专利快速检索-快速检索全球专利，免费商用专利数据库-IPRDB

1. 发明专利

JP2012052889A Neutron measuring device 有权
标题翻译： NEUTRON测量装置
公开(公告)号：JP2012052889A
公开(公告)日：2012-03-15
申请号：JP2010195043
申请日：2010-08-31
申请人： Toshiba Corp , 株式会社東芝
发明人： TAKEMURA MAKOTO , NAITO SUSUMU , SAKURAI SHUNGO , ISHIGE TAKAYUKI
IPC分类号： G21C17/108
摘要： PROBLEM TO BE SOLVED: To provide a neutron measuring device that reduces scattered neutrons and improves measurement accuracy of an occurrence position of neutrons in a neutron source.SOLUTION: A neutron measuring device of the present invention includes: a neutron detection device 1; a first moderator 2 that is provided on a neutron incident face side of the neutron detection device 1; and a second moderator 3 that is arranged to cover a face other than faces that are in contact with the neutron incident face of the first moderator 2 and the neutron detection device, and has a higher moderating effect than the first moderator 2.
摘要翻译：要解决的问题：提供一种中子测量装置，其减少散射中子并提高中子源中的中子发生位置的测量精度。解决方案：本发明的中子测量装置包括：中子检测装置1; 设置在中子检测装置1的中子入射面侧的第一调节器2; 以及第二调节器3，其布置成覆盖与第一调节剂2和中子检测装置的中子入射面接触的面以外的面，并且具有比第一调节剂2更高的调节作用。版权所有（C）2012，JPO＆INPIT

2. 发明专利

JP2007198997A Super-critical pressure water cooled reactor and super-critical pressure water cooled fuel assembly 审中-公开
标题翻译：超临界压力水冷却反应堆和超临界压力水冷却燃料装配
公开(公告)号：JP2007198997A
公开(公告)日：2007-08-09
申请号：JP2006020146
申请日：2006-01-30
申请人： Toshiba Corp , 株式会社東芝
发明人： OKAWA MASAHIRO , MOROOKA SHINICHI , SAKURAI SHUNGO
IPC分类号： G21C15/02 , G21C1/08 , G21C3/326
CPC分类号： Y02E30/38
摘要： PROBLEM TO BE SOLVED: To secure a slowing-down power required by a reactor core of a thermal neutron super-critical pressure water cooled reactor without causing decrease in steam temperature at an outlet of a reactor core.
SOLUTION: A super-critical pressure water cooled reactor comprises a plurality of fuel assemblies 30 consisting of a water rod 6, a plurality of fuel rods 3 and a channel box 1 surrounding the side faces of them, and super-critical pressure water is used as a moderator and a cooling medium. The cooling medium is made to flow upward outside of the channel box 1 and inside of the channel box 1 to the outside of the water rod 6. A water rod moderator feeding passage 16 for feeing the moderator into the water rod 6 from outside of the channel box 1 is formed at a height corresponding the top of the fuel rod 3, and a moderator discharging hole 13 is formed at the height corresponding to the bottom of the fuel rod 2 in the wall of the water rod 6 to allow the cooling medium in the water rod 6 to flow out of the water rod 6 inside of the channel box 1 to cause a downward flow of the moderator in the water rod 6.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：确保热中子超临界压力水冷却反应堆的反应堆芯所需的减速功率，而不会引起反应堆堆芯出口处蒸汽温度的降低。解决方案：超临界压力水冷却反应器包括由水杆6，多个燃料棒3和围绕它们的侧面的通道箱1组成的多个燃料组件30和超临界压力水用作调节剂和冷却介质。使冷却介质在通道箱1的外部和通道箱1的内部向外流动到水杆6的外部。一个水杆调节剂供给通道16，用于从慢冷器的外部向冷凝器6供水通道箱1形成在与燃料棒3的顶部相对应的高度处，并且在与水杆6的壁中的燃料棒2的底部相对应的高度处形成有减速剂排放孔13，以允许冷却介质在水杆6中从通道箱1内部的水杆6流出，以使慢化剂在水杆6中向下流动。版权所有（C）2007，JPO＆INPIT

3. 发明专利

JP2007192550A Method of calculating particle transportation, calculation device and program, method of calculating nuclear constant, calculation device and program, nuclear reactor simulation method, nuclear reactor simulator, and nuclear reactor simulation program 有权
标题翻译：计算粒子运输，计算装置和程序的方法，计算核常数计算方法，计算装置和程序，核反应堆模拟方法，核反应堆模拟器和核反应堆模拟程序
公开(公告)号：JP2007192550A
公开(公告)日：2007-08-02
申请号：JP2006008197
申请日：2006-01-17
申请人： Toshiba Corp , 株式会社東芝
发明人： UENOHARA YUJI , SAKURAI SHUNGO , YOSHIDA NORIYUKI
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To evaluate in a short time a nuclear constant of a fuel assembly having an optional shape and an optional size.
SOLUTION: A method of calculating particle transportation has a step (S3) of generating a low-discrepancy sequence, a step (S4) of designating the start point and the direction of ray tracing by the sequence, a step (S5) of ray tracing by using the start point and the direction and determining the locus of a particle, a step (S6) of generating a Green function of a transportation equation of the particle, and a step (S7) of solving a particle transportation Boltzmann equation by using the Green function and evaluating a particle distribution. The nuclear constant is generated from the particle distribution acquired thereby.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：为了在短时间内评估具有任选形状和任选尺寸的燃料组件的核常数。解决方案：计算粒子输送的方法具有产生低差异序列的步骤（S3），指定序列的起始点和光线跟踪方向的步骤（S4），步骤（S5）通过使用起点和方向确定光线跟踪并确定粒子的轨迹，生成粒子的运输方程的绿色函数的步骤（S6）以及求解粒子运输波尔兹曼方程的步骤（S7）通过使用Green函数和评估粒子分布。核常数由其获得的粒子分布产生。版权所有（C）2007，JPO＆INPIT

4. 发明专利

JP2015007596A 溶融燃料切削装置及びその切削方法有权
标题翻译：螺旋式燃料切割装置及其切割方法
公开(公告)号：JP2015007596A
公开(公告)日：2015-01-15
申请号：JP2013133409
申请日：2013-06-26
申请人：株式会社東芝 , Toshiba Corp
发明人： KIMURA REI , TAKIWAKI KENYA , TAKEUCHI YUTAKA , SAKURAI SHUNGO , YAMAMOTO YASUSHI , YASUDA TOSHIHIRO
IPC分类号： G21F9/30 , G21F3/00
摘要：【課題】溶融燃料の切削作業を行いつつ、作業中の臨界安全性を十分に確保可能な溶融燃料切削装置を提供する。【解決手段】実施形態によれば、溶融した核燃料を切削工具1により切削する溶融燃料切削装置であって、切削工具1が中性子吸収材を含む。また、切削工具1は、着脱部3を介して切削工具1を駆動する駆動部2に着脱可能に取り付けられている。さらに、切削工具1は、切削工具1が着脱部3から切り離されたときに面積が拡がる展開部を設けるようにしてもよい。【選択図】図1
摘要翻译：要解决的问题：提供一种熔融燃料切割装置，其能够在进行熔融燃料的切割操作时令人满意地确保工作期间的关键安全性。解决方案：熔融燃料切割装置利用切割工具1对熔融核燃料进行切割。切割工具1包括中子吸收体。切割工具1可拆卸地附接到驱动切割工具1的驱动器2，驱动器2由附接/拆卸部分3插入。切割工具1可以包括显影部分，当切割工具1从附件/拆卸部分3。

5. 发明专利

JP2013104790A Emergency power supply system 审中-公开
标题翻译：紧急电源系统
公开(公告)号：JP2013104790A
公开(公告)日：2013-05-30
申请号：JP2011249075
申请日：2011-11-14
申请人： Toshiba Corp , 株式会社東芝
发明人： KITAMURA TAKU , SAKAI NORIO , TAKEUCHI YUTAKA , SAKURAI SHUNGO , TAKIWAKI KENYA
IPC分类号： G21D3/04 , G21D7/04 , H01L35/30
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To enable a stable supply of emergency power when all power sources are lost.SOLUTION: An emergency power supply system includes: a chemical heat storage facility 11 that includes a reaction vessel 16 filled with a heat storage medium 28 and a storage container 17 connected to the reaction vessel via a communication pipe 18 and stores heat using a chemical reaction of the heat storage medium to radiate the heat; a first heat exchange loop 13 for performing heat exchange between the storage container and a nuclear reactor vessel primary system to heat the storage container; a thermoelectric conversion device 12 for generating electricity by a temperature difference between a high-temperature part 12A and a low-temperature part 12B; a second heat exchange loop 14 for performing heat exchange between the reaction vessel and a high-temperature part of the thermoelectric conversion device to heat the high-temperature part; and a final radiation cooling loop 15 for performing heat exchange between a low-temperature part of the thermoelectric conversion device and a final heat sink 25 to cool the low-temperature part. Further, a valve disposed in the first heat exchange loop 13 passively open-operates when power is lost to cause the storage container to be heated by a nuclear reactor vessel primary coolant to radiate the heat stored in the chemical heat storage facility 11 so that the thermoelectric conversion device 12 generates power using the heat.
摘要翻译：要解决的问题：为了在所有电源丢失时能够稳定地提供应急电源。解决方案：应急电源系统包括：化学蓄热设备11，其包括填充有蓄热介质28的反应容器16和经由连通管18连接到反应容器的储存容器17，并且使用蓄热介质的化学反应来散热; 第一热交换回路13，用于在存储容器和核反应堆容器主系统之间进行热交换以加热存储容器; 用于通过高温部分12A和低温部分12B之间的温度差发电的热电转换装置12; 用于在反应容器和热电转换装置的高温部分之间进行热交换以加热高温部分的第二热交换回路14; 以及用于在热电转换装置的低温部分和最终散热器25之间进行热交换以最终冷却低温部分的最终辐射冷却回路15。此外，当功率消失时，设置在第一热交换回路13中的阀被动地打开，以使存储容器被核反应堆容器的一次冷却剂加热，以辐射存储在化学储热设备11中的热量，热电转换装置12使用热量来发电。版权所有（C）2013，JPO＆INPIT

6. 发明专利

JP2011017551A Device and method for measuring void fraction 审中-公开
$Device and method for measuring void fraction$
标题翻译：用于测量无声分段的装置和方法
公开(公告)号：JP2011017551A
公开(公告)日：2011-01-27
申请号：JP2009160712
申请日：2009-07-07
申请人： Toshiba Corp , 株式会社東芝
发明人： SAKURAI SHUNGO
IPC分类号： G21C17/038
摘要： PROBLEM TO BE SOLVED: To measure a local void fraction inside a core, in real time.SOLUTION: A void fraction measuring device 10, which measures void fraction inside a core of a boiling water reactor includes a detector assembly 20, a void fraction dependency memory 13 and a void fraction calculating device 14. The detector assembly 20, which includes a neutron detector 11 and a gamma-ray detector 12, is placed inside the core. The void fraction dependency memory 13 stores the void fraction dependency of the ratio of the neutron flux measured by the neutron detector 11 to the intensity of the gamma rays measured by the gamma-ray detector 12. The void fraction calculating device 14, to which the neutron flux measured by the neutron detector 11 and the intensity of the gamma rays measured by the gamma-ray detector 12 are conveyed, calculates the ratio of the neutron flux to the intensity of the gamma rays and computes a void fraction, on the basis of the ratio of the former to the latter and the void fraction dependence.
摘要翻译：要解决的问题：实时测量芯内的局部空隙率。解决方案：测量沸水反应堆核心内的空隙率的空隙分数测量装置10包括检测器组件20，空隙率依赖性存储器13和空隙分数计算装置14.包括中子检测器11和伽马射线检测器12的检测器组件20放置在芯内。空隙率依存存储器13存储由中子检测器11测量的中子通量与由γ射线检测器12测量的伽马射线强度的比率的空隙率依赖性。空隙率计算装置14，传送由中子检测器11测量的中子通量和由伽马射线检测器12测量的伽马射线的强度，计算出中子通量与γ射线强度的比值，并基于前者与后者的比率和空隙率依赖性。

7. 发明专利

JP2010019806A Pressurized-water reactor and fuel assembly used therefor 审中-公开
标题翻译：加压水反应器和燃料组件
公开(公告)号：JP2010019806A
公开(公告)日：2010-01-28
申请号：JP2008183031
申请日：2008-07-14
申请人： Toshiba Corp , 株式会社東芝
发明人： SAKURAI SHUNGO
IPC分类号： G21C3/322 , G21C3/324
CPC分类号： Y02E30/38
摘要： PROBLEM TO BE SOLVED: To prevent the lateral flow of the coolant in the fuel assembly in a pressurized-water reactor.
SOLUTION: The fuel assembly 10 loaded to the pressurized-water reactor is configured in such a way that a plurality of fuel rods 4 containing a nuclear fuel material, intra-reactor instrumentation guide thimbles 6 and control rod guide thimbles 7 are arranged in a square lattice shape and the outer circumference is surrounded by a lateral flow control plate 1 of a square tube shape. When loading a pressurized-water reactor loaded with a so called can-less type fuel assembly, the fuel rods 4 of the outermost circumference can be configured not to interfere with the lateral flow control plate 1 and the neighboring fuel assembly, even if the outer width of the flow control plate 1 is made equal to the outer width of the fuel assembly by reducing the outer diameter of the outermost circumference of the fuel rods 4 or by reducing the fuel rod pitch of the outermost circumference of the fuel rods 4.
COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：为了防止加压水反应器中的燃料组件中的冷却剂的横向流动。解决方案：装载到加压水反应堆的燃料组件10被配置成使得包含核燃料材料，反应堆内仪表导向套管6和控制棒导向套管7的多个燃料棒4被布置并且外周由方管形状的侧流控制板1包围。当装载装有所谓的无罐式燃料组件的加压水反应器时，最外周的燃料棒4可以构造成不干扰侧流控制板1和相邻的燃料组件，即使外部通过减少燃料棒4的最外周的外径或通过减少燃料棒4的最外周的燃料棒间距，使流量控制板1的宽度等于燃料组件的外部宽度。 P>版权所有（C）2010，JPO＆INPIT

8. 发明专利

JP2014224764A 小型原子炉およびその制御方法审中-公开
标题翻译：小核反应堆及其控制方法
公开(公告)号：JP2014224764A
公开(公告)日：2014-12-04
申请号：JP2013104170
申请日：2013-05-16
申请人：株式会社東芝 , Toshiba Corp
发明人： SAKURAI SHUNGO , KITAMURA TAKU , YAMAMOTO YASUSHI , TAKIWAKI KENYA
IPC分类号： G21C7/28
CPC分类号： Y02E30/39
摘要：【課題】液体状の反射体のみで原子炉の反応度を制御可能とするとともに、給排液管又は給排気管が破断又は損傷した場合でも炉心の損傷を抑制する。【解決手段】炉心1の周囲に配置され内部に液体の反射体2aが収容される反射体容器2と、圧力容器5を貫通し前記反射体容器2の上部に接続される給排液管3及び給排気管4と、を有し、前記反射体2aの液位を調整することで炉心1の反応度を制御する小型原子炉であって、前記給排液管3及び給排気管4が前記圧力容器5を貫通する貫通部と、前記給排液管3及び給排気管4と反射体容器2との接続部が前記炉心1の最上端1aよりも高い位置にある。【選択図】図1
摘要翻译：要解决的问题：提供一种能够仅通过液体反射器控制反应器的反应性的小核反应堆，并且即使当液体供给/排出管或气体供给/放电管断裂时也能够防止反应堆堆芯的损坏或损坏。解决方案：小型核反应堆包括：反射器容器2，其设置在反应堆芯1周围以在其中存储液体反射器2a; 以及液体供给/排出管3和气体供给/排出管4，其穿过压力容器5并连接到反射器容器2的上部，通过调节反应堆堆芯1的反应性，的反射器2a的液体。液体供给/排出管3和气体供给/排出管4穿过压力容器5的穿透部分和液体供应/排出管3和气体供应/排出管4与反射器容器连接的连接部分 2被定位成高于反应堆堆芯1的最上端1a。

9. 发明专利

JP2014145635A Core fused material extracting method and system 审中-公开
标题翻译：核心熔融材料提取方法和系统
公开(公告)号：JP2014145635A
公开(公告)日：2014-08-14
申请号：JP2013013847
申请日：2013-01-29
申请人： Toshiba Corp , 株式会社東芝
发明人： KITAMURA TAKU , SAKAI NORIO , TAKEUCHI YUTAKA , SAKURAI SHUNGO , GUNJI SATOSHI , HAYASHI YAMATO
IPC分类号： G21F9/30
摘要： PROBLEM TO BE SOLVED: To extract a core fused material after a severe accident of a nuclear power plant while keeping the subcriticality.SOLUTION: The core fused material extracting system 10 crushes a core fused material lump 1 to be extracted into core fused material pieces 2 and extracts them. The system 10 includes a fine crushing device 11 that includes a drilling section 14 for drilling the core fused material lump 1 at a tip of a rotation shaft 15, drills the core fused material lump 1 by rotation of the drilling section 14 to change the shape thereof, and crushes it into fine core fused material pieces 2. The drilling section 14 of the fine crushing device is configured so that, when the core fused material lump 1 is drilled for shape change, the shape is changed in the direction in which the superficial area of the core fused material lump 1 per volume deviates from a spherical shape and becomes large.
摘要翻译：要解决的问题：在核电站发生严重事故后提取核心熔融材料，同时保持次临界。解决方案：芯熔融材料提取系统10将芯熔融材料块1压碎以提取到芯熔料2中并提取它们。系统10包括细碎破碎装置11，该破碎装置11包括用于在旋转轴15的尖端处钻取核心熔融材料块1的钻孔部分14，通过钻孔部分14的旋转来钻取芯熔融材料块1以改变形状将其粉碎成细芯材料片2.细碎破碎装置的钻孔部分14构造成使得当芯熔融材料块1被钻孔以形状改变时，其形状沿着每个体积的芯部熔融材料块1的表面积偏离球形并变大。

10. 发明专利

JP2014106035A Supercritical pressure light water cooled nuclear reactor 审中-公开
标题翻译：超临界轻水冷却核反应堆
公开(公告)号：JP2014106035A
公开(公告)日：2014-06-09
申请号：JP2012257535
申请日：2012-11-26
申请人： Toshiba Corp , 株式会社東芝
发明人： SAKURAI SHUNGO , KITAMURA TAKU , KIMURA REI
IPC分类号： G21C15/02 , G21C1/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To cause a core flow amount to increase by using a part of supercritical pressure steam as a recirculating flow, and thereby to attain improvement in a thermal transfer characteristic of cooling water and increase in output improvement, and to maintain soundness of a pressure vessel.SOLUTION: The supercritical pressure light water cooled nuclear reactor includes: an intermediate vessel 2 that accommodates a reactor core 1, a plurality of cylindrical members 7 arranged at an upper part of the reactor core and a steam reservoir 8 formed at an upper part of the cylindrical member; a pressure vessel 3 that accommodates the intermediate vessel 2; a plurality of water supply pipes 5 that is provided on a side wall of the intermediate vessel 2, and guides supercritical pressure light water 14 flowed into the pressure vessel 3 to the intermediate vessel 2; and an opening 11 that is provided on a side wall of the steam reservoir 8 and causes a part of supercritical pressure steam 15 to be flowed out to the intermediate vessel 8.
摘要翻译：要解决的问题：通过使用一部分超临界压力蒸汽作为再循环流使核心流量增加，从而提高冷却水的热传递特性并提高输出改善，并且保持良好的压力容器。解决方案：超临界压力轻水冷却核反应堆包括：容纳反应堆堆芯1的中间容器2，布置在反应堆芯的上部的多个圆柱形构件7和形成在反应堆芯1的上部的蒸汽储存器8。圆柱体的上部; 容纳中间容器2的压力容器3; 多个供水管5设置在中间容器2的侧壁上，并将超临界压力轻水14引导到压力容器3中的中间容器2; 以及设置在蒸汽容器8的侧壁上并使一部分超临界压力蒸汽15流出到中间容器8的开口11。

你已经成功收藏专利！

检索式保存成功!

IPRDB

热门服务

关于我们

友情链接

联系方式