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    • 1. 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
    • 4. 发明专利
    • Core and fuel assembly for boiling water reactor
    • 锅炉水反应堆核心和燃料组件
    • JP2009198515A
    • 2009-09-03
    • JP2009136809
    • 2009-06-08
    • Hitachi Ltd株式会社日立製作所
    • TAKEDA RENZOAOYAMA TADAOMIWA JUNICHIIKEGAWA TOMOHIKOMORIYA KIMIAKI
    • G21C3/328G21C1/08G21C3/30G21C3/32G21C3/324G21C3/326G21C3/62G21C5/00
    • G21C3/326G21C1/084G21C3/32G21C5/18Y02E30/31Y02E30/38
    • PROBLEM TO BE SOLVED: To provide a core and fuel assemblies which make it possible (1) to curtail construction costs of a power plant by lowering the height of the core significantly, (2) to cut down fuel cycle costs by increasing the yield of plutonium during the operation of a reactor to prolong the life of the fuel assemblies and (3) to reduce power generation costs of the plant by extending an its continuous operation period to improve its availability while maintaining thermal margin and safety at the same level as those of boiling water reactors (BWRs) which are now operating.
      SOLUTION: The ratio of the number of fuel assemblies loaded into the core to the radix of a control rod drive mechanism is ≥3. The fuel assemblies contain an oxide of low enriched uranium where the average enrichment of the fuel assemblies is 3 wt.% to 8 wt.% or a mixed oxide where the average fissile plutonium enrichment of the fuel assemblies is both ≥2 wt.% and less than 6 wt.%. In the BWR core of a burner type loaded with such fuel assemblies, the average weight of uranium, plutonium, minor actinides contained in a unit volume of a core domain is 2.1 to 3.4 kg/l in terms of values obtained when they are not burnt.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:提供一种核心和燃料组件,使得可以通过大幅降低铁芯的高度来减少发电厂的建造成本,(2)通过增加燃料循环成本来降低燃料循环成本 在反应堆运行期间钚的产量延长燃料组件的寿命和(3)通过延长其连续运行时间来降低发电成本,以提高其可用性,同时保持同样的热裕度和安全性 水平与现在正在运行的沸水反应堆(BWR)一样。

      解决方案:加载到铁​​芯中的燃料组件数量与控制棒驱动机构的基数之比≥3。 燃料组件包含低浓度铀的氧化物,其中燃料组件的平均浓度为3重量%至8重量%,或燃料组件的平均易裂变钚浓缩度≥2重量%的混合氧化物,以及 小于6重量%。 在装载有这种燃料组件的燃烧器类型的BWR型芯中,核心区域的单位体积中所含的铀,钚,次要锕系元素的平均重量为2.1至3.4kg / l,当它们不被燃烧时获得的值 。 版权所有(C)2009,JPO&INPIT

    • 6. 发明专利
    • Light-water reactor core and fuel assembly
    • 轻水反应堆芯和燃料组件
    • JP2010025948A
    • 2010-02-04
    • JP2009249615
    • 2009-10-30
    • Hitachi Ltd株式会社日立製作所
    • TAKEDA RENZOMIWA JUNICHIMORIYA KIMIAKI
    • G21C3/328G21C5/00G21C7/26
    • Y02E30/38Y02E30/39
    • PROBLEM TO BE SOLVED: To provide a light-water reactor core and a fuel assembly that can extend burnup by enlarging nuclear nonproliferation resistance while observing safety restrictions and conditions and make multi-recycling possible. SOLUTION: The core flow of a BWR is regulated in such a way as to be a setup core flow that is determined from the characteristic of Fig. 2 according to the percentage of Pu-239 in TRU contained in a new fuel assembly that is loaded into the core. The core flow is held at the setup core flow in the core through each operation cycle of the BWR. Thus, the percentage of a plurality of isotopes of TRU contained in the fuel assembly at the point of time where the fuel assembly is taken out of the BWR core as a used fuel assembly becomes substantially equal to the percentage of those isotopes of TRU contained in the fuel assembly when the fuel assembly is loaded into the BWR core as a new fuel assembly. The percentage of Pu-239 in TRU contained in a new fuel assembly is not less than 3% and not greater than 45%. COPYRIGHT: (C)2010,JPO&INPIT
    • 要解决的问题:提供一种轻水反应堆核心和燃料组件,通过在遵守安全限制和条件的同时扩大核不扩散阻力并使多重循环成为可能,从而延长燃耗。 解决方案:BWR的核心流程以这样的方式进行调节,即作为从图1的特性确定的设置核心流程。 2根据装载在核心中的新燃料组件中的TRU中的Pu-239的百分比。 核心流程通过BWR的每个操作周期保持在核心的安装核心流程。 因此,在将燃料组件作为使用燃料组件从BWR铁心中取出的时间点处的燃料组件中所含的多个同位素的多个同位素的百分比基本上等于TRU所含的同位素的百分比 燃料组件当燃料组件作为新的燃料组件装载到BWR芯中时。 新燃料组件中所含的TRUU中的Pu-239的百分比不小于3%且不大于45%。 版权所有(C)2010,JPO&INPIT
    • 7. 发明专利
    • Boiling water type light water reactor core
    • 锅炉水型轻水反应堆核心
    • JP2008045874A
    • 2008-02-28
    • JP2006218714
    • 2006-08-10
    • Hitachi Ltd株式会社日立製作所
    • MIWA JUNICHITAKEDA RENZOMITSUYASU TAKESHIMORIYA KIMIAKI
    • G21C3/324G21C3/328G21C5/00
    • Y02E30/31Y02E30/38
    • PROBLEM TO BE SOLVED: To provide a boiling water type light water reactor core capable of increasing output, while keeping a thermal margin in the same degree as a BWR in operation at present, and uniformizing furthermore cooling of each fuel rod in a fuel assembly at an increased output time.
      SOLUTION: The fuel assembly 5 constituting this boiling water type light water reactor core includes fuel rods 6A, 6B, 6C, 6D, 6E including uranium and not including gadolinium, and fuel rods 6F, 6G, 6H including uranium and gadolinium. The fuel rod 6E is a partial length fuel rod. The average wall thickness of a channel box 7 is 2.6 mm, and the ratio of the inner width of the channel box 7 to the width of a fuel assembly lattice is 0.863. An average uranium enrichment on a cross section of the fuel assembly 5 is 4.73 wt.%. The uranium weight included in a unit volume in a core domain is 2.4 kg/l. A reactor output can be improved by 20% from the present BWR/5.
      COPYRIGHT: (C)2008,JPO&INPIT
    • 要解决的问题:提供一种能够增加输出的沸水型轻水反应堆堆芯,同时保持与当前操作中的BWR相同程度的热裕度,并且进一步均匀化每个燃料棒的冷却 燃料组件在增加的输出时间。 构成该沸水型轻水反应堆堆芯的燃料组件5包括包括铀的不包括钆的燃料棒6A,6B,6C,6D,6E以及包括铀和钆的燃料棒6F,6G,6H。 燃料棒6E是部分长度的燃料棒。 通道箱7的平均壁厚为2.6mm,通道箱7的内部宽度与燃料组件格架的宽度的比为0.863。 在燃料组件5的横截面上的平均铀浓缩为4.73重量%。 核心区域中单位体积的铀重量为2.4 kg / l。 反应堆产量可以比现在的BWR / 5提高20%。 版权所有(C)2008,JPO&INPIT
    • 9. 发明专利
    • Nuclear power plant
    • 核电站
    • JP2005140711A
    • 2005-06-02
    • JP2003379257
    • 2003-11-10
    • Hitachi Ltd株式会社日立製作所
    • TAKAHASHI SHIROOTSUKA MASAYASHIINA KOJIHISATSUNE SHINICHIMORIYA KIMIAKI
    • G21C19/26G21D1/00G21D1/02
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To provide a nuclear power plant equipped with structures for capturing foreign matter inside feed water pipe lines for a nuclear reactor.
      SOLUTION: The nuclear power plant has structures for capturing foreign matters using gravity, inertia force, centrifugal force or magnetic force which are mounted on the route from a high-pressure feed water heater closest to the reactor to a feed water sparger in it. The plant also has structures for capturing foreign matters by using filters downstream from curved pipes, branch pipes and confluent pipes are mounted on the route, from the high-pressure feed water heater closest to the reactor to the feed water sparger in it. A safer nuclear power plant is realized, by restraining the damages to in-pile structures and equipment caused by the foreign matters.
      COPYRIGHT: (C)2005,JPO&NCIPI
    • 要解决的问题:提供一种装备有用于在核反应堆的给水管线内捕获异物的结构的核电站。 解决方案:核电站具有使用重力,惯性力,离心力或磁力捕获异物的结构,其安装在从最接近反应器的高压给水加热器到馈送水分配器的路线上 它。 该设备还具有通过使用弯曲管下游的过滤器,分支管和汇流管从最靠近反应器的高压给水加热器安装到其中的给水喷射器的路线上来捕获异物的结构。 通过限制由异物引起的桩内结构和设备的损坏,实现了更安全的核电厂。 版权所有(C)2005,JPO&NCIPI