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1. 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

2. 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

3. 发明专利

JP2007232423A Natural circulation boiling water reactor 有权
标题翻译：自然循环锅炉水反应堆
公开(公告)号：JP2007232423A
公开(公告)日：2007-09-13
申请号：JP2006051513
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 , HINO TETSUSHI
IPC分类号： G21C15/26 , G21C15/02
CPC分类号： G21C1/084 , G21C15/26 , G21Y2002/201 , G21Y2002/204 , G21Y2004/302 , Y02E30/31
摘要： PROBLEM TO BE SOLVED: To provide a natural circulation boiling water reactor to which a thermal margin evaluation method for a core proven in a forced circulation boiling water reactor and having a high accuracy can be applied.
SOLUTION: The natural circulation boiling water reactor 1 comprises a core 7 loaded with a plurality of fuel assemblies 21 and a chimney 11 installed above the core 7 and having channel bulkheads 11b guiding a two-phase (gas-liquid) flow ascending from the core 7 to a plurality of vertical lattice channels 11a, and an equalizing space 35 not having the channel bulkhead 11b is provided below the chimney 11. Therefore, the distribution of the flow to the individual fuel assemblies 21 can be calculated by the calculation of the difference in pressure between the tip end and the bottom end of the core 7 without need of the void ratios of the individual lattice channels 11a.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种自然循环沸水反应器，可以应用在强制循环沸水反应器中证实的具有高精度的芯的热裕度评估方法。解决方案：自然循环沸水反应器1包括装载有多个燃料组件21的核心7和安装在核心7上方的烟囱11，并且具有引导两相（气液）流上升的通道隔板11b 从核心7到多个垂直格子通道11a，并且在烟囱11的下方设置不具有通道隔板11b的平衡空间353.因此，可以通过计算来计算流向单个燃料组件21的流量分布的磁芯7的顶端和底端之间的压力差，而不需要各个晶格通道11a的空隙率。版权所有（C）2007，JPO＆INPIT

4. 发明专利

JP2006125950A Feed water nozzle and reactor facility using feed water nozzle 有权
标题翻译：进料水喷嘴和反应器使用进水喷嘴
公开(公告)号：JP2006125950A
公开(公告)日：2006-05-18
申请号：JP2004313221
申请日：2004-10-28
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： SHIINA KOJI , AOYAMA TADAO , OTSUKA MASAYA , CHAGI MASAO , KITO KAZUAKI
IPC分类号： G21C13/032 , G21C15/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To ensure a structural integrity of a feed water nozzle by suppressing a temperature fluctuation in an annular flow path between a thermal sleeve and a feed water nozzle even for mixing core water and feed water with a large temperature difference at the feed water nozzle part in an operation method for removing heat by lowering feed water temperature without increasing steam flow generating from a reactor when a reactor core thermal power increases in a reactor power generation system and suppressing the occurrence of high cycle thermal fatigue caused by the temperature fluctuation due to thermal stratification.
SOLUTION: The feed water nozzle 13, attached to the reactor pressure vessel 1 of a nuclear power generation system and connected with the feed water system, forms a double tube structure having a thermal sleeve 14 inside the feed water nozzle 13. The relation between the gap δ of an annular flow path 16 formed between the outer surface of the thermal sleeve 14 and a feed water nozzle inner surface 13a and the inner diameter Di is δ/D
i ≤0.03.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：为了通过抑制热套筒和给水嘴之间的环形流动路径中的温度波动来确保给水喷嘴的结构完整性，即使用于混合芯水和具有较大温度差的给水在反应堆发电系统中，当反应堆堆芯火力增加并且抑制由于反应堆发电系统引起的高循环热疲劳的发生时，通过降低供水温度而不增加从反应器产生的蒸汽流来除热的操作方法由于热分层引起的温度波动。
解决方案：连接到核发电系统的反应堆压力容器1并与给水系统连接的给水喷嘴13形成在给水喷嘴13内部具有热套筒14的双管结构。形成在热套14的外表面和给水喷嘴内表面13a之间的环形流路16的间隙δ与内径Di之间的关系为δ/ D i ≤0.03。版权所有（C）2006，JPO＆NCIPI

5. 发明专利

JP2005201714A Boiling water reactor, fuel-supporting fixture, fuel assembly, and operation method of the boiling water reactor 审中-公开
标题翻译：锅炉水反应堆，燃油支撑装置，燃油组件及其操作方法
公开(公告)号：JP2005201714A
公开(公告)日：2005-07-28
申请号：JP2004006600
申请日：2004-01-14
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： CHAGI MASAO , AOYAMA TADAO , MORIWAKI MASANAO , HINO TETSUSHI
IPC分类号： G21C5/06 , G21C3/322 , G21C3/33 , G21C15/02
CPC分类号： Y02E30/31 , Y02E30/38
摘要： PROBLEM TO BE SOLVED: To provide a boiling water reactor, a fuel-supporting fixture, a fuel assembly, and an operation method of the boiling water reactor capable of increasing effectively thermal allowance of a core, by suppressing the output rise caused by flow distribution increase, without impairing the flexibility of fuel arrangement.
SOLUTION: This reactor is equipped with many fuel assemblies 7 loaded on the reactor core 1 at a prescribed cycle, and the fuel supporting fixture 15, having a coolant passage 20 for guiding a coolant into the core 1 for each fuel assembly 7. A flow resistance body 21 is detachably provided in a coolant passage 20 corresponding to the fuel assemblies 7, after the third cycle loaded at a place other than the outermost periphery of the core 1.
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：提供一种沸水反应器，燃料支撑固定装置，燃料组件以及能够有效地提高芯的热容限的沸水反应器的操作方法，通过抑制所产生的输出上升通过流量分布增加，而不损害燃料排列的灵活性。解决方案：该反应器配备有以规定的循环装载在反应堆堆芯1上的许多燃料组件7，以及燃料支撑固定件15，其具有用于将冷却剂引导到每个燃料组件7的芯体1中的冷却剂通道20 在第三次循环加载在除了铁心1的最外周之外的位置上，可将流动阻力体21可拆卸地设置在对应于燃料组件7的冷却剂通道20中。（C）2005，JPO＆NCIPI

6. 发明专利

JP2004093142A Nuclear steam supply cassette and nuclear reactor of package type using it 有权
公开(公告)号：JP2004093142A
公开(公告)日：2004-03-25
申请号：JP2002250598
申请日：2002-08-29
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： USUI SHUJI , OYAMA TAKESHI , HIBI HIROMOTO , TAKIMOTO HIROKI , MAKIHARA YOSHIAKI , GOTO HIROSHI , MORIYA KIMIAKI , MATSUURA MASAYOSHI , KOYAMA KAZUTO , CHAGI MASAO
IPC分类号： G21C1/20
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide nuclear steam supply cassettes which can be used for a nuclear power plant as a non-network power source unconnected with an electric power system network and a nuclear reactor of a package type using the cassette.
SOLUTION: The nuclear steam supply cassettes 21 are laid out radially from the center in a moderator tank 31 to be filled with a moderator 30. The nuclear steam supply cassettes 21 are equipped with pressure tubes 22, steam generators 23 laid out circumferentially and extending upward from the center of inner walls of the pressure tubes 22 and in-cassette cores 24, fuel assemblies placed below the steam generators 23. The steam tubes 22 have reinforced fiber layers 26 made by wrapping carbon fiber around the outer peripheral face of pressure tube liners 25. Control rods 32 are laid out around the nuclear steam supply cassette 21 located in the center, and a water shielding tank 35 is placed outside the moderator tank 31. Pressure reducing valves 40 and emergency cooling water supply valves 38 are connected to the nuclear steam supply cassettes 21.
COPYRIGHT: (C)2004,JPO

7. 发明专利

JP2000304885A FUEL ASSEMBLY AND UNCLEAR REACTOR CORE 失效
公开(公告)号：JP2000304885A
公开(公告)日：2000-11-02
申请号：JP11609399
申请日：1999-04-23
申请人： HITACHI LTD
发明人： CHAGI MASAO , NISHIDA KOJI , KANAZAWA TORU , ORII AKIHITO
IPC分类号： G21C3/334 , G21C3/322 , G21C3/324 , G21C3/328
摘要： PROBLEM TO BE SOLVED: To provide a fuel assembly having a large thermal margin and allowing improvement of a critical power of fuel. SOLUTION: This fuel assembly has plural fuel rods 2 arranged in plural lines and plural rows and having lower end parts held by a lower tie plate; and a channel box 7 formed so as to surrounds the fuel rods 2, holding the fuel rods 2. A structure material (a partition member) 33 for plurally partitioning the inside of the channel box 7 in a horizontal cross section is provided inside the channel box 7. An interval C2 between a wall face of the partition member 33 and the fuel rods 2 facing the partition member 33 is set to a smaller value than an interval C1 between the inner wall face of the channel box 7 and the fuel rods 2 facing the channel box 7.

8. 发明专利

JP2000009869A REACTOR CORE OF COILING WATER REACTOR, BOILING WATER REACTOR, AND METHOD FOR OPERATING BOILING WATER REACTOR 失效
公开(公告)号：JP2000009869A
公开(公告)日：2000-01-14
申请号：JP17358398
申请日：1998-06-19
申请人： HITACHI LTD
发明人： CHAGI MASAO , NISHIDA KOJI
IPC分类号： G21C3/326 , G21C1/08 , G21C3/32 , G21C3/322 , G21C7/27
摘要： PROBLEM TO BE SOLVED: To sufficiently improve the nuclear thermohydrulic power stability of a reactor core on non-rated operation while sufficiently preventing the influence of a transition event at the time of rated operation. SOLUTION: In the reactor core with a fuel assembly 2 having a fuel rod, a water rod 13, and a lower tie plate 16 and a fuel-supporting metal 10 for placing the fuel assembly 2, the fuel-supporting metal 10 is provided with a side surface opening 10b whose inner diameter is approximately 6.2 cm, the lower tie plate 16 is provided with an upper end part 16b where a cooing material passage for guiding a cooling material to a fuel bundle is provided, and the water rod 13 is provided with a rising pipe 13a and a descending pipe 13b. The ratio (r) between a total traverse sectional area S1 of a cooling material passage 18 and a total traverse sectional area S2 of a cooling material channel in a channel box 17 is expressed by 0.2

9. 发明专利

JPH1048373A FUEL ASSEMBLY, CHANNEL BOX AND REACTOR CORE 失效
公开(公告)号：JPH1048373A
公开(公告)日：1998-02-20
申请号：JP20341596
申请日：1996-08-01
申请人： HITACHI LTD
发明人： CHAGI MASAO , AOYAMA TADAO , YUJI YOKO , SHIMADA HIDEMITSU , MIWA JUNICHI
IPC分类号： G21C5/00 , G21C3/324 , G21C3/328
摘要： PROBLEM TO BE SOLVED: To provide a fuel assembly, channel box and reactor core capable of sufficiently flattening the axial power distribution and increasing safety margin even with the use of MOX (uranium-plutonium mixed oxide) fuel. SOLUTION: A channel box 7 is constituted of 2 kinds of structure with different materials and the upper structure 12 is made of Zircaloy-2 and the lower structure 11 is made of stainless steel which has larger neutron absorptivity than Zircaloy-2. The boundary between the upper structure 12 and the lower structure 11 is positioned at about 5/24 of the total length from the lower end of the channel box 7 and the upper structure 12 and the lower structure 11 are connected by welding.

10. 发明专利

JP2007225461A Output control method of nuclear reactor and nuclear reactor plant 有权
标题翻译：核反应堆和核反应堆输出控制方法
公开(公告)号：JP2007225461A
公开(公告)日：2007-09-06
申请号：JP2006047674
申请日：2006-02-24
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： ISHII YOSHIHIKO , CHAGI MASAO , KITO KAZUAKI
IPC分类号： G21D3/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To shorten a period at a reactor start time for increasing reactor output up to a rated output in a natural circulation boiling water reactor.
SOLUTION: A feed water control device controls the first temperature of feed water to be supplied to the reactor to become higher than the second temperature of the feed water to be supplied to the reactor at a rated output time in a partial period at the reactor start time for raising the reactor output up to the rated output. The reactor output can be raised also by extracting control rods from the core at the reactor start time. The feed water control device lowers the first temperature to the second temperature after stopping extraction operation of the control rods at the reactor start time.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：在自然循环沸水反应堆中缩短反应堆起始时间以增加反应器输出直到额定输出的时间。供水控制装置控制供给到反应器的供给水的第一温度，以在部分时间内以额定输出时间高于供给到反应器的给水的第二温度反应堆启动时间，将反应堆输出升高到额定输出。反应器输出也可以通过在反应器启动时从芯中提取控制棒而提高。进料水控制装置在反应器启动时停止控制棒的抽出操作后将第一温度降至第二温度。版权所有（C）2007，JPO＆INPIT

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