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1. 发明专利

JP2006208238A Operation method for nuclear power plant 有权
标题翻译：核电厂操作方法
公开(公告)号：JP2006208238A
公开(公告)日：2006-08-10
申请号：JP2005021835
申请日：2005-01-28
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： CHAGI MASAO , KITO KAZUAKI , AOYAMA TADAO , OTSUKA MASAYA , SHIINA KOJI
IPC分类号： G21D3/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear power plant which enables operators to increase the power of the plant by maintaining almost the same pressure loss characteristics of core, safety margin and design margin in transient as before the power increase without changing match the constitution of the plant components, and an operation method for the plant.
SOLUTION: Thermal power in the second operation cycle of a reactor is increased from that in the first operation cycle which is further one operation cycle before the second operation cycle. The fraction of extraction steam from the middle of a high-pressure turbine and the outlet of the high-pressure turbine extracted out of the steam system and leading to a supply water heater vs the main steam flow rate is made smaller in the second operation cycle than in the first operation cycle so that the temperature of the water exhausted out of the supply water heater is lowered by 1°C or higher and 40°C or lower.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供一个核电站，使运营商能够通过在功率增加之前保持几乎相同的核心压力损失特性，安全裕度和设计余量，而不改变匹配，从而提高工厂的功率植物成分的构成以及植物的操作方法。解决方案：反应堆的第二个运行循环中的热功率比第一个运行循环中的热功率增加，这是第二个运行循环之前的一个运行循环。在第二个运行周期中，从高压汽轮机的中部抽出的蒸汽和从蒸汽系统中抽出并导致供热水器与主蒸汽流量相比的出口被抽取得较小比在第一操作循环中使得从供给热水器排出的水的温度降低1℃以上40℃以下。版权所有（C）2006，JPO＆NCIPI

2. 发明专利

JP2006038499A Nuclear power plant and method for operating it 有权
标题翻译：核电厂及其运行方法
公开(公告)号：JP2006038499A
公开(公告)日：2006-02-09
申请号：JP2004215095
申请日：2004-07-23
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： KITO KAZUAKI , CHAGI MASAO , SHIINA KOJI , AOYAMA TADAO , OTSUKA MASAYA , OKURA MINORU , NEMOTO SEIJI , TAKAHASHI YASUHIRO
IPC分类号： G21D3/00 , G21D1/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To increase the electric output of a reactor while curbing both the quantity of generated main steam and the decrease in the design freedom of a main steam system in the increase in the thermal output of the reactor in a nuclear power plant. SOLUTION: In a nuclear power generation system, the thermal output of the reactor is increased by boosting the quantity of the energy (generation) recovered in a low-pressure turbine through the increase in the quantity of the steam entering the low-pressure turbine while the steam extracted from a midpoint in a high-pressure turbine is reduced selectively and the heating amount of the feed water heated by the extracted steam of the main steam is decreased to curb the increase in the flow rate of the main steam by lowering the enthalpy (temperature) of feed water. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：为了增加反应堆的电力输出，同时遏制主蒸汽量和主蒸汽系统的设计自由度的降低，因为核反应堆的热输出增加发电厂。解决方案：在核能发电系统中，通过增加进入低压涡轮机的蒸汽量的增加，增加了低压涡轮机中回收的能量（发电量），从而提高了反应堆的热输出。在从高压汽轮机的中点抽取的蒸汽选择性地降低的同时，由主蒸汽的提取蒸汽加热的供给水的加热量减少，以抑制主蒸汽的流量的增加，从而抑制主蒸汽的流量的增加降低给水的焓（温度）。版权所有（C）2006，JPO＆NCIPI

3. 发明专利

JP2007147466A Water supply device for nuclear reactor 有权
标题翻译：核反应堆供水装置
公开(公告)号：JP2007147466A
公开(公告)日：2007-06-14
申请号：JP2005343016
申请日：2005-11-29
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： FUJIMOTO KIYOSHI , SHIINA KOJI , KITO KAZUAKI , CHAGI MASAO
IPC分类号： G21C15/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To prevent thermal fatigue from occurring owing to temperature variation in water supply nozzles or in thermal sleeves inside thereof by suppressing the effect of temperature variation disturbance on an interface between high-temperature and low-temperature water formed in an annular flow path between the supply nozzles and the thermal sleeves of a nuclear-reactor pressure vessel.
SOLUTION: A water supply device provided on the nuclear-reactor pressure vessel 11 for a nuclear power plant includes, as basic compositions, the water supply nozzles 1 with a water supply system connected thereto, the thermal sleeves 3 on the inside thereof, a header tube 35 connected to their end parts via a T-tube 6, and water injection nozzles 2 connected to the header tube 35. The supply nozzles 1, the thermal sleeves 3, the T-tube 6, the header tube 35, and the injection nozzles 2 are disposed below the liquid level of reactor water in the pressure vessel 11 during rated operation of a nuclear reactor. The thermal sleeves 3 and the injection nozzles 2 are disposed so that the central axes 2a of discharge ports 36 of the injection nozzles 2 are positioned below the positions of the central axes 3a of the thermal sleeves 3.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：为了防止由于供水喷嘴或其内部的热套筒中的温度变化而引起的热疲劳，通过抑制温度变化扰动对形成的高温和低温水之间的界面的影响供应喷嘴和核反应堆压力容器的热套管之间的环形流动路径。解决方案：在核电厂的核反应堆压力容器11上设置的供水装置包括作为基本组成的供水喷嘴1，其具有与其连接的供水系统，其内部的热套3 通过T型管6连接到它们的端部的集管35和连接到集管35的喷水嘴2.供给喷嘴1，热套3，T形管6，集管35，并且注射喷嘴2在核反应堆的额定运行期间设置在压力容器11中的反应堆水的液面之下。热套筒3和注射喷嘴2设置成使得喷嘴2的排出口36的中心轴线2a位于热套筒3的中心轴线3a的位置之下。（C） 2007年，日本特许厅和INPIT

4. 发明专利

JP2007278814A Reactor water supply nozzle 审中-公开
标题翻译：反应器水供应喷嘴
公开(公告)号：JP2007278814A
公开(公告)日：2007-10-25
申请号：JP2006104810
申请日：2006-04-06
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： FUJIMOTO KIYOSHI , SHIINA KOJI , KITO KAZUAKI
IPC分类号： G21C15/02 , G21C13/032
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To improve structure soundness of a water supply nozzle by suppressing thermal fatigue, caused by temperature fluctuation to the inside of the water supply nozzle attached to a reactor pressure vessel.
SOLUTION: This reactor water supply nozzle is equipped as a basic constitution with the water supply nozzle 1 being provided in the reactor pressure vessel, to which a water supply system is connected; a thermal sleeve 3 provided in the inside; a header tube 35 connected to its end through a T-piece 6; and a water injection nozzle 2 connected to the header tube 35. The width of a circular channel 9, between the water supply nozzle 1 inner surface and the thermal sleeve 3 outer surface, is widened to satisfy the inequality: 0.11
摘要翻译：要解决的问题：通过抑制由连接到反应堆压力容器的供水喷嘴内部的温度波动引起的热疲劳来提高供水喷嘴的结构稳定性。解决方案：该反应器供水喷嘴配置为基本构造，其中供水喷嘴1设置在反应堆压力容器中，供水系统连接到反应堆压力容器; 设置在内部的热套筒3; 通过T形件6连接到其端部的集管35; 以及与集管35连接的注水喷嘴2.在供水喷嘴1内表面和热套筒3外表面之间的圆形通道9的宽度被加宽以满足不等式：0.11 <δ/Di≤ 0.16，在从供水喷嘴1的喷嘴角38到安全端39的水平距离的范围内，其中Di是供水喷嘴的内径的最小值，δ是圆形的宽度供水喷嘴的内径的最小值Di与热套筒的外径do的最大值之间的通道。版权所有（C）2008，JPO＆INPIT

5. 发明专利

JP2007232398A Nuclear power plant and pressurizing device for reactor start 审中-公开
标题翻译：核反应堆启动装置和加压装置
公开(公告)号：JP2007232398A
公开(公告)日：2007-09-13
申请号：JP2006050920
申请日：2006-02-27
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： KITO KAZUAKI , ISHII YOSHIHIKO , MURASE MICHIO , CHAGI MASAO
IPC分类号： G21D3/00 , G21C1/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To shorten a start time by avoiding unstableness of a core at the start time of a natural circulation type BWR.
SOLUTION: A steam providing means 33 for providing steam having a required pressure is provided in a reactor of the natural circulation type BWR 1, and steam is supplied to a domain outside a shroud 8 inside the reactor and over the water surface 29, to thereby pressurize the reactor 1 primarily at the start time.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：通过在自然循环型BWR的开始时避免核心的不稳定来缩短开始时间。解决方案：在自然循环型BWR 1的反应器中提供用于提供具有所需压力的蒸汽的蒸汽提供装置33，并且将蒸汽供应到反应器内部的护罩8外部的区域和水面29上，从而主要在开始时对反应器1加压。版权所有（C）2007，JPO＆INPIT

6. 发明专利

JP2006153869A Boiling water reactor and its acoustic vibration suppression method 有权
标题翻译：锅炉水反应器及其振动抑制方法
公开(公告)号：JP2006153869A
公开(公告)日：2006-06-15
申请号：JP2005320566
申请日：2005-11-04
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： OTSUKA MASAYA , AOYAMA TADAO , SHIINA KOJI , CHAGI MASAO , KITO KAZUAKI , TAKAHASHI SHIRO , FUJIMOTO KIYOSHI , TSUBAKI MASAAKI
IPC分类号： G21D3/08 , F01D25/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To suppress pressure vibration accompanying acoustic resonance occurring in a main steam system of a boiling water reactor.
SOLUTION: Pressure sensors 13 and 14 are disposed in a steam dome 6 and a steam pipe 9, and pressure vibration amplitude is detected. The steam dome 6 or steam pipe 9 is provided with a Helmholtz resonance tube 12, and an opening regulating valve 11 is mounted to an inlet pipe 121. The opening of the opening regulating valve 11 is regulated in the direction of decreasing the detected pressure vibration amplitude. Thus, when the detected pressure vibration amplitude becomes minimum, the resonance frequency of the Helmholtz resonance tube 12 matches with (is close to) resonance vibration frequency of the steam system, and can effectively suppress the pressure vibration due to the acoustic resonance.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：抑制在沸水反应堆的主蒸汽系统中发生的伴随声共振的压力振动。解决方案：压力传感器13和14设置在蒸汽穹顶6和蒸汽管9中，并且检测压力振动振幅。蒸汽穹顶6或蒸汽管9设置有亥姆霍兹共振管12，并且开口调节阀11安装在入口管121上。打开调节阀11的开口沿减小检测到的压力振动的方向振幅。因此，当检测到的压力振动振幅变得最小时，亥姆霍兹共振管12的共振频率与蒸汽系统的（接近）共振振动频率相匹配，并且可以有效地抑制由于声共振引起的压力振动。版权所有（C）2006，JPO＆NCIPI

7. 发明专利

JP2015010749A 伝熱装置审中-公开
标题翻译：传热装置
公开(公告)号：JP2015010749A
公开(公告)日：2015-01-19
申请号：JP2013135740
申请日：2013-06-28
申请人：株式会社日立製作所 , Hitachi Ltd
发明人： TAMURA AKINORI , KAWAMURA TOSHINORI , KITO KAZUAKI , NAKANO HIROSHI
IPC分类号： F28F13/12 , F28D7/16 , F28F1/12
CPC分类号： F28D7/16 , F28F13/06 , F28F13/12 , F28F13/185 , F28F13/187
摘要：【課題】本発明の課題は、低流速時においても微細多孔質層による伝熱促進効果を十分に得ることにある。【解決手段】本発明は、前記低温流体と接する伝熱管表面に、微細多孔質層と複数の伝熱促進構造を備え、流れの代表長さDに対し、前記伝熱促進構造の高さHが0.05≧H/D≧0.01であり、かつ、前記伝熱促進構造の流れ方向への設置間隔Lが40
摘要翻译：要解决的问题：以低流速充分提供微细多孔层的传热促进效果。解决方案：该传热装置包括在传热表面上的细多孔层和多个传热促进结构与低温流体接触的管道。传热促进结构的高度H相对于流动代表长度D满足0.05≥H/D≥0.01，传热促进结构向流动方向的安装间隔L满足40

8. 发明专利

JP2008249580A Nuclear power plant, thermal fatigue monitoring method for water supply nozzle, and operation method for nuclear power plant 有权
标题翻译：核电厂，供水喷射器的热疲劳监测方法及核电厂的运行方法
公开(公告)号：JP2008249580A
公开(公告)日：2008-10-16
申请号：JP2007092884
申请日：2007-03-30
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： FUJIMOTO KIYOSHI , SHIINA KOJI , KITO KAZUAKI
IPC分类号： G21C17/003 , G21D3/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear power plant capable of enhancing an operation rate.
SOLUTION: A monitor 42 has a computing device 43 and a determination device 44. A temperature detector 41 measures a cooling water temperature in the vicinity of a water supply nozzle 12 provided in an RPV 3. The computing device 43 input with a temperature measured value calculates a non-stationary stress δ
alt and a cumulative damage coefficient Uf. The determination device 44 determines whether respective calculated values satisfy respective set values thereof or not. For example, a controller 48 increases an opening degree of an extraction steam flow regulating valve 40, when the cumulative damage coefficient Uf is 1 or more, to increase a water supply temperature. The computing device 43 predicts the cumulative damage coefficient Uf in the future. The determination device 44 determines whether the predicted cumulative damage coefficient Uf is less than 1 or not. The controller 48 increases the water supply temperature, for a period from a time point when the predicted cumulative damage coefficient Uf comes to 1, up to the stop of the plant, when the time point of reaching 1 is before the next periodic inspection.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：提供能够提高运行速率的核电站。解决方案：监视器42具有计算装置43和确定装置44.温度检测器41测量设置在RPV 3中的供水喷嘴12附近的冷却水温度。计算装置43输入温度测量值计算非稳定应力δ alt 和累积损伤系数Uf。确定装置44确定各个计算值是否满足其各自的设定值。例如，当累积破坏系数Uf为1以上时，控制器48增加抽取蒸汽流量调节阀40的开度，以增加供水温度。计算装置43预测将来的累积损伤系数Uf。确定装置44确定预测的累积损伤系数Uf是否小于1。控制器48在从下一个周期性检查之前到达1的时间点的预测累积损伤系数Uf达到1的时间点到设备的停止时间段时，增加供水温度。版权所有（C）2009，JPO＆INPIT

9. 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

10. 发明专利

JP2005299644A Nuclear power generation system 有权
标题翻译：核发电系统
公开(公告)号：JP2005299644A
公开(公告)日：2005-10-27
申请号：JP2005068317
申请日：2005-03-11
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： SHIINA KOJI , KITO KAZUAKI , OTSUKA MASAYA , AOYAMA TADAO
IPC分类号： G21D1/02 , F01D17/00 , F01D19/00 , F01K7/24
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a compact moisture separating superheater by installing a built-in moisture separating superheater in a main vapor pipe between the outlet of a high pressure turbine and the inlet of a low pressure turbine during increasing the heat output of a reactor core, while solving the problem on a conventional nuclear power generation system that main vapor at the outlet of the high pressure turbine gets to a high wetness to lower the performance of the low pressure turbine when increasing the heat output of the reactor core as an existing moisture separator remains as it is.
SOLUTION: This nuclear power generation system comprises the built-in moisture separating superheater installed in the main vapor pipe between the outlet of the high pressure turbine and the inlet of the low pressure turbine, whereby the compact moisture separating superheater is provided for improving the heat efficiency of nuclear power to increase the electric output of a nuclear reactor.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：通过在高压涡轮机的出口和低压涡轮机的入口之间的主蒸气管中安装内置的分水过热器来提供紧凑的水分分离过热器，以增加热量输出在解决常规核动力发电系统的问题时，高压涡轮机出口处的主蒸气达到高湿度，以便在增加反应堆堆芯的热量输出时降低低压涡轮机的性能因为现有的水分分离器保持原样。解决方案：该核发电系统包括安装在高压汽轮机出口与低压汽轮机入口之间的主蒸气管内的内置分水过热器，由此提供紧凑的水分分离过热器提高核电热效率，增加核反应堆的电力输出。版权所有（C）2006，JPO＆NCIPI

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