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1. 发明专利

JP2002022564A TORQUE MEASURING INSTRUMENT 失效
公开(公告)号：JP2002022564A
公开(公告)日：2002-01-23
申请号：JP2000207478
申请日：2000-07-07
申请人： TOSHIBA CORP , TOKYO ELECTRIC POWER CO
发明人： KURODA HIDEHIKO , KANEMOTO SHIGERU , SATO MICHIO , KONDO TAKAHISA , YAMASHITA TATSUO , SAKAKIDA HITOSHI , OYAGI KIYOTO , UMEZAWA SHUICHI , OBIKAWA HAJIME
IPC分类号： G01L3/10 , G01L3/12
摘要： PROBLEM TO BE SOLVED: To provide a torque measuring instrument capable of measuring a rotating speed and torque for every rotation with high accuracy by finding the cycle of rotation for every rotation with a measurement accuracy higher than 10 ns with respect to a rotating body whose rotating speed finely varies. SOLUTION: This instrument is equipped with an irradiation means 20 for light beam irradiation, a beam adjustment means 21 for branching a light beam into a plurality of beams and adjusting the beam diameter of each beam to irradiate a measuring body 37 therewith, a plurality of reflection means 22 and 23 mounted on a surface of the measuring body 37 to individually change the reflection state of the plurality of beams, a plurality of detection means 24 and 25 for detecting an intensity change in each reflected beam of the plurality of beams, and a signal processing means 26 for computing the torque of the measuring body 37 based on the output signals of the detection means 24 and 25.

2. 发明专利

JP2000205977A TORQUE MEASURING APPARATUS 失效
公开(公告)号：JP2000205977A
公开(公告)日：2000-07-28
申请号：JP568899
申请日：1999-01-12
申请人： TOSHIBA CORP , TOKYO ELECTRIC POWER CO
发明人： UMEZAWA SHUICHI , SAITO KAZUO , KURODA HIDEHIKO , KANEMOTO SHIGERU , SATO MICHIO , KONDO TAKAHISA , OCHIAI MAKOTO
IPC分类号： G01L3/08
摘要： PROBLEM TO BE SOLVED: To provide a torque measuring apparatus capable of measuring the rotational speed and torque per rotation of a rotor whose rotational speed varies subtly, by determining the rotational period of the rotor per rotation with a measuring accuracy of higher than 10 ns. SOLUTION: This apparatus includes an irradiation means 20 which irradiates a light beam, a beam adjustment means 21 which causes the light beam to branch into a plurality of light beams and irradiates the subject of measurement 37 with the light beams while adjusting the diameter of each light beam, a plurality of reflection means 22, 23 mounted on the surface of the subject of measurement 37 for varying the reflections of the plurality of light beams, a plurality of detection means 24, 25 for detecting changes in intensity of the plurality of reflected light beams, and a signal processing means 26 which determines the torque of the subject of measurement 37 by calculating its period of rotation on the basis of signals outputted from the detection means 24, 25.

3. 发明专利

JP2002267787A METHOD FOR MEASURING FLOW RATE OF REACTOR CORE COOLANT 失效
公开(公告)号：JP2002267787A
公开(公告)日：2002-09-18
申请号：JP2001065416
申请日：2001-03-08
申请人： TOKYO ELECTRIC POWER CO , TOSHIBA CORP
发明人： MORI HARUTSUGU , ENOMOTO MITSUHIRO , KANEMOTO SHIGERU , EHATA SHIGEO
IPC分类号： G21C17/032 , G21C17/00 , G21C17/02
摘要： PROBLEM TO BE SOLVED: To improve the error of a conventional measuring method for flow rate of reactor core coolant while considering the thermal hydraulic condition and control rod position in a fuel channel. SOLUTION: The bubble transmission time between detectors is measured from the correlation of the fluctuation components of the output signals detected by at least two neutron detectors arranged in axially different positions between a plurality of fuel channels. The bubble and liquid phase average transmission times in a plurality of fuel channels are calculated on the basis of the thermal output distribution and hot water model of fuel channel determined by core performance calculation, and the arithmetic weighted mean based on a preset weighting value is determined from the calculation values for four fuel channels adjacent to the neutron detectors among the resulting calculated values. At this time, the weight value is corrected, considering the horizontal distribution of bubble speed in the fuel channel. The inlet coolant flow rates of each fuel channel and the whole reactor core are estimated so that the measured value of the bubble transmission time is matched to the arithmetic weighted mean.

4. 发明专利

JPH10115693A METHOD OF MONITORING NUCLEAR REACTOR CORE 失效
公开(公告)号：JPH10115693A
公开(公告)日：1998-05-06
申请号：JP26976096
申请日：1996-10-11
申请人： TOKYO ELECTRIC POWER CO , TOSHIBA CORP
发明人： MORI HARUTSUGU , KANEMOTO SHIGERU , ENOMOTO MITSUHIRO , EHATA SHIGEO
IPC分类号： G01F1/712 , G21C17/00 , G21C17/02 , G21C17/032
摘要： PROBLEM TO BE SOLVED: To enable highly-accurate monitoring of a state of flowing of a coolant in a nuclear reactor by a method wherein a detection signal of a local neutron flux monitor (LPRM) detector is subjected to a statistic processing after general fluctuation components are removed therefrom. SOLUTION: Four LPRM detectors 1 are disposed at prescribed intervals in an instrumentation tube 4 provided in a bypass passage surrounded by four fuel channels 3 in a reactor core 2. Each LPRM detector 1 measures thermal neutrons moderated by water in the bypass passage and the fuel channels. After general fluctuation components fluctuating in the whole reactor core in the nuclear thermal hydraulic terms are removed from detection signals of the LPRM detectors 1, a correlation function between these detection signals is determined and the state of flowing of a coolant in a nuclear reactor is monitored on the basis of this correlation function. Since the information on local voids in the circumference of the LPRM detectors 1 is extracted beforehand with high accuracy in this way, the accuracy in monitoring of local behaviors in the axial and radial directions of the coolant is improved.

5. 发明专利

JP2004020540A Method and apparatus for measuring displacement of rotator and method for installing ultrasonic sensor 有权
公开(公告)号：JP2004020540A
公开(公告)日：2004-01-22
申请号：JP2002180253
申请日：2002-06-20
申请人： Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝
发明人： ARAKAWA KATSUHIRO , HASHIMOTO SATORU , NAKAYAMA SHIGEO , UDAGAWA KAZUYUKI , SATO MICHIO , KANEMOTO SHIGERU , UHARA YOSHIHIKO
IPC分类号： G01B17/00
摘要： PROBLEM TO BE SOLVED: To provide a method and an apparatus for measuring displacements of rotator of performing measurements at some distance from the rotator without being restrained by the conditions of the surface of the rotator and to provide a method for installing an ultrasonic sensor for measuring displacements of the rotator.
SOLUTION: The rotator 9 is placed in a container 5 filled with a liquid 4. Ultrasonic waves are transmitted to the rotator via the container and the liquid. The ultrasonic waves reflected from the rotator are received. This method and the apparatus measures the displacement of the rotator by determining the presence or absence and vibrations of the rotator through waveform computation on the received ultrasonic waves. The ultrasonic waves are transmitted to the rotator via the liquid, and the ultrasonic waves reflected from the rotator via the liquid are received. Then, by determining a location at which the waveform of the ultrasonic echoes reflected from the rotator and the container become maximum, the ultrasonic sensor is installed at the location where the waveform of the ultrasonic echoes become maximum in the method for installing the ultrasonic sensor.
COPYRIGHT: (C)2004,JPO

6. 发明专利

JP2005134291A Reactor core monitoring method for boiling water nuclear reactor 审中-公开
标题翻译：水核反应堆锅炉反应器核心监测方法
公开(公告)号：JP2005134291A
公开(公告)日：2005-05-26
申请号：JP2003372183
申请日：2003-10-31
申请人： Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝
发明人： KAGAMI YUICHI , MORI HARUTSUGU , KANEMOTO SHIGERU , ENOMOTO MITSUHIRO , KAWAMURA SHINICHIRO
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To estimate a main parameter affecting a reactor core dynamic characteristic such as a void reactivity coefficient, and a noise source causing a steady state fluctuation, from time to time, without imparting disturbance to a plant under an operation, so as to be utilized for monitoring a reactor core.
SOLUTION: A statistical feature amount is found by frequency analysis, based on fluctuation components of a neutron flux signal and a reactor core flow rate signal of a boiling water nuclear reactor, a theoretical value of the statistical feature amount is found by assuming the plurality of noise sources in a dynamic characteristic model of the reactor core of the boiling water nuclear reactor, a level of the parameter or the noise source in the dynamic characteristic model to minimize a difference between the statistical feature amount and the theoretical value of the statistical feature amount, and the level of the parameter or the noise source is used for the monitoring.
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：不时地对工厂造成干扰的情况，不时地估计影响反应堆堆芯动态特性（如空隙反应性系数）的主要参数和引起稳态波动的噪声源，以便用于监测反应堆堆芯。解决方案：根据沸腾核反应堆的中子通量信号和反应堆核心流量信号的波动分量，通过频率分析发现统计特征量，统计特征量的理论值通过假设在沸水核反应堆的反应堆核心的动态特性模型中的多个噪声源，动态特性模型中的参数或噪声源的水平，以最小化统计特征量与理论值之间的差异统计特征量，以及参数或噪声源的水平用于监测。版权所有（C）2005，JPO＆NCIPI

7. 发明专利

JP2004279338A Method for measuring temperature reactivity coefficient of nuclear reactor 审中-公开
公开(公告)号：JP2004279338A
公开(公告)日：2004-10-07
申请号：JP2003074055
申请日：2003-03-18
申请人： Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝
发明人： MORI HARUTSUGU , KAGAMI YUICHI , KANEMOTO SHIGERU , ENOMOTO MITSUHIRO , EHATA SHIGEO , TAMAOKI TETSUO
IPC分类号： G21C17/108 , G21C17/00
摘要： PROBLEM TO BE SOLVED: To measure temperature reactivity coefficient in shorter time than a conventional method from observation signals of neutron flux and coolant temperature.
SOLUTION: The method comprises a state equation conversion part 1 constituted of one-point approximate dynamics model 1a of neutron flux and dynamics model 1b of coolant temperature of a reactor where observation signal of neutron flux and coolant temperature of the reactor is input, a likelihood calculation part for calculating logarithmic likelihood by applying Kalman filter to the state equation obtained from the state equation conversion part 1, and a temperature reactivity coefficient estimation part 4 for estimating the temperature reactivity coefficient by maximizing the logarithmic likelihood obtained in the likelihood calculation step. The temperature reactivity coefficient is measured from the observation signals of the neutron flux and coolant temperature of the reactor.
COPYRIGHT: (C)2005,JPO&NCIPI

8. 发明专利

JP2004279333A Method of monitoring inside of boiling water nuclear reactor 有权
公开(公告)号：JP2004279333A
公开(公告)日：2004-10-07
申请号：JP2003074026
申请日：2003-03-18
申请人： Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝
发明人： MORI HARUTSUGU , UNNO MASARU , KANEMOTO SHIGERU , ENOMOTO MITSUHIRO , EHATA SHIGEO
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To provide a method of monitoring blocking in a fuel channel with practically usable measurement precision, utilizing both a shape feature of a mutual correlation function of fluctuation signals from two detectors in a neutron instrumentation tube, and a void distribution and void speed information of the four fuel channels in a periphery of the instrumentation tube. SOLUTION: A fluctuation component in a specified frequency band is extracted to calculate the mutual correlation function, based on the signals from the two detectors arranged vertically in the same instrumentation tube, and a void moving time between the two detectors is calculated based on a peak of the mutual correlation function. A void moving speed is calculated, using a hydrothermal power model, based on an output temperature distribution in a nuclear reactor core calculated by a process computer, and an inlet flow rate and an inlet temperature in the fuel channel, and an average void moving time is calculated based thereon. The average void moving time is compared with the void moving time obtained by the mutual correlation function, and an alarm is generated for notifying the presence of abnormality in the flow rate in the fuel channel in the periphery of the marked detectors, when a prescribed value or more of difference is observed therebetween. COPYRIGHT: (C)2005,JPO&NCIPI

9. 发明专利

JP2005061937A Ultrasonic sensor 审中-公开
标题翻译：超声波传感器
公开(公告)号：JP2005061937A
公开(公告)日：2005-03-10
申请号：JP2003291125
申请日：2003-08-11
申请人： Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝
发明人： NAKAYAMA SHIGEO , KANEMOTO SHIGERU , HIKUMA KOJI
IPC分类号： G01B17/02 , G01N29/24
摘要： PROBLEM TO BE SOLVED: To provide an ultrasonic sensor not needing to be kept on by a worker, and having a structure in which the ultrasonic sensor is appropriately pressed against a measuring object whether a material is magnetic or non-magnetic.
SOLUTION: This ultrasonic sensor 1 is structured to irradiate an ultrasonic wave to the measuring object 4 and to receive a reflected wave from the measuring object. A suction cup 9 is provided sticking fast to the measuring object with a surface where the ultrasonic sensor makes contact with the measuring object kept at its center position.
COPYRIGHT: (C)2005,JPO&NCIPI

10. 发明专利

JPH11125688A REACTOR VIBRATION MONITOR 失效
公开(公告)号：JPH11125688A
公开(公告)日：1999-05-11
申请号：JP29124197
申请日：1997-10-23
申请人： TOKYO ELECTRIC POWER CO , TOSHIBA CORP
发明人： HASHIMOTO SATORU , SATO MICHIO , SAKUMA MASATAKE , KANEMOTO SHIGERU
IPC分类号： G01H17/00 , G21C17/00
摘要： PROBLEM TO BE SOLVED: To directly measure the vibration of core structure from outside the pressure vessel, by introducing ultrasonic pulse signal into the reactor through the reactor pressure vessel, and receiving and processing the reflection signal from the core structure. SOLUTION: A reactor vibration monitor is constituted of an ultrasonic transducer 1 and the like placed on the outer surface of a reactor pressure vessel 2. The transducer 1 capable of both transmission and reception is connected to an ultrasonic signal processor consisting of an ultrasonic transmitter 6, an ultrasonic receiver 7, a signal processor 8, etc. When electric pulse signal 10 is added from the transmitter 6, ultrasonic pulse signal 1 is generated in the pressure vessel 2, which transmits in core water 12, reflects on the core structure 14 and returns to the transducer 1 as an ultrasonic pulse signal 15, and is converted to electric pulse signal. This signal is processed in a signal processor 8 and the like, and vibration information such as vibration amplitude and waveform 16 is indicated. By using pulse signal of radio frequency, Doppler shift can be utilized.

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