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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
    • ADVANCED BOILING WATER REACTOR
    • JPH10300879A
    • 1998-11-13
    • JP10425797
    • 1997-04-22
    • HITACHI LTD
    • TAKII TAICHIMORIYA KIMIAKISONEDA HIDEO
    • G21C7/08G21D3/04
    • PROBLEM TO BE SOLVED: To reduce the equipment cost by reducing the scram function of a control rod driving mechanism in a reactor peripheral part and a hydraulic control unit, and shortening the scram insertion time of a control rod or enhancing neutron absorbability as occasion demands. SOLUTION: To a reactor core are charged, for example, 872 fuel assemblies to form, for example, 205 reactor cells 2 in which one control rod is surrounded by 4 fuel assemblies except, for example, 52 partial peripheral part fuel assemblies 1. Control rod driving mechanisms of, for example, 161 reactor cells 2 having scram function are connected in sets of two to one hydraulic control unit. In this case, no scram function is imparted to, for example, 44 slashed peripheral reactor cells 3, and they are not connected to the hydraulic control units. Consequently, 22 hydraulic control unit can be reduced in this example, compared with in the past, and the equipment cost can be reduced.