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1. 发明专利

JP2005274337A Nuclear reactor 审中-公开
标题翻译：核反应堆
公开(公告)号：JP2005274337A
公开(公告)日：2005-10-06
申请号：JP2004087719
申请日：2004-03-24
申请人： Hitachi Ltd , Mitsubishi Heavy Ind Ltd , 三菱重工業株式会社 , 株式会社日立製作所
发明人： HIBI HIROMOTO , TAKIMOTO HIROKI , OYAMA TAKESHI , MORIYA KIMIAKI , MATSUURA MASAYOSHI , CHAGI MASAO , HINO TETSUSHI
IPC分类号： G21C9/004 , G21C1/08 , G21C15/18
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear reactor dispensing with ECCS for injecting a coolant into a high pressure system.
SOLUTION: Each set of six cassettes 2 having respectively a core 23 inside is arranged respectively on two concentric circles, and three steam generators 3 communicated with some cassette 2 are provided over the cassettes 2 and connected to the cassettes 2 through a riser pipe 5 and a condensate pipe 6. The heat generation rate during the 100% operation of the core in the cassette 2 is determined in consideration of a relation with a heat discharge by self-cooling of a containment vessel 1, and the cassettes 2, the riser pipe 5, the steam generators 3 and the condensate pipe 6 are arranged together within the containment vessel 1 whose inside has an atmospheric pressure. When LOCA occurs, a cap 20 is fused, and thereby water 16 in a water shielding tank 11 flows into a space 18 around the cassettes 2 through a communicating pipe 19.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供一个分配ECCS的核反应堆将冷却剂注入高压系统。
解决方案：分别具有内部的芯子23的每组六个盒2分别布置在两个同心圆上，并且与盒2连通的三个蒸汽发生器3设置在盒2上并且通过提升板连接到盒2 管5和冷凝管6.在盒2中的芯的100％操作期间的发热率是考虑到与安全壳1的自冷却的热放电的关系来确定的，升降管5，蒸汽发生器3和冷凝管6一起设置在内部具有大气压的安全壳1内。当LOCA发生时，帽20被熔化，从而水屏蔽罐11中的水16通过连通管19流入盒2周围的空间18中。（C）2006，JPO和NCIPI

2. 发明专利

JP2007101196A Spent fuel storage container 有权
标题翻译：燃油储存容器
公开(公告)号：JP2007101196A
公开(公告)日：2007-04-19
申请号：JP2005287383
申请日：2005-09-30
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： KUMAGAI NAOKI , HINO TETSUSHI , KAMOSHITA MAMORU , FUJIMURA KOJI
IPC分类号： G21F5/012 , G21C19/32 , G21F5/008 , G21F9/36
摘要： PROBLEM TO BE SOLVED: To enhance the subcriticality, heat removal properties, and shielding performance, of a spent fuel storage container when storing therein spent fuel assemblies without any channel box.
SOLUTION: The spent fuel storage container includes a bottomed cylindrical trunk part 10 provided with a plurality of section parts for therein storing the spent fuel assemblies with the assemblies sectioned by ones, and is equipped with regulation members 30 disposed detachably in the section parts 22 for regulating the positions of the fuel assemblies 40 in the section parts 22. The regulation members 30 are each disposed along at least one inside wall in a section part 22. The position of each spent fuel assembly 40 in a section part 22 is brought close to an an inside wall on the opposite side of the inside wall on the side where a regulation member is disposed.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：待解决的问题：为了提高废燃料储存容器在储存没有任何通道箱的废燃料组件时的亚临界性，除热性能和屏蔽性能。解决方案：废燃料储存容器包括一个有底的圆柱形主体部分10，该底部圆柱形主体部分10设置有多个部分，用于在其中存储由燃料组件分组的废燃料组件，并且装有可拆卸地设置在该部分中的调节部件30 用于调节部分22中的燃料组件40的位置的部分22.调节构件30各自沿截面部分22中的至少一个内壁设置。每个废燃料组件40在部分部分22中的位置是靠近位于配置有调节构件的一侧的内壁的相对侧上的内壁。版权所有（C）2007，JPO＆INPIT

3. 发明专利

JP2006200939A Spent fuel container basket and spent fuel storage vessel 审中-公开
标题翻译：燃油集装箱和燃油储存船
公开(公告)号：JP2006200939A
公开(公告)日：2006-08-03
申请号：JP2005010645
申请日：2005-01-18
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： ISHII YOSHIHIKO , FUJIMURA KOJI , ISHII KAZUYA , KUMAGAI NAOKI , HAYASHI MAKOTO , UENO MANABU , HINO TETSUSHI
IPC分类号： G21F5/012 , G21C19/32 , G21F9/36
摘要： PROBLEM TO BE SOLVED: To provide a spent fuel container basket which has grid type compartments, utilizes a box of cake structure using continuous members reaching the both ends in the radial direction of the container basket, maintains the function of ensuring strength and a function of maintaining subcriticality and a heat conduction function and suppresses the increase of weight and the outer diameter of the container basket.
SOLUTION: The spent fuel container basket forming a fuel assembly containing space 10 piles in the axial direction of a fuel assembly, crossing unit plates of a plate member 4a which is formed a plurality of notches 41a, 41a... on both of long sides along the longitudinal direction, has penetration holes 42a, 42a in the longitudinal direction, bearing a strength ensuring function and subcriticality maintaining function and a part of heat conduction function, and a plate 6a having a plurality of notches 61a, 61a... on both of long sides along the longitudinal direction and bearing heat conduction function.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：为了提供一种具有栅格型隔室的废燃料容器篮，利用连续构件在容器篮的径向方向上到达两端的饼块结构，保持了强度的功能，维持亚临界和热传导功能的功能，并且抑制容器篮的重量和外径的增加。解决方案：在燃料组件的轴向方向上形成燃料组件的空燃料容器筐形成多个凹口41a，41a ...的板构件4a的单元板，沿长度方向的长边沿长度方向具有贯通孔42a，42a，具有确保功能和亚临界保持功能和一部分导热功能的强度，以及具有多个切口61a，61a的板6a。在长方向的长边两侧均承受导热功能。版权所有（C）2006，JPO＆NCIPI

4. 发明专利

JP2005274336A Nuclear connection parting type shut-down device and nuclear reactor equipped therewith 审中-公开
标题翻译：核连接器类型关闭装置及其装备的核反应堆
公开(公告)号：JP2005274336A
公开(公告)日：2005-10-06
申请号：JP2004087718
申请日：2004-03-24
申请人： Hitachi Ltd , Mitsubishi Heavy Ind Ltd , 三菱重工業株式会社 , 株式会社日立製作所
发明人： HIBI HIROMOTO , TAKIMOTO HIROKI , OYAMA TAKESHI , MORIYA KIMIAKI , MATSUURA MASAYOSHI , CHAGI MASAO , HINO TETSUSHI
IPC分类号： G21C1/08 , G21C7/10
CPC分类号： Y02E30/39
摘要： PROBLEM TO BE SOLVED: To provide a nuclear connection parting type shut-down device capable of suppressing increase of construction cost by reducing one-rod stuck reactivity allowance at the reactor shut-down, and a nuclear reactor equipped therewith.
SOLUTION: This nuclear connection parting type shut-down device is a control body for controlling a reactor output, arranged insertably between containers by a lifting means disposed on a top part or a bottom part of a multi-type nuclear reactor equipped with the plurality of containers having respectively a built-in core, having a neutron absorber filled therein, and having the top end part and the bottom end part sealed respectively. The control body is constituted so as to enclose the side face of a cassette when inserted between each cassette.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：解决的问题：提供一种能够通过减少反应堆停机时的单杆卡住反应性容限而抑制建筑成本的增加的核连接分型式停机装置，以及配备有该反应堆的核反应堆。解决方案：该核连接分型式关闭装置是用于控制反应器输出的控制体，其通过设置在装备有多级核反应堆的多型核反应堆的顶部或底部的提升装置可插入容器之间所述多个容器分别具有内置的芯，其中填充有中子吸收体，并且分别具有顶端部分和底端部分。控制体被构造为当插入在每个盒之间时包围盒的侧面。版权所有（C）2006，JPO＆NCIPI

5. 发明专利

JP2007232547A Method and device for calculating reactor core performance in natural circulation type boiling water reactor 有权
标题翻译：计算自然循环型锅炉水反应器中反应器核心性能的方法和装置
公开(公告)号：JP2007232547A
公开(公告)日：2007-09-13
申请号：JP2006054094
申请日：2006-02-28
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： HINO TETSUSHI , CHAGI MASAO , AOYAMA TADAO , ISHII KAZUYA
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To provide a method and device for calculating reactor core performance in a natural circulation type boiling water reactor capable of accurately calculating the power of the fuel assembly in the core. SOLUTION: This method includes a thermal hydraulic calculating process of calculating the flow rate distribution of a plurality of fuel assemblies corresponding to respective grid channels 11a of a chimney 11, using core state data including reactor pressure and control rod insertion positions, plant data related to the reactor power of the feed water flow rate and feed water temperature, data of nuclear constant and thermal hydraulic constant prepared for each type of fuel assemblies 21, and hydraulic constant data of the grid channel, and of calculating the void fraction in the grid channel with a predetermined calculation formula based on the coolant flow rate from the fuel assemblies to the grid channel. Based on the calculated void fraction in the grid channel, three-dimensional power distribution calculation in the core 7 and the coolant flow rate distribution calculation to each fuel assembly are repeated. COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种能够精确计算核心中的燃料组件的功率的自然循环型沸水反应堆中的反应堆堆芯性能的计算方法和装置。解决方案：该方法包括使用包括反应堆压力和控制棒插入位置的核心状态数据来计算与烟囱11的各个电网通道11a对应的多个燃料组件的流量分布的热液压计算过程，与供水流量和给水温度的反应堆功率相关的数据，为每种燃料组件21准备的核常数和热液压常数的数据，以及电网通道的液压常数数据，以及计算空气分数基于从燃料组件到电网通道的冷却剂流量的具有预定计算公式的电网通道。基于计算的网格通道中的空隙率，重复核心7中的三维功率分布计算和对每个燃料组件的冷却剂流量分布计算。版权所有（C）2007，JPO＆INPIT

6. 发明专利

JP2005274335A Multi-type nuclear reactor 审中-公开
标题翻译：多型核反应堆
公开(公告)号：JP2005274335A
公开(公告)日：2005-10-06
申请号：JP2004087717
申请日：2004-03-24
申请人： Hitachi Ltd , Mitsubishi Heavy Ind Ltd , 三菱重工業株式会社 , 株式会社日立製作所
发明人： HIBI HIROMOTO , TAKIMOTO HIROKI , OYAMA TAKESHI , MORIYA KIMIAKI , MATSUURA MASAYOSHI , CHAGI MASAO , HINO TETSUSHI
IPC分类号： G21C1/08 , G21D9/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a multi-type nuclear reactor capable of facilitating arrangement of piping or a support structure, while keeping performance as a package type nuclear reactor. SOLUTION: This multi-type nuclear reactor is equipped with a cylindrical graphite reflector 12A having a circular or regularly-polygonal section, and a plurality of cassette 14 arranged inside a cylindrical space specified by the inner surface of the graphite reflector and having a built-in core respectively. The reactor has a constitution having a space as large as one cylindrical cassette having the center axis agreeing with the center axis of the cylindrical space. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供能够促进管道或支撑结构的布置的多型核反应堆，同时保持作为包装型核反应堆的性能。解决方案：这种多型核反应堆配备有圆形或规则多边形部分的圆柱形石墨反射器12A和多个盒14，其布置在由石墨反射体的内表面指定的圆柱形空间内，并具有内置内核。反应器具有一个具有与一个圆柱形盒一样大的空间的构造，其中心轴与圆柱形空间的中心轴线一致。版权所有（C）2006，JPO＆NCIPI

7. 发明专利

JP2003344574A Natural circulation nuclear reactor system and operation method therefor 审中-公开
标题翻译：自然循环核反应堆系统及其运行方法
公开(公告)号：JP2003344574A
公开(公告)日：2003-12-03
申请号：JP2002150152
申请日：2002-05-24
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： ISHII YOSHIHIKO , AOYAMA TADAO , HINO TETSUSHI , MORIYA KIMIAKI
IPC分类号： G21C1/08 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a natural circulation nuclear reactor system having a sufficiently enhanced profitability, and an operation method therefor.
SOLUTION: The natural circulation nuclear reactor system comprises a natural circulation nuclear reactor, a main steam pipe 9, a supply water pipe 10, and a flow regulating valve 15. The natural circulation nuclear reactor comprises a reactor core 1 with a fuel assembly 23 having a same geometric shape as that of a fuel assembly used in a forced circulation boiling water reactor loaded therein, a reactor pressure vessel 5 accommodating the reactor core 1, and a control rod 7 penetrating the reactor pressure vessel 5 and removably installed in the reactor core 1 for controlling an output of the reactor core 1. The main steam pipe 9 is connected to the reactor pressure vessel 5 for guiding steam from the core 1 to a turbine 8. The supply water pipe 10 condenses the steam which has been used for driving the turbine 8 and recirculates condensate to the reactor pressure vessel 5. The flow regulating valve 15 regulates a reactor water level H in the reactor pressure vessel 5 by controlling a flow rate of the condensate.
COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：提供具有充分提高的盈利能力的自然循环核反应堆系统及其操作方法。解决方案：天然循环核反应堆系统包括自然循环核反应堆，主蒸汽管9，供水管10和流量调节阀15.自然循环核反应堆包括具有燃料的反应堆堆芯1 组件23具有与在其中装载的强制循环沸水反应堆中使用的燃料组件的几何形状相同的几何形状;容纳反应堆堆芯1的反应堆压力容器5;以及穿过反应堆压力容器5并可移除地安装在用于控制反应堆芯1的输出的反应堆堆芯1.主蒸汽管9连接到反应堆压力容器5，用于将来自核心1的蒸汽引导到涡轮8.供水管10将已经用于驱动涡轮8并将冷凝物再循环到反应堆压力容器5中。流量调节阀15通过控制器调节反应堆压力容器5中的反应器水位H g冷凝水的流量。版权所有（C）2004，JPO

8. 发明专利

JP2008032696A Operation method of reactor, and nuclear power plant 有权
标题翻译：反应堆和核电厂的运行方法
公开(公告)号：JP2008032696A
公开(公告)日：2008-02-14
申请号：JP2007168985
申请日：2007-06-27
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： CHAGI MASAO , AOYAMA TADAO , ISHII KAZUYA , HINO TETSUSHI
IPC分类号： G21D3/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear power plant capable of improving the operation rate.
SOLUTION: A nuclear power plant comprises a water supply temperature control device 27; a heat balance calculating device 28; and a core thermal device 35 for limiting and monitoring. The heat balance calculating device 28 calculates a water supply temperature T. Water supply temperature is used as a set value of water supply temperature when MCPR(T) corresponding to the water supply temperature T is higher than MCPR(0) obtained by the core thermal device 35 for limiting and monitoring. The water supply temperature control device 27 controls an opening of a steam flow rate adjusting valve 17 for a measured value of the water supply temperature to be the set value of water supply temperature T based on the water supply temperature T and a thermometer 25. A temperature of cooling water supplied to a core 11 is retained at a temperature close to an upper limit which does not generate cavitation throughout a reactor cycle by controlling the water supply temperature.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：提供能够提高运行率的核电站。解决方案：核电站包括供水温度控制装置27; 热平衡计算装置28; 以及用于限制和监视的核心热设备35。热量平衡计算装置28计算供水温度T.当供水温度T对应的MCPR（T）高于通过核心热量获得的MCPR（0）时，供水温度被用作供水温度的设定值装置35用于限制和监测。供水温度控制装置27基于供水温度T和温度计25，将供水温度的测定值的蒸汽流量调节阀17的开度控制为供水温度T的设定值。供给到芯11的冷却水的温度通过控制供水温度而保持在接近整个反应器循环的空穴接近上限的温度。版权所有（C）2008，JPO＆INPIT

9. 发明专利

JP2007232505A Natural circulation type boiling water reactor 有权
标题翻译：自然循环型锅炉水反应堆
公开(公告)号：JP2007232505A
公开(公告)日：2007-09-13
申请号：JP2006053088
申请日：2006-02-28
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： ISHII KAZUYA , AOYAMA TADAO , HINO TETSUSHI
IPC分类号： G21C15/02
CPC分类号： G21C1/084 , G21C7/005 , G21Y2002/201 , G21Y2004/30 , G21Y2004/403 , Y02E30/31 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To provide a natural circulation boiling water reactor capable of flattening a core output distribution, and increasing a thermal margin.
SOLUTION: This natural circulation type boiling water reactor has characteristics wherein, when dividing into three domains, namely, the outermost layer 1 of the core 7 named as an outermost layer domain 61, two or three layers provided inside the outermost layer domain 61 named as an outside domain 62, and the other part named as an inside domain 63, an orifice pressure loss coefficient of the outermost layer domain 61 is set to be maximum, and an orifice pressure loss coefficient of the outside domain 62 is set to be minimum, so that the flow rate of a coolant W per body of a fuel assembly 21 to the outermost layer domain 61 becomes minimum, and that the flow rate of the coolant W per body of the fuel assembly 21 to the outside domain 62 becomes maximum.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供能够使核心输出分布变平的自然循环沸水反应器，并增加热裕度。解决方案：该自然循环型沸水反应器具有以下特征：当被分为三个区域即核心7的最外层1称为最外层区域61时，在最外层区域内设置两层或三层 61被称为外部区域62，另一部分被称为内部区域63，最外层区域61的孔口压力损失系数被设定为最大，并且外部区域62的孔口压力损失系数被设定为最小，使得燃料组件21的每个主体到最外层区域61的冷却剂W的流量变得最小，并且燃料组件21的每个主体到外部区域62的冷却剂W的流量变为最大值。版权所有（C）2007，JPO＆INPIT

10. 发明专利

JP2007232500A Operation method of nuclear reactor and nuclear power plant 审中-公开
标题翻译：核反应堆和核电厂的运行方法
公开(公告)号：JP2007232500A
公开(公告)日：2007-09-13
申请号：JP2006053050
申请日：2006-02-28
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： CHAGI MASAO , AOYAMA TADAO , HINO TETSUSHI , ISHII KAZUYA
IPC分类号： G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide an operation method of a nuclear reactor and a nuclear power plant capable of increasing fuel economic efficiency even when an operational cycle is prolonged by increasing a thermal output of the nuclear power plant. SOLUTION: In performing an operation of the nuclear power plant in one operation cycle, when a flow rate of a coolant supplied to a reactor core of the nuclear reactor operated with the nuclear reactor output at a set output at the last period of the operation cycle increases, the temperature of the supply water to be supplied to the nuclear reactor is lowered. According to such an operation method, the fuel economic efficiency can be improved even when the operation cycle is prolonged by increasing the thermal output of the nuclear power plant. In particular, even when the reactor core flow rate is increased at the last period of the operation cycle, it is possible to prevent the temperature of the coolant at the inlet of the reactor core from being raised. Thus, a reactivity gain when the reactor core flow rate is increased at the last period of the operation cycle is increased more than that when the reactor core flow rate is merely increased. COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供即使当通过增加核电站的热输出延长运行周期时，能够提高燃料经济性的核反应堆和核电站的操作方法。解决方案：在一个操作循环中执行核电站的运行时，当供应给核反应堆的反应堆核心的冷却剂的流量在核反应堆运行时，输出在最后一个时期的设定输出操作循环增加，供给到核反应堆的供给水的温度降低。根据这种操作方法，即使通过增加核电站的热输出来延长运行周期，也可以提高燃料经济性。特别是即使在操作循环的最后期间反应堆堆芯流量增加，也可以防止反应堆堆芯入口处的冷却剂的温度升高。因此，当反应堆堆芯流量在操作循环的最后期间增加时的反应性增益比仅仅增加反应堆堆芯流量时的反应性增加更多。版权所有（C）2007，JPO＆INPIT

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