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21. 发明专利

JP2014206399A 放射能汚染水貯蔵システム审中-公开
标题翻译：辐射污染水储存系统
公开(公告)号：JP2014206399A
公开(公告)日：2014-10-30
申请号：JP2013082749
申请日：2013-04-11
申请人：白川利久 , Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21F9/22
摘要：【課題】大量の放射能汚染水を早急に廉価に貯蔵保管したい。【解決手段】水密性能が弱いプールの中に多数個の貯水タンクを正方格子状に敷設し、貯水タンクの中に放射能汚染水を保管貯蔵する。貯水タンクからの放射能汚染水漏洩を監視する。【選択図】図1
摘要翻译：要解决的问题：以低价格尽可能快地储存大量的辐射污染的水。解决方案：许多储罐在水中具有低水密性能的池中以方形格子形式放置，以将辐射污染的水储存在储罐。进行监测是为了从储罐泄漏受辐射污染的水。

22. 发明专利

JP2011117855A Heat transfer coefficient and temperature of nuclear fuel rod in boiling water reactor 有权
标题翻译：锅炉水反应堆核燃料热交换系数和温度
公开(公告)号：JP2011117855A
公开(公告)日：2011-06-16
申请号：JP2009276095
申请日：2009-12-04
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C17/00 , G21C17/06
摘要： PROBLEM TO BE SOLVED: To raise void fraction in a core while maintaining safety in order to efficiently burn plutonium in a boiling water reactor. SOLUTION: The higher void fraction easily causes dryout. Even if the dryout occurs, temperatures of nuclear fuel rods are analyzed, indicated and monitored so as to maintain the integrity of them. In order to calculate surface temperatures of cladding tubes in dryout states, formulae for deriving new heat transfer coefficients and cladding tube calculation formulae are shown. COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：为了在保持安全性的同时提高芯中的空隙率，以便有效地在沸水反应器中焚烧钚。
解决方案：较高的空隙率容易引起干燥。即使发生干涸，也会分析，指示和监测核燃料棒的温度，以保持其完整性。为了计算干燥状态下包层管的表面温度，示出了用于导出新的传热系数和包层管计算公式的公式。版权所有（C）2011，JPO＆INPIT

23. 发明专利

JP2011060477A SUBCRITICAL AMOUNT RECESSIVE PLUTONIUM HEATING SOURCE NaS MODULE STORAGE BATTERY POWER SOURCE DRIVING ELECTRIC VEHICLE 审中-公开
标题翻译：亚临时收货台式加热炉NaS模块存储电池电源驱动电动车
公开(公告)号：JP2011060477A
公开(公告)日：2011-03-24
申请号：JP2009206679
申请日：2009-09-08
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： H01M2/10 , B60L11/18 , G21D9/00 , G21H3/00 , H01M10/39 , H01M10/44 , H01M10/60 , H01M10/615 , H01M10/625 , H01M10/6556 , H01M10/6561 , H01M10/6567 , H01M10/6595
CPC分类号： Y02T10/7016
摘要： PROBLEM TO BE SOLVED: To solve a problem as to what should be used as a clean high temperature heat source to keep an operating temperature high and what structure should be used for a storage battery for an electric vehicle with a drastic load variation, though an NaS storage battery exhibits a high performance.
SOLUTION: As the high temperature heat source of the NaS storage battery, a subcritical amount of recessive Pu is used. A main travel storage battery of the electric vehicle depends on discharge from the NaS storage battery. The charging and discharging with the load variation (further discharging during acceleration, charging by recovery power due to an electric brake during deceleration) depend on a normal temperature-operating auxiliary storage battery such as a lead-acid battery with a long cycle life and being inexpensive.
COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：为了解决作为干净的高温热源应该使用什么来保持工作温度高的问题和用于具有剧烈负载变化的电动车辆的蓄电池的结构尽管NaS蓄电池表现出很高的性能。解决方案：作为NaS蓄电池的高温热源，使用亚临界量的隐性Pu。电动车辆的主要行驶蓄电池取决于NaS蓄电池的放电。具有负载变化的充放电（加速期间的进一步放电，由减速时的电动制动引起的恢复功率的充电）取决于常温操作辅助蓄电池，例如长循环寿命的铅酸蓄电池，便宜。版权所有（C）2011，JPO＆INPIT

24. 发明专利

JP2010025781A γ-RAY DECAY ACCELERATOR OF NEUTRON-IRRADIATED HAFNIUM CONTROL ROD 审中-公开
标题翻译：中子辐射高压控制线的γ射线衰减加速器
公开(公告)号：JP2010025781A
公开(公告)日：2010-02-04
申请号：JP2008188104
申请日：2008-07-22
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21F9/00 , G21H1/06
摘要： PROBLEM TO BE SOLVED: To reduce cost required for the long-term storage of activated hafnium generated from a control rod in a nuclear reactor.
SOLUTION: An isomer being Hf 178m2 is generated from Hf subjected to neutron irradiation. The decay of Hf 178m2 is induced by decelerating the γ-ray radiated from the isomer to make the γ-ray collide with Hf 178m2, and thereby progressed earlier than spontaneous decay.
COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：降低长期储存核反应堆中控制杆产生的活性铪所需的成本。解决方案：由Hf进行中子照射产生Hf为178m 2的异构体。通过使从异构体辐射的γ射线减速使Hf×178m 2的衰变引起γ射线与Hf×178m 2碰撞，从而比自发衰变更早进行。版权所有（C）2010，JPO＆INPIT

25. 发明专利

JP2009222617A Bleedable nuclear fuel assembly using non-plutonium-based nuclear fuel, and core of light water-cooled bwr 有权
标题翻译：使用非基于钚的核燃料的可燃核燃料组件和轻水冷却BWR的核心
公开(公告)号：JP2009222617A
公开(公告)日：2009-10-01
申请号：JP2008068784
申请日：2008-03-18
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C3/62 , G21C3/30 , G21C3/328 , G21C5/00 , G21C7/10 , G21C7/113
CPC分类号： Y02E30/31 , Y02E30/38 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To provide a reactor of low Pu generation by improving the core of a BWR under operation.
SOLUTION: Pellets having higher degree of U233 enrichment is filled into the upper part of a TMOX obtained by easy reprocessing, and pellets where enriched uranium is added to Th are deposited and filled in the bottom part, and a thorium-based nuclear fuel assembly 130, where many thorium-based nuclear fuel rods 131 are arranged in a square form and a boronized titanium control rod 101 are loaded in the core of the BWR currently in operation.
COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：通过改善操作中的BWR的核心来提供低Pu代的反应堆。解决方案：将具有较高程度的U233富集的颗粒填充到通过易于再处理获得的TMOX的上部，并且将沉积有浓缩铀的颗粒沉积并填充到底部，并将钍基核燃料组件130，其中许多钍基核燃料棒131以正方形排列，并且硼化钛控制棒101装载在当前操作的BWR的核心中。版权所有（C）2010，JPO＆INPIT

26. 发明专利

JP2009115571A Renewed abwr adapted to combined power generation 审中-公开
标题翻译：再生ABWR适用于组合发电
公开(公告)号：JP2009115571A
公开(公告)日：2009-05-28
申请号：JP2007288046
申请日：2007-11-06
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C5/22 , G21C1/08 , G21C15/02 , G21D7/04
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To improve power generation efficiency by renewing a current advanced boiling water reactor (ABWR) by modifying it not on a large scale.
SOLUTION: Further power generation through the agency of a steam turbine (41) with high-pressure saturated steam (23) produced by cooling high-pressure superheated steam (24) during a power generation process in a newly laid electrothermal semiconductor (100) after generating power with the electrothermal semiconductor (100) by producing the high-pressure superheated steam (24) through some modification of a licensed ABWR leads to combined power generation to improve the power generation efficiency.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：通过更新现有的先进沸水反应堆（ABWR），通过不大规模改造来提高发电效率。解决方案：通过在新生电热半导体的发电过程中通过冷却高压过热蒸汽（24）产生的具有高压饱和蒸汽（23）的蒸汽轮机（41）的进一步发电（ 100）通过利用许可的ABWR的一些修改来生产高压过热蒸汽（24），通过电热半导体（100）发电来实现组合发电以提高发电效率。版权所有（C）2009，JPO＆INPIT

27. 发明专利

JP2009036604A Spacer in nuclear fuel assembly for nuclear reactor 有权
标题翻译：核反应堆核燃料组件中的间隙
公开(公告)号：JP2009036604A
公开(公告)日：2009-02-19
申请号：JP2007200384
申请日：2007-08-01
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C3/34 , G21C3/332
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To reduce the proportion of coolant within limits allowing heat removal in order to efficiently cause plutonium to fission.
SOLUTION: Springy hollow cylinders 543 are disposed in a large opening part surrounded by nuclear fuel rods 31 to maintain distances between the nuclear fuel rods 31 while preventing water film deposited on the nuclear fuel rods 31 or a coolant flow from being disturbed.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：为了有效地使钚发生裂变，将冷却剂的比例降低到允许散热的范围内。解决方案：弹性中空圆筒543设置在由核燃料棒31围绕的大开口部分中，以保持核燃料棒31之间的距离，同时防止沉积在核燃料棒31上的水膜或冷却剂流动受到干扰。版权所有（C）2009，JPO＆INPIT

28. 发明专利

JP2008309748A Repairing of bwr or abwr 有权
标题翻译：修理BWR或ABWR
公开(公告)号：JP2008309748A
公开(公告)日：2008-12-25
申请号：JP2007160243
申请日：2007-06-18
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C17/00 , G21C7/10 , G21C7/14
CPC分类号： Y02E30/31 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To easily inspect an existing light-water reactor without changing it greatly. SOLUTION: An electric wire 21 for power supplies and an electric wire 22 for signals connected to dynamic equipment laid in an already approved ABWR and a measuring device are removed. A leading edge 400 is led from the dynamic equipment or the measuring device, a radio apparatus 32 incorporating a battery having a battery 31 and an antenna 33 is connected, and the reactor 1 is controlled remotely via a radio repeater 34. COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：轻松检查现有的轻水反应器，而不会大大改变。解决方案：去除了用于电源的电线21和用于连接到已经批准的ABWR中的动态设备的信号的电线22和测量装置。引导边缘400从动态设备或测量装置引出，结合具有电池31和天线33的电池的无线电设备32连接，并且电抗器1经由无线电中继器34远程控制。（C）2009，JPO＆INPIT

29. 发明专利

JP2006194588A Atomic nuclear fuel assembly for short half-life nuclide combustion 审中-公开
标题翻译：原子核燃料组件，用于短寿命核素燃烧
公开(公告)号：JP2006194588A
公开(公告)日：2006-07-27
申请号：JP2005003290
申请日：2005-01-11
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C3/30 , G21C3/18 , G21C3/28 , G21C3/328 , G21C3/33 , G21C3/62
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To enhance combustion efficiency by increasing the percentage of short half-life nuclear fissile materials which undergo fission before they decay by themselves.
SOLUTION: This atomic nuclear fuel assembly of high power density is made up of a multitude of arranged thin and short nuclear fuel rods 131 with reflectors each being one tenth in length of conventional ones. This fuel assembly is used to perform combustion at a power density about ten times that of a conventional boiling water reactor while maintaining a maximum linear power density.
COPYRIGHT: (C)2006,JPO&NCIPI

30. 发明专利

JP2005062059A Boiling water type nuclear power plant 审中-公开
标题翻译：锅炉水型核电厂
公开(公告)号：JP2005062059A
公开(公告)日：2005-03-10
申请号：JP2003294352
申请日：2003-08-18
申请人： Toshihisa Shirakawa , 白川利久
发明人： SHIRAKAWA TOSHIHISA
IPC分类号： G21C9/016 , G21C9/004 , G21C13/00 , G21C15/18
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a boiling water type nuclear power plant which reduces partition walls constituting each building, and improves economy and safety by making a large space around a reactor pressure vessel (1).
SOLUTION: By combining a reactor building 18 and a turbine building 30, a reactor turbine containment vessel 117 is made and the reactor pressure vessel 1 and ECCS and a turbine equipment are contained together. A rigid sealed large space is made with a cylindrical large containment vessel wall 116, an openable containment vessel seal lid 201 and an openable containment structure lid 202. The openable containment vessel seal lid 201 and an openable containment structure lid 202 are fastened with bolts 204 by an openable containment vessel strap 203 to the large containment vessel wall 116 to be opened.
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：提供一种沸水型核电站，其减少构成每个建筑物的隔壁，并且通过在反应堆压力容器（1）周围形成大的空间来提高经济性和安全性。解决方案：通过组合反应堆建筑物18和涡轮机建筑物30，制成反应堆涡轮机容纳容器117，反应堆压力容器1和ECCS以及涡轮设备被包含在一起。刚性密封的大空间由圆柱形的大型容纳容器壁116，可打开的容纳密封盖201和可打开的容纳结构盖202制成。可开启的容纳密封盖201和可打开的容纳结构盖202用螺栓204 通过可打开的容纳带203连接到要打开的大容器壁壁116。版权所有（C）2005，JPO＆NCIPI

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