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1. 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.

2. 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.

3. 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

4. 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

5. 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

6. 发明专利

JPH1010276A METHOD AND SYSTEM FOR COOLANT FLOWRATE MEASUREMENT IN REACTOR CORE 失效
公开(公告)号：JPH1010276A
公开(公告)日：1998-01-16
申请号：JP15855896
申请日：1996-06-19
申请人： TOKYO ELECTRIC POWER CO , TOSHIBA CORP
发明人： MORI HARUTSUGU , KANEMOTO SHIGERU , ENOMOTO MITSUHIRO , EHATA SHIGEO , TAKAMORI YUKIO
IPC分类号： G01F1/00 , G21C17/032
摘要： PROBLEM TO BE SOLVED: To accurately measure the estimation value of coolant flowrate by making use of the method for coolant flowrate measurement and the advantage of its system using a prior art neutron detector and adding the characteristics of each fuel channel, and raise the reliability of core management and the like during operation. SOLUTION: For measuring method of coolant flowrate in a reactor core, a measuring value Tmeas of bubble transmission time corresponding to the delay time of fluctuation components is obtained in step S1 from the frequency components X1 and X2 detected with two neutron detectors arranged in different axial positions between a plurality of fuel channels in the reactor core. In step S2, based on thermal power distribution pattern obtained with the specified reactor core performance calculation, a prediction value Tcal of bubble transmission time in each of a plurality of fuel channels is determined. In step S3, based on the measured value Tmeas and the predicted value Tcal of the bubble transmission time, methods to measure an estimation value WT of gross flowrate of coolant in the whole reactor and an estimation value W (n) of local coolant flowrate at each of a plurality of fuel channels are used.

7. 发明专利

JP2003114294A MONITOR, DIAGNOSIS, INSPECTION AND MAINTENANCE SYSTEM FOR POWER-GENERATING PLANT 审中-公开
公开(公告)号：JP2003114294A
公开(公告)日：2003-04-18
申请号：JP2001309124
申请日：2001-10-04
申请人： TOSHIBA CORP
发明人： SONODA YUKIO , ENOMOTO MITSUHIRO , HIROSE YUKINORI , UDAGAWA KAZUYUKI , UHARA YOSHIHIKO , HIKUMA KOJI , NAKANO TOMOHITO , SHIMIZU SHUNICHI , NAGASE KOICHI , OKAMURA KIYOSHI
IPC分类号： G01M99/00 , G05B23/02 , G06Q50/00 , G06Q50/06 , G06Q50/10 , G21C17/00 , G21C17/003 , G01M19/00 , G06F17/60
摘要： PROBLEM TO BE SOLVED: To provide a monitor, diagnosis, inspection and maintenance system for power-generating plants capable of having high operability and economical efficiency by collecting plant operation and maintenance field data from a plurality of power-generating plants in maintenance service centers through a network. SOLUTION: The operation data 7 about plants and equipment are monitored by a monitoring means 3, controlled by a control means 5, retrieved and browsed by a retrieving means 4. A transmitting means 15 transmits the operation data 7 and the like to a company 10 providing a maintenance service from the power-generating plants 1, the operation data 7 received by the maintenance service providing company 10 is stored in a storage means 12, and a sub-analysis means evaluates the abnormality, performance and degradation of the plants and the equipment by using the operation data or the like stored in the storage means 12 to determine a maintenance measure. The analysis result and data are displayed in a site by a communicating means 15. The data and the analysis result and the like are encrypted by a security means.

8. 发明专利

JP2002296142A LEAKAGE DETECTING DEVICE 失效
公开(公告)号：JP2002296142A
公开(公告)日：2002-10-09
申请号：JP2001097331
申请日：2001-03-29
申请人： TOSHIBA CORP
发明人： KANEMOTO SHIGERU , SONODA YUKIO , KURODA HIDEHIKO , ENOMOTO MITSUHIRO , HIKUMA KOJI
IPC分类号： G01M3/38
摘要： PROBLEM TO BE SOLVED: To make it possible to detect a place where leakage occurs and estimate the quantity of the leakage, even in the case the leakage is in very small quantities and leaking vapor is transparent. SOLUTION: Moving picture data from a photographing section 30 is converted into a digital image by a data converting section 41, and velocity vector is calculated on the basis of the digital image by a section for calculating velocity vector 42. Then, the velocity vector image is divided into small regions P, and a value of surface integration representing the degree of convergence of the velocity vector at the small region P is calculated by a section for calculating surface integration 43. The presence or absence of the occurrence of leakage at the region can be judged based on the value of surface integration, and the judgement whether the leakage is inner leak or outer leak can be made when it occurs.

9. 发明专利

JP2001042078A METHOD AND APPARATUS FOR MEASUREMENT OF VOID REACTIVITY COEFFICIENT OF BOILING WATER REACTOR 失效
公开(公告)号：JP2001042078A
公开(公告)日：2001-02-16
申请号：JP21917699
申请日：1999-08-02
申请人： TOSHIBA CORP
发明人： TAMAOKI TETSUO , KANEMOTO SHIGERU , ENOMOTO MITSUHIRO , EHATA SHIGEO , SUGAWARA MASATOSHI
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To measure the void reactivity coefficient in an on-line manner without giving a disturbance by a method wherein a transfer function which uses a core flow rate as an input and which uses a neutron flux as an output is identified, a feature parameter value is found and a correlation expression is used. SOLUTION: A plant signal 100 is measured by a signal input part 1 so as to be converted into time-series data 101. In succession, in a transfer-function identification part 2, an autoregressive model is fitted to the time-series data 101, and a transfer function is identified. Identified transfer function data 102 is input to a transfer characteristic parameter computing part 3, and a transfer characteristic parameter Θ is calculated. Its calculated result 103 is input to a void reactivity coefficient computing part 4, and a void reactivity coefficient is computed by using a correlation expression 104 of K=F (Θ) which is stored in advance in a correlation expression storage part 5. Then, its computed result 105 is output to an output display part 6 so as to be displayed, and one measurement is finished.

10. 发明专利

JPH08234832A DEVICE AND METHOD FOR MONITORING AND DIAGNOSTIC PLANT 失效
公开(公告)号：JPH08234832A
公开(公告)日：1996-09-13
申请号：JP3726495
申请日：1995-02-24
申请人： TOSHIBA CORP
发明人： TAMAOKI TETSUO , SONODA YUKIO , ENOMOTO MITSUHIRO , KANEMOTO SHIGERU , KOMAI NORIMITSU , KAGEYAMA TAKAO , OTA YASUO
IPC分类号： G21D3/04 , G05B23/02
摘要： PURPOSE: To speedily diagnose the factor of abnormality even when the influence of abnormality generated at a large scale plant is propagated between systems or subsystems in a short time and any change appears in process signals over a wide range. CONSTITUTION: This device is provided with a monitor processing part 3 for detecting the runaway of a monitor index from a normal range calculated by the process signal observed at the plant as an abnormality indication, qualitative model data base 6 registering a network model describing the characteristics of influence propagation between the respective monitor indexes, abnormality propagation route identifying part 4 for identifying the route of abnormality propagation caused by abnormality by collating the observed indication pattern with the network model, cause-and-effect table data base 7 registering a cause- and-effect table describing the indication patterns of respective monitor indexes estimated to various abnormality factors, abnormality factor identifying part 5 for identifying the abnormality factor by collating the cause-and-effect table of monitor indexes identified as the origins of abnormal changes with the observed indication patterns, and output display part 10 for outputting the identified influence propagation route.

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