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1. 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。

2. 发明专利

JP2004093435A Fuel assembly 审中-公开
公开(公告)号：JP2004093435A
公开(公告)日：2004-03-25
申请号：JP2002256500
申请日：2002-09-02
申请人： Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝
发明人： KITAMURA HIDEYA , OKADA SUKEYUKI , AKIBA YOSHIYUKI , MOROOKA SHINICHI , MIURA SHIGERU , YAMAMOTO YASUSHI , HAYASHI YAMATO
IPC分类号： G21C3/34 , G21C3/32 , G21C3/322 , G21C3/328
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To provide a fuel assembly having a critical power not lower than that of an evenly arranged fuel assembly of a conventional type by preventing a critical value of the unevenly arranged fuel assembly from being lowered. SOLUTION: The fuel assembly has an arrangement with a spacer of a lattice type including lateral plates 1-4 and longitudinal plates 1-5, and the thickness of the plate in a coarse part having fuel rods arranged at wide intervals is heavier than that of the plate in a dense part having the fuel rods arranged at narrow intervals. COPYRIGHT: (C)2004,JPO

3. 发明专利

JP2004028879A Fuel assembly and reactor core 审中-公开
公开(公告)号：JP2004028879A
公开(公告)日：2004-01-29
申请号：JP2002187855
申请日：2002-06-27
申请人： Toshiba Corp , 株式会社東芝
发明人： KUROKI MASAHIKO , SATO HISAKI , HAYASHI YAMATO
IPC分类号： G21C3/334 , G21C3/328
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To improve minimum critical power ratio and reactor shutdown margin of a boiling water reactor to reduce the size of control rods without degrading reactor shutdown margin.
SOLUTION: In a fuel assembly 1 having a plurality of fuel rods 2 bundled in a square grid, fuel rods contain a plurality of first fuel rods 10 having a first outer diameter and a plurality of second fuel rods 11 having a second outer diameter smaller than the first outer diameter, the first fuel rods are arranged in inner region of the fuel assembly and the second fuel rods are arranged in the periphery of the fuel assembly. A plurality of fuel rods constitute a plurality of sub-bundles having a plurality of fuel rods arranged in square grid and have a channel box 4 having square cross section shape covering whole side part of the sub-bundles, and partition plates 8 partitioning inside the channel box.
COPYRIGHT: (C)2004,JPO

4. 发明专利

JP2000241582A FUEL ASSEMBLY, FUEL ROD AND REACTOR CORE 失效
公开(公告)号：JP2000241582A
公开(公告)日：2000-09-08
申请号：JP3908499
申请日：1999-02-17
申请人： TOSHIBA CORP
发明人： UEDA KIYOSHI , MIYASHITA SHIGERU , HAYASHI YAMATO , KAWASHIMA MASATOSHI
IPC分类号： G21C3/06 , G21C3/16 , G21C3/17 , G21C3/28 , G21C3/324 , G21C3/326 , G21C3/328 , G21C7/00 , G21C7/06
摘要： PROBLEM TO BE SOLVED: To provide a fuel assembly, fuel rods and a reactor core for using MOX based on a new principle improving void coefficient. SOLUTION: A fuel assembly 1 is constituted, from the upstream to the downstream, of an upstream side blanket 17, an upstream side main heated region 16, a low concentration region 15, a downstream side main heated region 13 and a downstream side blanket 14. In the downstream side blanket 14, a low scattering space 6 and a moderator and coolant space are provided. When the void coefficient of the coolant rises, neutron moving area (distance) increases and the dispersed absorber segments can absorb neutrons in longer distance. On the other hand, the absorbing ability of the absorber segment is saturation type and does not reduce even with hardening of neutron spectrum and so the absorbing ability eventually increases and the void coefficient can be improved in negative direction.

5. 发明专利

JP2015052558A 溶融核燃料物質の搬出管理方法审中-公开
标题翻译：执行和管理熔炼核燃料材料的方法
公开(公告)号：JP2015052558A
公开(公告)日：2015-03-19
申请号：JP2013186325
申请日：2013-09-09
申请人：株式会社東芝 , Toshiba Corp
发明人： KAWANO SHOHEI , HAYASHI YAMATO , MORI ATSUSHI , SUZUKI ATSUSHI
IPC分类号： G21F9/00 , G21C17/06 , G21F9/30
摘要：【課題】溶融核燃料物質の搬出工程で、溶融核燃料物質に含まれるウラン235の含有率を簡便に解析し、再臨界を評価・管理する方法を提供する。【解決手段】溶融核燃料物質を昇降装置の端部に取り付けられた採取工具により採取する工程ステップ1と、採取した溶融核燃料物質の水中重量W1及び気中重量W2を測定する工程ステップ2、3と、炉心に装荷された核燃料物質の密度D0及びウラン235含有率U0と前記測定された水中重量W1及び気中重量W2とから前記採取した溶融核燃料物質中のウラン235含有率を算出する工程ステップ4と、前記算出されたウラン235含有率から前記溶融核燃料物質の再臨界を評価する工程ステップ5とを、有する。【選択図】図2
摘要翻译：要解决的问题：提供一种能够容易地分析在熔化的核燃料材料的执行步骤期间熔化的核燃料材料中包含的铀235的含有率以评估和管理重新生产的方法。解决方案：在步骤1中，a 使用附接到升降机的尖端的拾取工具拾取熔化的核燃料材料。在步骤2和3中，测量所拾取的熔融核燃料材料的水下重量W1和空气W2中的重量。在步骤4中，通过使用密度D0和安装在反应堆堆芯中的核燃料材料的铀235的含有率U0和测量的水下重量W1来计算拾取的熔融核燃料材料中所含的铀235的含有率并在空气中的重量W2中拾取熔化的核燃料材料。在步骤5中，通过使用计算的铀235含量率来评估熔化的核燃料材料的重新连接性。

6. 发明专利

JP2015010940A 溶融炉心切断装置および切断方法审中-公开
标题翻译： MULTEN REACTOR CORE CUTTING DEVICE AND CUTTING METHOD
公开(公告)号：JP2015010940A
公开(公告)日：2015-01-19
申请号：JP2013136725
申请日：2013-06-28
申请人：株式会社東芝 , Toshiba Corp
发明人： SASAKI FUMIYO , ISHIWATARI YUTAKA , FUJITA TOSHIYUKI , HAYASHI YAMATO
IPC分类号： G21F9/30 , G21C19/26 , G21C19/40
摘要：【課題】溶融炉心の融解物を切断する際、融解物の切断部の核分裂反応が活性化するのを抑制し、再臨界事象の発生を防ぐもの。【解決手段】本発明に係る溶融炉心切断装置は、溶融炉心2の融解物3を遠隔操作により切断する切断機構11Aと、この切断機構11Aにより切断される融解物3の切断部5に熱中性子吸収材料7を供給する材料供給機構12Aとを備えたことを特徴とするものである。【選択図】図6
摘要翻译：要解决的问题：为了防止在切割熔融反应堆芯的熔体期间熔体的切割部分的核裂变反应被活化，并且防止重新发生事件的发生。解决方案：熔融反应堆芯切割根据本发明的装置包括：切割机构11A，用于通过遥控器切割熔融反应堆堆芯2的熔体3; 以及供给由切割机构11A切割的熔融体3的切断部5用热中子吸收材料7供给的材料供给机构12A。

7. 发明专利

JP2014115143A Thermal neutron absorbing material and coating method using the same 审中-公开
标题翻译：热中子吸收材料和使用它的涂层方法
公开(公告)号：JP2014115143A
公开(公告)日：2014-06-26
申请号：JP2012268233
申请日：2012-12-07
申请人： Toshiba Corp , 株式会社東芝
发明人： SASAKI FUMIYO , ISHIWATARI YUTAKA , KATAYAMA YOSHINORI , FUJITA TOSHIYUKI , YOSHIOKA KENICHI , HAYASHI YAMATO
IPC分类号： G21F3/00 , G21C19/40
摘要： PROBLEM TO BE SOLVED: To provide a thermal neutron absorbing material which sufficiently absorbs thermal neutrons so that, for example, a recriticality state can be prevented from occurring during operations of demolishing a melting reactor core.SOLUTION: A thermal neutron absorbing material includes: particulate thermal neutron absorbers each of which has a thermal neutron absorption cross section of 100 barns or more; and resin layers coating each surface of the thermal neutron absorbers. The material is used for recriticality prevention during operations of demolishing a melting reactor core and for a coating of a fuel storage container. A gadolinium oxide or boron carbide is especially suitable for the thermal neutron absorbers.
摘要翻译：要解决的问题：提供一种充分吸收热中子的热中子吸收材料，使得例如在拆除熔融反应堆芯的操作期间可以防止再发生状态。解热：热中子吸收材料包括：颗粒热中子吸收体的热中子吸收截面为100巴以上。以及涂覆热中子吸收体的每个表面的树脂层。该材料用于拆除熔化反应堆堆芯和燃料储存容器的涂层操作期间的重新防止。氧化钆或碳化硼特别适用于热中子吸收剂。

8. 发明专利

JP2013205359A Gelatinous neutron absorber and molten core recovery method 审中-公开
标题翻译： GELATINOUS NEUTRON吸收器和MORE CORE RECOVERY方法
公开(公告)号：JP2013205359A
公开(公告)日：2013-10-07
申请号：JP2012077360
申请日：2012-03-29
申请人： Toshiba Corp , 株式会社東芝
发明人： FUJITA TOSHIYUKI , KATAYAMA YOSHINORI , ISHIWATARI YUTAKA , YOSHIOKA KENICHI , HAYASHI YAMATO
IPC分类号： G21F3/00 , G21C9/016 , G21C19/40 , G21F1/10
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To surely prevent recriticality of a radioactivated substance such as a molten core.SOLUTION: A gelatinous neutron absorber 10 is a gelatinous composite constituted by composing a thermal neutron absorption substance including an element whose thermal neutron absorption cross section becomes 100 barns or more and a gelatinous substance. The gelatinous neutron absorber 10 is constituted such that powder or a small piece of the same/different kind of thermal neutron absorption substance as/from the thermal neutron absorption substance including the composite is added to the gelatinous composite and can mold a coat by being applied on the surface of a molten core 11.
摘要翻译：要解决的问题：确保防止诸如熔融芯的放射性物质的重新生成。溶胶凝胶状中子吸收体10是由热中子吸收物质构成的凝胶状复合体，其包含热中子吸收截面为100巴的元素或更多和凝胶状物质。凝胶状中子吸收体10构成为使得与包含该复合体的热中子吸收物质相同/不同种类的热中子吸收物质的粉末或小片添加到凝胶状复合体中，并且可以通过涂布来形成涂层在熔核11的表面上。

9. 发明专利

JP2010256094A Control rod for nuclear reactor 有权
标题翻译：核反应堆控制棒
公开(公告)号：JP2010256094A
公开(公告)日：2010-11-11
申请号：JP2009104544
申请日：2009-04-22
申请人： Toshiba Corp , 株式会社東芝
发明人： UEDA KIYOSHI , YOSHIOKA KENICHI , KIKUCHI TSUKASA , NAKAMURA MITSUHARU , TAJIMA TOMOKO , HAYASHI YAMATO
IPC分类号： G21C7/113 , G21C7/10
CPC分类号： Y02E30/39
摘要： PROBLEM TO BE SOLVED: To provide a control rod for regulating power that makes the average reactivity value over its lifetime equivalent to that of a shut-down control rod, while achieving the mitigation of problems about blade history, reducing the usage of hafnium, and eliminating the non-integrity and difficulties in the manufacture due to welding deformation or mechanical imbalance. SOLUTION: The control rod CR includes: blades 1 made by confronting one piece of blade pieces 10 holding Hf plates 12 whose thickness in at least 1/4 segment is 1.5 to 2.5 mm with each other; a tie cross 4 arranged with a space secured along the shaft of the control rod CR to hold four blades 1 so that its cross section can be cruciform; a trap 13 arranged in a space between the confronted blade pieces 10 and filled with reactor water; water windows 3 arranged in at least 1/4 segment of each of the blade pieces 10, and forming partial hafnium loss sections; and a shaft center water region 5 arranged in a space between locations of the tie cross 4 with the shaft center water width CW of 10 to 40 mm in at least 1/4 segment of an effective part of the control rod CR. COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：为了提供一种用于调节功率的控制棒，其使得在其寿命中的平均反应性值等于关闭控制棒的平均反应性值，同时实现减轻关于叶片历史的问题，减少了使用铪，并消除由于焊接变形或机械不平衡而导致的制造中的不完整和困难。解决方案：控制杆CR包括：通过面对一个片材10制成的刀片1，刀片10保持在至少1/4段中的厚度彼此为1.5至2.5mm的Hf板12; 连接横梁4，其具有沿着控制杆CR的轴固定的空间，以保持四个叶片1，使得其横截面可以是十字形的; 设置在面对的叶片10之间并填充有反应器水的空间中的捕集器13; 每个叶片10的至少1/4节段布置的水窗3，并且形成部分铪损失部分; 以及轴心水区域5，其布置在接头十字4的位置之间的空间中，轴中心水宽度CW在控制杆CR的有效部分的至少1/4段中为10至40mm。版权所有（C）2011，JPO＆INPIT

10. 发明专利

JP2001004772A FUEL ASSEMBLY 失效
公开(公告)号：JP2001004772A
公开(公告)日：2001-01-12
申请号：JP17623999
申请日：1999-06-23
申请人： TOSHIBA CORP
发明人： YOSHIDA NORIYUKI , HAYASHI YAMATO
IPC分类号： G21C3/328 , G21C3/326
摘要： PROBLEM TO BE SOLVED: To improve the critical power of a fuel assembly by averaging the power of fuel rods and preventing the rising of boiling transition of specific fuel rods. SOLUTION: In a boiling water reactor fuel assembly wherein long size fuel rods N1 to N5 without gadolinia, long size fuel rods G1 and G2 with gadolinia and short size fuel rods V are arranged in a channel box and water rods 6 are arranged in the center part, all fuel rods G1 and G2 except the outermost part and the short size fuel rods V are installed by fuel pellets including burnable poison at least a part in a clad.

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