimating a circumferential distribution of a neutron irradiation amount has: a step S01 of calculating a circumferential distribution of a neutron irradiation amount; a step S02 of selecting an installation position of a neutron dosimeter on the basis of a calculation result; a step S04 of installing a dosimeter device during stop of an operation; a step S05 in which the neutron dosimeter is irradiated by the operation of a nuclear reactor installation; a step S06 of recovering the dosimeter device during the stop of the operation; a step S07 of measuring the neutron irradiation amount; and a step S08 of correcting the circumferential distribution of the neutron irradiation amount from the calculation result of the circumferential distribution of the neutron irradiation amount and a measurement result of the neutron irradiation amount to obtain a circumferential distribution of the neutron irradiation amount after correction.
摘要翻译：要解决的问题：精确地估计反应堆压力容器等的中子照射量的周向分布。解决方案：用于估计中子照射量的圆周分布的方法具有：计算中子辐射量的周向分布的步骤S01 中子辐射量; 基于计算结果选择中子剂量计的安装位置的步骤S02; 在停止操作期间安装剂量计装置的步骤S04; 其中通过核反应堆装置的操作照射中子剂量计的步骤S05; 在操作停止期间恢复剂量计装置的步骤S06; 测量中子照射量的步骤S07; 以及从中子照射量的周向分布的计算结果和中子照射量的测定结果来校正中子照射量的周向分布的步骤S08，得到校正后的中子照射量的周向分布。

2. 发明专利

JP2013170825A Method for evaluating activated radioactivity and system for evaluating activated radioactivity 有权
标题翻译：用于评估激活的放射性的方法和用于评估激活的放射性的系统
公开(公告)号：JP2013170825A
公开(公告)日：2013-09-02
申请号：JP2012032800
申请日：2012-02-17
申请人： Japan Atom Power Co Ltd:The , 日本原子力発電株式会社 , Toshiba Corp , 株式会社東芝 , Toshiba Plant Systems & Services Corp , 東芝プラントシステム株式会社
发明人： TANAKA KENICHI , TANABE HIDENORI , ICHIGE HIDEAKI , KUROSAWA MASAHIKO , YAGISHITA SATOSHI , MATSUSHITA KAORU , HIROUCHI TAKAYUKI , IIDA HIDEHIKO , IKEDA TATSUYA , AKATSU KO
IPC分类号： G21C17/00
CPC分类号： G01T3/001 , G21D1/003
摘要： PROBLEM TO BE SOLVED: To provide an efficient method for evaluating activated radioactivity with effective accuracy for advance planning.SOLUTION: A method for evaluating activated radioactivity includes: a first input step S01 of inputting a neutron spectrum at each object position, an irradiation period, a cooling period, and a material composition of each object portion; a selection step S02 of selecting and inputting a typical neutron spectrum and a typical neutron fluence rate; a second input step S03; an activation calculation step S04 of calculating and storing the amount of activated radioactivity on the basis of the neutron spectrum at each object position, the irradiation period, the cooling period, and the material composition of each object portion, the typical neutron spectrum and the typical neutron fluence rate; and data storage steps S05 and S06. The method further includes: a step S09 of a multistep arithmetic processing for each nuclide by calculating and accumulating the activation reaction rate for each nuclide on the basis of the neutron spectrum at each object position and the activated radioactivity data; a step 10 of accumulating for each object portion, and a step S11 of determining the nuclide and a step S12 of determining the object position for determination whether one round is complete.
摘要翻译：要解决的问题：提供一种用于预先计划的有效准确度的活性放射性评估的有效方法。解决方案：一种用于评估活化放射性的方法，包括：在每个物体位置输入中子谱的第一输入步骤S01，冷却期间和每个物体部分的材料组成; 选择和输入典型的中子谱和典型的中子注量率的选择步骤S02; 第二输入步骤S03; 基于每个物体位置上的中子谱，照射周期，冷却周期和每个物体部分的材料组成，典型的中子谱和典型的中子谱计算和存储激活的放射性量的激活计算步骤S04 中子注量率; 和数据存储步骤S05和S06。该方法还包括：通过基于每个物体位置处的中子谱和活化的放射性数据计算和累积每个核素的活化反应速率，对每个核素进行多步运算处理的步骤S09; 对每个物体部分进行累积的步骤10，以及确定核素的步骤S11和确定物体位置的步骤S12，以确定一轮是否完成。

3. 发明专利

JP2005195541A Material deterioration diagnosing method for nuclear reactor structure 有权
标题翻译：核反应堆结构材料检测方法
公开(公告)号：JP2005195541A
公开(公告)日：2005-07-21
申请号：JP2004004305
申请日：2004-01-09
申请人： Toshiba Corp , 株式会社東芝
发明人： KAWANO SHOHEI , OBATA MINORU , TANAKA SHIGEAKI , SAKAMOTO HIROSHI , KUROSAWA MASAHIKO
IPC分类号： G21C17/003 , G21C17/025 , G21C19/02
摘要： PROBLEM TO BE SOLVED: To provide a material deterioration diagnosing method for a nuclear reactor structure capable of precisely estimating the distribution of nuclear transformation helium quantity contained in the nuclear reactor structure.
SOLUTION: The material deterioration diagnosing method for a nuclear reactor comprising the process 1 of extracting a sample 15 from the nuclear reactor structure 14 irradiated with a neutron beam, the process 2 of analyzing the extracted sample 15 to determine the quantity 16 of boron-11, the process 3 of estimating the initial quantity of boron 18 contained in a constituent material of the structure before being irradiated with the neutron beam by using the quantity 17 of boron-11 analyzed in the process 2 and the process 4 of estimating the distribution of nuclear transformation helium contained in the structure on the basis of the estimated initial quantity of boron, another chemical constituent 9 contained in the constituent material of the structure and the distribution 10 of the neutron dose.
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：提供能够精确估计核反应堆结构中包含的核转化氦量的分布的核反应堆结构的材料劣化诊断方法。解决方案：包括从用中子束照射的核反应堆结构14提取样品15的方法1的核反应堆的材料劣化诊断方法，分析提取的样品15以确定提取的样品15的量16的方法2 硼-11，通过使用在过程2中分析的硼-11的量17和估计的过程4来估计在用中子束照射之前结构的构成材料中包含的硼18的初始量的过程3 基于硼的估计初始量，结构的构成材料中包含的另一种化学成分9和中子剂量的分布10，在结构中包含的核转化氦的分布。版权所有（C）2005，JPO＆NCIPI

4. 发明专利

JP2013015375A Reactivity suppression method for nuclear fuel and reactivity suppression device therefor 有权
标题翻译：核燃料的反应性抑制方法及其反应活性抑制装置
公开(公告)号：JP2013015375A
公开(公告)日：2013-01-24
申请号：JP2011147524
申请日：2011-07-01
申请人： Toshiba Corp , 株式会社東芝
发明人： SUZUKI ATSUSHI , HIRAYAMA HIROSHI , YOSHIDA HIROYUKI , JINBO MASAKAZU , OKONOGI KAZUNARI , YOSHIDA NORIYUKI , KUROSAWA MASAHIKO , MATSUNAGA KEIJI
IPC分类号： G21C9/033
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a reactivity suppression technique for nuclear fuel which is effective for various conditions with the same method at the time of an accident event in a nuclear reactor.SOLUTION: At the time of an accident event, water sprinkling 18 is performed in a nuclear reactor pressure vessel 11 and neutron absorbers 20 insoluble in water are fed thereinto.
摘要翻译：要解决的问题：提供在核反应堆中事故事件时以相同方法对各种条件有效的核燃料的反应抑制技术。解决方案：在事故发生时，在核反应堆压力容器11中进行洒水18，将不溶于水的中子吸收体20送入。版权所有（C）2013，JPO＆INPIT

5. 发明专利

JP2005351805A Prediction method for neutron irradiated quantity distribution of reactor structure 审中-公开
标题翻译：反应器结构中性辐射量分布预测方法
公开(公告)号：JP2005351805A
公开(公告)日：2005-12-22
申请号：JP2004174245
申请日：2004-06-11
申请人： Toshiba Corp , 株式会社東芝
发明人： KAWANO SHOHEI , OBATA MINORU , TANAKA SHIGEAKI , SAKAMOTO HIROSHI , KUROSAWA MASAHIKO
IPC分类号： G21C17/00 , G21C17/003
摘要： PROBLEM TO BE SOLVED: To provide a method for accurately estimating distribution of neutron irradiation quantity that reactor structure receives.
SOLUTION: The method is constituted of an analysis process S1 for numerically analyzing neutron irradiation quantity of reactor structure receiving or having received neutron irradiation, a selection process S2 for selecting a sampling position of a specimen of reactor structure, based on the analyzed neutron irradiation distribution; a sampling process S3 for obtaining a sample from the reactor structure; an investigation process S4 for investigating the neutron irradiation quantity of the sample obtained, a correction process S5, for correcting the neutron irradiation quantity distribution analyzed from the investigated neutron irradiation quantity, and an estimation process S6 for estimating the actual neutron irradiation distribution quantity from the corrected neutron irradiation quantity distribution.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供一种精确估计反应堆结构接收的中子辐射量分布的方法。解决方案：该方法由用于数字分析接收或接收中子辐射的反应堆结构的中子辐射量的分析过程S1，基于分析的反应器结构的样品的取样位置的选择过程S2 中子辐射分布; 用于从反应器结构获得样品的采样过程S3; 用于调查所获得的样品的中子照射量的调查处理S4，用于校正从所研究的中子辐射量分析的中子辐射量分布的校正处理S5以及用于从所研究的中子辐射量估计中子辐射分布量的估计处理S6 校正中子辐射量分布。版权所有（C）2006，JPO＆NCIPI

6. 发明专利

JP2005321252A Method for measuring distribution of void rate in boiling water reactor 有权
标题翻译：用于测量锅炉水反应器中无效率分布的方法
公开(公告)号：JP2005321252A
公开(公告)日：2005-11-17
申请号：JP2004138236
申请日：2004-05-07
申请人： Toshiba Corp , 株式会社東芝
发明人： KIKUCHI TSUKASA , UEDA KIYOSHI , MIHASHI TAKESHI , HAYASHIDA YOSHIHISA , KUROSAWA MASAHIKO
IPC分类号： G21C17/02 , G21C17/038
摘要： PROBLEM TO BE SOLVED: To obtain a method for measuring void rates which makes it possible to easily measure a void rate inside a core and an effective void rate on the outer periphery in a boiling water reactor with an existing actual device without installing any new jigs for measurement, producing distortions of neutron flux or output or causing the loss of the reactivity in the core. SOLUTION: Given a threshold energy causing an activation reaction by fast neutrons whose energy is a certain value or higher, the reactivity ratio[(F)/(S)] of the fast neuron activation reactivity (F) of fast neutron threshold reaction nuclides to the slow neutron activation reactivity (S) in the activation of slow neutrons consisting of thermal and epithermal neutrons through the absorption of them is measured to a void rate measurement position (x) and a position (0) of a known void rate. Then, the reactivity ratio R=[(Fx)/(Sx)]/[(Fo/So)] of the reactivity ratio (Fx)/(Sx) of the void rate measurement position (x) to the reactivity ratio (Fo/So) of the position (0) of the known void rate is determined and is used together with a calibration curve found otherwise to determine the axial distribution of void rates of the reactor. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：为了获得一种用于测量空隙率的方法，其使得可以容易地测量具有现有实际装置的沸水反应堆中的芯内的空隙率和外周上的有效空隙率，而无需安装任何新的测量夹具，产生中子通量或输出失真或引起芯体反应性的损失。解决方案：考虑到能量为一定值或更高的快中子引起活化反应的阈值能量，快中子阈值的快速神经元激活反应性（F）的反应性比[（F）/（S）] 将通过其吸收由热和超热中子组成的缓慢中子活化的缓慢中子活化反应性（S）的反应核素测量为空隙率测量位置（x）和已知孔隙率的位置（0）。然后，空隙率测定位置（x）与反应性比例（Fo）的反应性比（Fx）/（Sx））的反应性比R = [（Fx）/（Sx）] / [（Fo / 确定了已知空隙率的位置（0）），并且与校准曲线一起使用，否则确定反应器的空隙率的轴向分布。版权所有（C）2006，JPO＆NCIPI

7. 发明专利

JP2008020272A Structure and method of radiation shield 审中-公开
标题翻译：辐射屏蔽的结构与方法
公开(公告)号：JP2008020272A
公开(公告)日：2008-01-31
申请号：JP2006191141
申请日：2006-07-12
申请人： Toshiba Corp , 株式会社東芝
发明人： YOSHIOKA KENTARO , KUROSAWA MASAHIKO
IPC分类号： G21F3/00
摘要： PROBLEM TO BE SOLVED: To prevent or reduce an employee's exposure to radiation due to the leakage of a neutron beam by preventing or reducing the leakage from a deficient part of a neutron shield even if the employee should be required to access the neutron shield.
SOLUTION: A radiation shield has a gamma-ray shield 5 mounted on the side of a radiation source 6 to shield an object from gamma rays, the neutron shield 2 mounted in the upper part of the gamma-ray shield 5 to shield the object from neutrons, an annular support 3 placed through the neutron shield 2 to reinforce it and a columnar neutron shield 4 contained inside the annular support 3.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：为防止或减少员工因中子束泄漏而导致的辐射暴露，即使雇员需要进入中子，防止或减少来自中子屏障的不足部分的泄漏屏蔽。解决方案：辐射屏蔽具有安装在辐射源6的侧面以将物体与伽马射线屏蔽的伽马射线屏蔽5，安装在伽马射线屏蔽5的上部的中子屏蔽2屏蔽来自中子的物体，通过中子屏蔽2放置的环形支撑件3以加强它，以及包含在环形支撑件3内部的柱状中子屏蔽4.版权所有（C）2008，JPO＆INPIT

8. 发明专利

JP2003017454A Tool for cleaning substrate, and apparatus and method for treating the substrate 有权
标题翻译：用于清洁基板的工具，以及用于处理基板的装置和方法
公开(公告)号：JP2003017454A
公开(公告)日：2003-01-17
申请号：JP2001199874
申请日：2001-06-29
申请人： Shibaura Mechatronics Corp , Toshiba Corp , 株式会社東芝 , 芝浦メカトロニクス株式会社
发明人： KUROSAWA MASAHIKO , HIRAKAWA TADAO
IPC分类号： H01L21/304
摘要： PROBLEM TO BE SOLVED: To provide a tool for cleaning a substrate which maintains cleaning effects by preventing particles released, by cleaning from accumulating between cleaning brushes 31, 32 and a semiconductor wafer W, and which prevents a readhesion of the particles to a surface of the substrate.
SOLUTION: The tool 76 for cleaning the substrate cleans the substrate W, while making the substrate W rotate in the circumferential direction. The tool 76 comprises the cleaning brushes having large-diameter parts 31a, 32a at one ends to clean the surface of the substrate W, a brush holder 70 for holding the brushes incapable of dropping if and rotatably driving the brushes, and an opening 73 provided at a sidewall of the holder to discharge a treatment liquid which is to be supplied to the substrate W.
COPYRIGHT: (C)2003,JPO
摘要翻译：要解决的问题：提供一种清洁基板的工具，其通过防止颗粒释放的清洁效果，通过清洁从清洁刷31,32和半导体晶片W之间的积聚而防止颗粒再次粘附到底物。解决方案：用于清洁基板的工具76在使基板W沿圆周方向旋转的同时清洁基板W。工具76包括一端的具有大直径部分31a，32a的清洁刷，以清洁基板W的表面;刷子保持器70，用于保持刷子不能下落并且可旋转地驱动刷子;以及提供的开口73 在保持器的侧壁处排出要供应到基板W的处理液体。

9. 发明专利

JPH052093A ABNORMALITY DIAGNOSIS DEVICE FOR PRESSURIZED WATER REACTOR 失效
公开(公告)号：JPH052093A
公开(公告)日：1993-01-08
申请号：JP15439391
申请日：1991-06-26
申请人： TOSHIBA CORP
发明人： KUROSAWA MASAHIKO
IPC分类号： G21C17/00 , G21C17/02
摘要： PURPOSE:To find abnormality of radioactives leakage due to heat conduction pipe rupture and grasp the evolution and the type of the leakage and fuel failure, etc. CONSTITUTION:In the secondary main steam line 8 and the primary coolant pipe 13, measurement systems for gamma spectrum 22 and dose rate 26 having bypass systems 21 and 25 capable of reducing sufficiently short half-life species are provided. An arithmetic processor 30 capable of comparing the data obtained with these measurement system 22 and 26, judging the existence of sign of abnormality due to leakage and calculating the radioactives density in the main steam at each measurement point using the dose rate and also the leakage radioactives density in the secondary main steam line with time, is provided.

10. 发明专利

JPH03255398A WATER FEEDING FACILITY OF NUCLEAR REACTOR 失效
公开(公告)号：JPH03255398A
公开(公告)日：1991-11-14
申请号：JP5183090
申请日：1990-03-05
申请人： TOSHIBA CORP
发明人： KUROSAWA MASAHIKO
IPC分类号： G21D3/08
摘要： PURPOSE:To diminish dose equivalent rate at the inside and outside of a turbine building and to intend reduction of worker exposures by connecting an injection facility of carbon oxides to a feed water piping of nuclear reactor water feeding facility led to the inside of nuclear reactor pressure vessel from a turbine. CONSTITUTION:An injection facility 13 of carbon oxides is connected between a condensate demineralizer tower 8 and a feed water heater 9 of nuclear reactor water feeding facility. Since a C such as a CO2 from the injection facility 13, or a CO2 when an oxigen is injected, can be injected into feed water, by this constitution, an existence ratio of C such as a CO2 in the nuclear reactor water feeding facility, or a CO2 when an oxigen is injected, reduces consequently. And also, since a ratio of the CO2 or a CO when an oxigen is injected, increases, an activated C which is transfered to a main steam system, reduces accordingly. In this way, transfer of the C to the main steam system reduces and therefore dose equivalent rate in a turbine building also reduces and reduction of worker exposure can be well intented.

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