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    • 31. 发明专利
    • Reactor core of light-water reactor, and fuel assembly
    • 轻水反应堆的核反应堆和燃料组件
    • JP2010032559A
    • 2010-02-12
    • JP2009262499
    • 2009-11-18
    • Hitachi Ltd株式会社日立製作所
    • TAKEDA RENZOMIWA JUNICHIMORIYA KIMIAKI
    • G21C5/00G21C3/328G21C3/62
    • Y02E30/38
    • PROBLEM TO BE SOLVED: To provide a reactor core of a light-water reactor and a fuel assembly capable of further improving the degree of combustion by observing safety restriction conditions and increasing nuclear non-proliferation resistance properties, and capable of performing multiple-recycle and decreasing trans-uranium nuclides. SOLUTION: The reactor core flow rate of BWR is adjusted to a set reactor core flow rate determined from characteristics shown in Fig.2 according to the ratio of Pu-239 in TRU included in a new fuel assembly loaded to the reactor core. The reactor core flow rate is held at a set reactor core flow rate in the reactor core through each operation cycle of BWR. As a result, the ratio of a plurality of isotopes of TRU included by the fuel assembly when the fuel assembly is taken out of the BWR reactor core as a spent fuel assembly becomes essentially the same as the ratio of the isotopes of TRU included by the fuel assembly in the state of the new fuel assembly loaded to the BWR reactor core. The ratio of Pu-239 in TRU included in the new fuel assembly is not less than 40% and not more than 50%. COPYRIGHT: (C)2010,JPO&INPIT
    • 要解决的问题:提供一种轻水反应堆的反应堆堆芯和燃料组件,其能够通过观察安全限制条件和增加核不扩散阻力特性来进一步提高燃烧程度,并且能够执行多个 反循环和减少反铀核素。 解决方案:将BWR的反应堆堆芯流量调整到根据图2所示特性确定的设定的反应堆堆芯流量,根据加载到反应堆堆芯的新燃料组件中包含的TRU中的Pu-239的比例 。 通过BWR的每个操作循环,反应堆堆芯流量在反应堆堆芯中以设定的反应堆堆芯流速保持。 结果,当将燃料组件作为乏燃料组件从BWR反应堆堆芯中取出时,由燃料组件包括的多个同步物的TRU的比率变得基本上与TRU所包含的TRU的同位素的比率相同, 燃料组件处于装载到BWR反应堆堆芯的新燃料组件的状态。 新燃料组件中包含的TRUU中的Pu-239比例不小于40%且不超过50%。 版权所有(C)2010,JPO&INPIT
    • 35. 发明专利
    • Nuclear fuel assembly
    • 核燃料装配
    • JP2009156628A
    • 2009-07-16
    • JP2007332600
    • 2007-12-25
    • Global Nuclear Fuel-Japan Co Ltd株式会社グローバル・ニュークリア・フュエル・ジャパン
    • SAEKI JUNNAGANO MAMORUDOISHIKAWA AKIKOTSUCHIDA TSUGUMIFUJIMAKI SHINGOGOTO DAISUKE
    • G21C3/328
    • Y02E30/31Y02E30/38
    • PROBLEM TO BE SOLVED: To provide a fuel assembly which can improve reactor shutdown margins while curbing the degradation in reactivity over a late period of an operation cycle in a reactor core whose output is improved or which is geared to longer operation.
      SOLUTION: Refueling nuclear fuel assemblies for a boiling water reactor where fuel rods and at least one water rod or water channel are bundled like a tetragonal lattice and the number of refueling assemblies to be replaced at once and to be loaded at the same time in refueling are more than 30% of that of assemblies loaded into the whole core have two or more kinds of fuel assemblies with different numbers of fuel rods (B) containing burnable poison in most domains of the central section except for blankets at the upper and lower ends in the axial direction. One or more of the fuel rods (B) in the fuel assemblies have low-concentration domains of the burnable poison in a domain (C) just under the blanket at the upper end in the axial direction and the average concentration of the burnable poison in the domain (C) of the fuel assemblies with the most number of the fuel rods (B) is set to exceed that of the burnable poison in the domain (C) of the fuel assemblies with the least number of the fuel rods (B).
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:提供一种燃料组件,其可以在抑制输出改善的反应堆堆芯中的运行周期的较晚期间或者适合于更长的操作的同时抑制反应性的降低,从而提高反应堆的停机裕度。 解决方案:加油用于沸水反应堆的核燃料组件,其中燃料棒和至少一个水杆或水通道如四方网格捆扎,并且立即更换并加载的加油组件的数量 加油时间超过加载到整个核心的组件的30%具有两个或更多种具有不同数量的燃料棒(B)的燃料组件(B),其在中部的大多数领域中含有可燃毒物,除了上部的毯子 和轴向的下端。 燃料组件中的一个或多个燃料棒(B)在轴向上端的橡皮布正下方的区域(C)中具有低浓度的可燃毒物区域,并且可燃性毒物的平均浓度 具有最多数量的燃料棒(B)的燃料组件的区域(C)设定为超过具有最少数量的燃料棒(B)的燃料组件的区域(C)中的可燃毒物的区域(C) 。 版权所有(C)2009,JPO&INPIT
    • 36. 发明专利
    • Fuel assembly and core of boiling water reactor using it
    • 燃料组装及其使用的锅炉水反应堆核心
    • JP2009145203A
    • 2009-07-02
    • JP2007322999
    • 2007-12-14
    • Global Nuclear Fuel-Japan Co Ltd株式会社グローバル・ニュークリア・フュエル・ジャパン
    • TSUCHIDA TSUGUMIFUJIMAKI SHINGOSAEKI JUN
    • G21C3/328G21C3/326G21C5/00
    • Y02E30/31Y02E30/38
    • PROBLEM TO BE SOLVED: To enhance the thermal margin of a fuel assembly loaded into a boiling water reactor with a D-lattice core.
      SOLUTION: Standard-length fuel rods 21, long and partially long fuel rods 22 and short and partially long fuel rods 23 are provided in a fuel assembly 51. The top edges of fuel effective parts of the long and partially long fuel rods 22 are lower than those of the standard-length fuel rods 21. The top edges of fuel effective parts of the short and partially long fuel rods 23 are lower than those of the long and partially long fuel rods 22. When the domain where these fuel rods 21, 22 and 23 are laid out is divided into a first domain 41 where the distance from a corner rod 25 facing two sides of a wide gap 35 is shorter than that from a corner rod 26 facing two sides of a narrow gap 34 and a second domain 42 except for the first domain 41, the total of axial lengths of the fuel effective parts of the fuel rods 21, 22 and 23 laid out in the first domain 41 is set to exceed that of axial lengths of the fuel effective parts of the fuel rods 21, 22 and 23 laid out in the second domain 42.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:提高装载到具有D-晶格核心的沸水反应堆中的燃料组件的热裕度。 解决方案:标准长度的燃料棒21,长和部分长的燃料棒22以及短和部分长的燃料棒23设置在燃料组件51中。长和部分长的燃料棒的燃料有效部分的顶部边缘 22短于标准长度的燃料棒21。短部分和部分长的燃料棒23的燃料有效部分的顶部边缘比长的和部分长的燃料棒22的上边缘低。当这些燃料 布置的杆21,22和23被分成第一区域41,其中,距离较宽间隙35的两侧面的拐角杆25的距离短于面向狭窄间隙34两侧的拐角杆26的距离, 除了第一区域41之外的第二区域42,布置在第一区域41中的燃料棒21,22和23的燃料有效部分的轴向长度的总和被设定为超过燃料有效部分的轴向长度的总和 的燃料棒21,22和23布置在第二区域4中 2.版权所有(C)2009,JPO&INPIT
    • 38. 发明专利
    • Method for controlling criticality of nuclear fuel cycle facility, method for manufacturing uranium dioxide powder, nuclear reactor's fuel rods, and fuel assembly
    • 控制核燃料循环设施关键性的方法,制造二氧化铀粉末的方法,核反应堆燃料炉和燃料装配
    • JP2008286529A
    • 2008-11-27
    • JP2007128975
    • 2007-05-15
    • Toshiba Corp株式会社東芝
    • WATANABE SHOICHIMIHASHI TAKESHIYOSHIOKA KENICHI
    • G21C19/40C01G56/00G21C3/328G21C3/62
    • C01G43/00G21C3/623G21C7/04G21C21/02Y02E30/38Y02E30/39
    • PROBLEM TO BE SOLVED: To reduce an influence on criticality control measures in nuclear fuel cycle facility, by uniformly adding trace amounts of gadolinia to nuclear reactor's fuel having an uranium enrichment of over 5 wt.%, and to attain an improvement of economic efficiency, by effectively utilizing a fuel cycle cost reduction effect through increase of enrichment in the fuel of the nuclear reactor.
      SOLUTION: By uniformly adding minute amounts, for example, less than 0.1 wt.% gadolinia to UO
      2 powder, having an uranium enrichment of over 5 wt.% which is to be handled in a fuel production plant, criticality control of nuclear fuel cycle facility is performed, such that the effective neutron multiplication factor becomes equal to or smaller than the maximum value of effective neutron multiplication factor at the limiting value of mass control or geometric control, which serves as constraint on criticality safety for UO
      2 powder having an uranium enrichment of 5 wt.%.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:为了减少对核燃料循环设备中的关键控制措施的影响,通过将铀浓度超过5重量%的核反应堆燃料均匀加入痕量的氧化钆,并获得改进 经济效益,通过增加核反应堆燃料的浓缩有效利用燃料循环成本降低效果。 解决方案:通过将铀浓度超过5重量%的少量的例如小于0.1重量%的氧化钆与UO SB 2粉末均匀地添加,其将在 燃料生产车间,执行核燃料循环设备的临界控制,使得有效中子倍增系数在质控或几何控制的极限值下等于或小于有效中子倍增系数的最大值,其作为约束 对于铀浓缩为5重量%的UO 2 粉末的临界安全性。 版权所有(C)2009,JPO&INPIT