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31. 发明专利

JP2004286606A High-temperature fuel assembly for raising temperature of cooling water outlet, guide tube for upper part of control rod and high-temperature control rod in bwr 有权
公开(公告)号：JP2004286606A
公开(公告)日：2004-10-14
申请号：JP2003079360
申请日：2003-03-24
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C5/00 , G21C3/07 , G21C3/17 , G21C3/28 , G21C3/30 , G21C3/324 , G21C3/328 , G21C3/60 , G21C3/62
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To cut power generation costs by obtaining high-temperature superheated steam at a core outlet to heighten the thermal efficiency and improve the power generation efficiency and reduce the contamination due to exhaust heat and radioactive waste at the same time, in fuel assemblies and a control rod constituting a core of a boiling water reactor (BWR).
SOLUTION: Fuel assemblies and a control rod are composed of: protective fuel rods 140 made of pellets of a sintered fertile material; high-temperature fuel assemblies 100 consisting of output fuel rods 150 made of multilayer sintered pellets; a guide tube 110 for the upper part of the control rod; and a high-temperature control rod 120. As to a material for high-temperature cladding tubes and others, the percentage of nickel , not including cobalt, in an iron-based alloy demonstrated by gas turbine blades is 26% or less. The high-temperature superheated steam is obtained at the core outlet by equalizing the flow rate at a core inlet with that of the steam at the core outlet.
COPYRIGHT: (C)2005,JPO&NCIPI

32. 发明专利

JP2004257733A Core of cross type control rod boiling water reactor 审中-公开
公开(公告)号：JP2004257733A
公开(公告)日：2004-09-16
申请号：JP2003045309
申请日：2003-02-24
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C5/00 , G21C3/30 , G21C3/322 , G21C3/328 , G21C5/20 , G21C7/113
CPC分类号： Y02E30/31 , Y02E30/38 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To keep the safety by setting the coefficient of void reactivity negative while keeping high economical efficiency of MOX fuel assembly where an interval between fuel rods is narrowed to increase the conversion rate, with respect to a core of a cross type control rod boiling water reactor.
SOLUTION: A vacant assembly 100 is replaced for a part of the fuel assembly loaded on the core, whereby the leakage of neutrons to the vertical direction of the core is increased, and the nuclear fission is suppressed, when a flow rate is decreased and the voids are increased.
COPYRIGHT: (C)2004,JPO&NCIPI

33. 发明专利

JP2017083215A 超ウラン核燃料集合体（１３０）审中-公开
公开(公告)号：JP2017083215A
公开(公告)日：2017-05-18
申请号：JP2015209436
申请日：2015-10-24
申请人：白川利久 , Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C3/60 , G21C3/06 , G21C3/28 , G21C3/326 , G21C7/24
CPC分类号： Y02E30/40
摘要：【課題】沸騰水型原子炉においてボイド反応度係数を正にする傾向があるPuを始めとする超ウラン元素を効率よく燃焼でき、かつ、再処理し易い核燃料集合体を提供する。【解決手段】超ウラン元素核燃料棒131は、ステンレス製の鞘である被覆管151の中に中空燃料筒132を装荷密封してなる。中空燃料筒132は、非α-nホウ素含有材製またはホウ素含有材製の固体中性子吸収減速材円筒134の内側表面または外側表面に超ウラン元素金属133を塗布してなる。固体中性子吸収減速材棒161は、ステンレス製の鞘である被覆管152の中にホウ素含有材円柱153を装荷密封してなる。超ウラン核燃料集合体130は、ステンレス製のチャンネルボックス35の中に前記超ウラン元素核燃料棒131を正方格子状または3角格子状に配列し、配列された超ウラン元素核燃料棒131の1部を固体中性子吸収減速材棒161で置換する。【選択図】図4

34. 发明专利

JP2012083013A Active condenser 有权
标题翻译：主动冷凝器
公开(公告)号：JP2012083013A
公开(公告)日：2012-04-26
申请号：JP2010228761
申请日：2010-10-08
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： F28B9/00 , F28B1/02
摘要： PROBLEM TO BE SOLVED: To keep power-generation efficiency at high rate through a year, as the power generation efficiency is reduced in summer when electric power demand for air-conditioning increases because of rising of seawater temperature which is external atmosphere for a condenser.SOLUTION: The condenser is provided with a heat pump device to compensate increase of the seawater temperature. The invention is characterized by places arranged with a condenser and an evaporator.
摘要翻译：要解决的问题：为了在一年内保持发电效率高效，夏季电力需求由于海水温度升高而增加，发电效率因外部气氛升高一个冷凝器。
解决方案：冷凝器设有一个热泵装置，以补偿海水温度的升高。本发明的特征在于具有冷凝器和蒸发器的位置。版权所有（C）2012，JPO＆INPIT

35. 发明专利

JP2012006475A Engine with non-combustion type duct for electric airplane 有权
标题翻译：用于电动机的非燃烧式发动机
公开(公告)号：JP2012006475A
公开(公告)日：2012-01-12
申请号：JP2010143829
申请日：2010-06-24
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： B64D27/24
CPC分类号： Y02T50/62
摘要： PROBLEM TO BE SOLVED: To obtain a high speed flight engine which does not generate a carbon dioxide.SOLUTION: The engine capable of performing supersonic flight is provided by injecting high speed air from a Laval tube type nozzle by laying an electric fan in a Laval tube type casing.
摘要翻译：要解决的问题：获得不产生二氧化碳的高速飞行发动机。解决方案：能够进行超音速飞行的发动机通过在拉瓦尔管式外壳中放置电动风扇从拉瓦尔管式喷嘴喷射高速空气来提供。版权所有（C）2012，JPO＆INPIT

36. 发明专利

JP2010276564A 920k superheated steam boiling water reactor 审中-公开
标题翻译： 920K超级蒸汽锅炉水反应釜
公开(公告)号：JP2010276564A
公开(公告)日：2010-12-09
申请号：JP2009131761
申请日：2009-06-01
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C3/07 , G21C1/08 , G21C3/28 , G21C3/324 , G21C5/00 , G21C15/02 , G21D7/04
CPC分类号： Y02E30/31
摘要： PROBLEM TO BE SOLVED: To improve power generation by generating superheated steam by improving to some extent a nuclear fuel assembly and a shroud inside of a BWR (boiling water reactor).
SOLUTION: An upper structure material of a current nuclear fuel assembly is formed of stainless steel. An upper nuclear fuel pellet is thinned. A nuclear fuel pellet of a structure material connection part is long and thin. Superheated steam in the shroud is discharged from a nozzle into a mixture superheated steam pipe (1013), and thereby saturated steam in an upper part of a pressure vessel is sucked into the mixture superheated steam pipe (1013).
COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：通过在一定程度上改进BWR（沸水反应堆）内的核燃料组件和护罩来产生过热蒸汽来改善发电。解决方案：目前核燃料组件的上部结构材料由不锈钢形成。上部核燃料颗粒变薄。结构材料连接部件的核燃料芯片长而薄。护罩中的过热蒸汽从喷嘴排出到混合过热蒸汽管道（1013）中，由此将压力容器上部的饱和蒸汽吸入混合物过热蒸汽管道（1013）。版权所有（C）2011，JPO＆INPIT

37. 发明专利

JP2010164391A Nuclear power plant following daily load 有权
标题翻译：核电厂随着日常装载
公开(公告)号：JP2010164391A
公开(公告)日：2010-07-29
申请号：JP2009006239
申请日：2009-01-15
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21D3/00 , G21C7/28 , H02J3/32 , H02J3/46
CPC分类号： Y02E30/31 , Y02E30/39 , Y02E70/30
摘要： PROBLEM TO BE SOLVED: To cope with daily load changes in electric power demand by means of a nuclear power plant. SOLUTION: With an AC-to-DC converter and a large-sized storage battery introduced into a power line installation of a nuclear power plant, a control panel (10) and charging/discharging of the storage battery are used to cope with daily load changes while keeping reactor output constant. COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：通过核电厂应对日常负荷变化的电力需求。
解决方案：将AC-DC转换器和大型蓄电池引入核电站的电力线安装中，使用控制面板（10）和蓄电池的充放电来应对日常负载变化，同时保持反应堆输出不变。版权所有（C）2010，JPO＆INPIT

38. 发明专利

JP2008151625A Control rod of self-propelled type 有权
标题翻译：自蔓延型控制杆
公开(公告)号：JP2008151625A
公开(公告)日：2008-07-03
申请号：JP2006339375
申请日：2006-12-18
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C7/12 , G21C7/10 , G21C7/103 , G21C7/113 , G21C7/16
CPC分类号： Y02E30/39
摘要： PROBLEM TO BE SOLVED: To reduce construction costs and decrease power generation costs by shortening the lower parts of reactor structural materials though they are required to be about three times as long as nuclear fuel assemblies because they need a space for accommodating control rods below a core, further below which a space for a control rod drive mechanism is required. SOLUTION: A control rod 400 of a self-propelled type consists of support rods 420 made of titanium alloy or stainless steel incorporating a driving part, a propelling part, a fixing part and a receiver 440 and battery-cum-control-rod-blades 410 which incorporate as a power source silver-cadmium batteries functioning also as a neutron absorber. The control rod 400 can move vertically by driving a screw 412 coupled directly to a drive motor 411 by the receiver 440 which receives signals from outside with the silver-cadmium batteries, sucking water from a tapered water inlet 419 and spouting the water from a fountain nozzle 413 and can stay in a fixed position for a long period owing to a round-bar notch 424. COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：通过缩短反应堆结构材料的下部来减少建造成本并降低发电成本，尽管它们需要约为核燃料组件的三倍，因为它们需要用于容纳控制棒的空间在芯之下，进一步下方需要用于控制杆驱动机构的空间。解决方案：自走式控制杆400由钛合金或不锈钢制成的支撑杆420组成，该支撑杆420包括驱动部件，推进部件，固定部件和接收器440以及电池控制 - 其结合作为还用作中子吸收体的功率源银镉电池的棒片410。控制棒400可以通过驱动由接收器440直接耦合到驱动马达411的螺钉412而移动，该接收器440用银镉电池从外部接收信号，从锥形入口419吸入水并从喷嘴喷出水喷嘴413，并且由于圆棒凹口424可以长时间保持在固定位置。版权所有（C）2008，JPO＆INPIT

39. 发明专利

JP2006300849A Abwr reactor core with high conversion ratio capable of being converted into breeder reactor 有权
标题翻译：具有转换成BREEDER反应器的具有高转换比率的ABWR反应器芯
公开(公告)号：JP2006300849A
公开(公告)日：2006-11-02
申请号：JP2005125862
申请日：2005-04-25
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C3/328 , G21C3/62 , G21C5/00
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To provide an ABWR reactor core with a high conversion ratio capable of being converted into a breeder reactor requiring low reprocessing costs without need of any structural change other than change of nuclear fuel assemblies and control rods.
SOLUTION: Dense compensated nuclear fuel assemblies 130 each having a weight and a heat removal area in the allowance range of a nuclear fuel assembly loaded in a currently operated ABWR are installed with a nuclear fuel assembly pitch of 15.4 cm, and a row of Zircaloy-made hollow tubes 200 and a row of extension Zircaloy hollow tubes 300 extended above a control rod are disposed in a leak water passage.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供具有高转化率的ABWR反应堆堆芯，其能够转化为需要低后处理成本的增殖反应器，而不需要除了核燃料组件和控制棒的改变之外的任何结构变化。解决方案：在负载在当前操作的ABWR中的核燃料组件的容许范围内具有重量和散热面积的密集补偿的核燃料组件130安装有15.4cm的核燃料组件间距和一排的Zircaloy制造的中空管200和在控制杆上方延伸的一排延伸Zircaloy中空管300设置在泄漏水通道中。版权所有（C）2007，JPO＆INPIT

40. 发明专利

JP2006145414A Spacerless nuclear fuel assembly 审中-公开
标题翻译：无油核燃料总成
公开(公告)号：JP2006145414A
公开(公告)日：2006-06-08
申请号：JP2004337010
申请日：2004-11-22
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C3/30
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a spacerless nuclear fuel assembly capable of maintaining a water film on the surface of a nuclear fuel rod (31) to avoid a disturbance in removal of heat, having decreased flow resistance to avoid rapid drop in flow rate in case of a failure of a circulation pump and alleviating damage of the fuel rod (31) due to insufficient removal of heat from the nuclear fuel rod (31).
SOLUTION: A hollow plate (235) and a free bottom-side connection plate (133) are employed, so that the spacers (34) are removed. A new coolant passage (151) is narrower than a conventional coolant passage (51) so that the region of water, which is a moderator, is reduced to hardly cause the speed of neutrons to drop so that plutonium can be efficiently burnt to become extinct.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供一种能够在核燃料棒（31）的表面上保持水膜的无间隔型核燃料组件，以避免热去除干扰，具有降低的流动阻力以避免快速下降在循环泵故障的情况下，由于不能从核燃料棒（31）中除去热量而减轻燃料棒（31）的损坏的情况下的流量。解决方案：采用中空板（235）和自由底侧连接板（133），从而移除间隔件（34）。新的冷却剂通道（151）比常规冷却剂通道（51）窄，使得作为调节剂的水的区域被减少，几乎不会使中子的速度下降，使得钚能够被有效地燃烧以消失。版权所有（C）2006，JPO＆NCIPI

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