WO2014091955A1 - Système de surveillance de barre de commande et procédé de surveillance de barre de commande - Google Patents

Système de surveillance de barre de commande et procédé de surveillance de barre de commande Download PDF

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Publication number
WO2014091955A1
WO2014091955A1 PCT/JP2013/082306 JP2013082306W WO2014091955A1 WO 2014091955 A1 WO2014091955 A1 WO 2014091955A1 JP 2013082306 W JP2013082306 W JP 2013082306W WO 2014091955 A1 WO2014091955 A1 WO 2014091955A1
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WO
WIPO (PCT)
Prior art keywords
relationship
control rod
model
monitoring system
pressure vessel
Prior art date
Application number
PCT/JP2013/082306
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English (en)
Japanese (ja)
Inventor
哲 寺澤
加藤　真也
敬之 山本
敬喜 朝倉
林　司
山本　秀夫
睦男 生田
安達　勝
将弘 崎部
健三 宮
知也 相馬
真弓 高城
大石　敏之
Original Assignee
日本電気株式会社
中国電力株式会社
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 日本電気株式会社, 中国電力株式会社 filed Critical 日本電気株式会社
Priority to JP2014551982A priority Critical patent/JP6418640B2/ja
Publication of WO2014091955A1 publication Critical patent/WO2014091955A1/fr

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108—Measuring reactor flux
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to sensing technology in a nuclear reactor, and more particularly to a control rod monitoring system and a control rod monitoring method for recognizing movement of a control rod from an event occurring in a reactor containment vessel.
  • FIG. 12 is a schematic diagram showing an arrangement of sensor positions such as a local output region monitor (LPRM). As shown in FIG.
  • a local output region monitor (local output region monitor detector: neutron sensor) is installed between fuel assemblies as measurement positions in the nuclear reactor, and emitted from the surrounding fuel assemblies. Measured neutron flux. As shown in FIG. 12B, a plurality of local output region monitor detectors are installed at different heights at one measurement position. A large number of local power region monitors are equally provided in one nuclear reactor. A large number of control rods (CR: Control Rod) are used for controlling the nuclear reactor. The control rod is made of a member that absorbs neutrons, and is inserted into the core from below in a boiling water reactor.
  • each control rod moves downward, which is a direction in which the control rod is pulled out in accordance with the operation of a control rod driving device (CRD: Control Rod Drive). Due to the movement of the control rod, the absorption amount of neutrons emitted from the nearby nuclear fuel assemblies by the control rod is reduced, and the reactor power is increased by increasing the nuclear chain reaction.
  • the local output region monitor detector is used for monitoring the neutron flux emitted at this time.
  • Related techniques used in nuclear reactors are described in, for example, Japanese Patent Application Laid-Open No. 2010-91475 and Japanese Patent Application Laid-Open No. 2012-02652 (hereinafter referred to as Patent Document 1 and Patent Document 2 in this order).
  • Patent Document 1 describes a control rod pull-out monitoring device that stops pulling out a control rod when the output of a nuclear reactor suddenly increases when the control rod is pulled out.
  • the control rod withdrawal monitoring device described in this document uses a local output region monitor (LPRM) and a control rod withdrawal monitoring portion (RBM).
  • LPRM local output region monitor
  • RBM control rod withdrawal monitoring portion
  • movement better by only a small addition change of the existing installation is described. This is a necessary measure to eliminate the adverse effects of modifications to reactor control.
  • Patent Document 2 describes a control rod position monitoring device that monitors the physical positions of individual control rods. More specifically, Patent Document 2 describes a control rod position detector using a mechanical multiple switch structure, and a control rod position monitoring device that multiplexes the output signal of the position detector to the control panel. Yes.
  • a local output region monitor detects a neutron flux that changes due to insertion and removal of a control rod. Using this detection value, an operator or system obtains an output from the local output area monitor.
  • control rods are inserted into and removed from the core by a control rod drive (CRD).
  • CCD control rod drive
  • the amount of each control rod inserted / extracted is obtained from the operation of the personnel and the hardware structure. Note that a mechanism for obtaining the position of the control rod is installed outside the reactor pressure vessel as in the position detector shown in Patent Document 2.
  • An object of the present invention is to provide a control rod monitoring system and a control rod monitoring method for identifying legitimacy of control rod position change from measured values obtained from a local output area monitor.
  • Another object of the present invention is to provide a control rod monitoring system and a control rod monitoring method for identifying a moved control rod from a measured value obtained from a local output area monitor.
  • the control rod monitoring system relates to a plurality of neutron beam measurement sensor means provided in a reactor pressure vessel, and the pressure indicating the mutual relationship between the output values of the individual neutron beam measurement sensor means.
  • a relationship model database storing in-vessel sensor known relationship models, a pressure vessel in-vessel sensor known relationship model recorded in the relationship model database, and a monitoring object obtained from the plurality of neutron beam measurement sensor means;
  • a relationship verification means for comparing the relationship model obtained from the measured values to monitor the relationship collapse based on the amount of the mismatched portion of the relationship and extracting a predetermined amount of the relationship collapse as a notification event; , Including.
  • control rod monitoring system is a known sensor distribution indicating the location of the mismatched relationship appearing in the broken relationship obtained from the relationship verification means and the physical position coordinates of the individual neutron beam measurement sensor means. Reference may be made to the position information, and control rod position detection means for specifying the control rod that caused the disruption of the relationship based on the distribution of the individual neutron beam measurement sensor means that appeared in the collapse may be further included. Moreover, when generating the relationship model obtained from the present neutron beam measurement sensor means, it is desirable to pre-process the measurement values.
  • control rod monitoring system and a control rod monitoring method for identifying the legitimacy of a control rod position change from a measurement value obtained from a local output area monitor. Further, according to the present invention, it is possible to provide a control rod monitoring system and a control rod monitoring method for identifying a moved control rod from a measured value obtained from a local output area monitor.
  • FIG. 1 is a block diagram showing a control rod monitoring system according to a first embodiment of the present invention.
  • FIG. 2 is a flowchart illustrating the processing operation of the control rod monitoring system according to the first embodiment.
  • FIG. 3 is a block diagram showing a control rod monitoring system according to the second embodiment of the present invention.
  • FIG. 4 is a flowchart illustrating the processing operation of the control rod monitoring system according to the second embodiment.
  • FIG. 5 is a flowchart illustrating another processing operation of the control rod monitoring system according to the second embodiment.
  • FIG. 6 is a block diagram showing a control rod monitoring system according to the second embodiment of the present invention.
  • FIG. 7 is a flowchart illustrating the processing operation of the control rod monitoring system according to the third embodiment.
  • FIG. 8 is explanatory drawing which shows the power station equipment concerning an Example.
  • FIG. 9 is an explanatory diagram showing temporal changes in measured values of LPRM collected at a nuclear power plant in the past.
  • FIG. 10 is a flowchart illustrating a model generation process in a steady state used in the control rod monitoring system.
  • FIG. 11 is an explanatory diagram that graphs the amount of disruption in the relationship between models using actual measurement values collected in the past for the LPRM group in the reactor pressure vessel.
  • FIG. 12 is a schematic diagram showing the position of a sensor such as a local output region monitor (LPRM) disposed in the reactor pressure vessel.
  • LPRM local output region monitor
  • FIG. 1 is a block diagram showing a control rod monitoring system 10 according to the first embodiment.
  • the control rod monitoring system 10 includes a plurality of local output region monitors (hereinafter referred to as LPRM) 101 to 10n, a relationship model database 200, and a relationship verification module 300.
  • LPRM local output region monitors
  • Each of the LPRMs 101 to 10n includes a plurality of LPRM detectors 111... 1 nm.
  • Each LPRM detector 111... 1 nm operates as neutron beam measurement sensor means.
  • the relationship model database 200 stores and holds a pressure vessel in-sensor known relationship model indicating a relationship between output values for the individual LPRMs 101 to 10n.
  • the pressure vessel sensor known relationship model models the relationship regarding the output value for all combinations of the individual LPRM detectors 111... 1 nm.
  • the relationship reflected in the known relationship model includes the presence or absence of the relationship and its strength.
  • reciprocity may be added.
  • the known relationship model reflects the order of the strength of the relationship of other LPRM detectors with respect to individual LPRM detectors as the correlation between the sensors.
  • a better model comparison can be performed by using the correlation.
  • the relationship verification module 300 models LPRM measurement values to be monitored, such as measurement values having real-time characteristics, and generates a relationship model for the monitoring targets.
  • the relationship verification module 300 acquires the in-pressure vessel sensor known relationship model recorded in the relationship model database 200, and compares the generated relationship model of the monitoring target with the in-pressure vessel sensor known relationship model. To do. Extract the inconsistent relationship found by comparison. This disagreement of relations occurs when the relations of the individual LPRM detectors differ from model to model. Next, the relationship verification module 300 monitors a mismatched portion of the relationship including the time axis, and calculates the relationship collapse. As the value indicating the collapse of the relationship, the number of mismatched portions, the increase amount per time of the mismatched portions, and the like can be used. The relationship verification module 300 may extract a notification event when the relationship collapse exceeds a predetermined amount (predetermined threshold value) and notify the administrator (control panel), other systems responsible for safety, and the like.
  • predetermined threshold value a predetermined amount
  • FIG. 2 is a flowchart illustrating the processing operation of the control rod monitoring system 10 according to the first embodiment.
  • the relationship verification module 300 receives measurement data such as LPRM to be monitored (S101).
  • the measurement data input at this time can monitor the current reactor state by using a real-time measurement data group.
  • measurement data collected in the past in an arbitrary section is used, information that can be used for grasping events in the reactor that have occurred in the section can be obtained.
  • information that can be used for verification of the movable test can be obtained.
  • the relationship verification module 300 identifies the received sensor value group and models it as a relationship model (S102). In parallel, the relationship verification module 300 acquires the pressure vessel in-sensor known relationship model recorded in the relationship model database 200 (S103). Next, the relationship verification module 300 performs a comparative analysis process on the generated relationship model and the acquired pressure vessel sensor known relationship model to calculate a value indicating the relationship breakage, and the relationship is broken. It is determined whether or not there is (S104). The relationship verification module 300 notifies a predetermined control panel or the like as a notification event when the relationship collapse occurs (S105). What is necessary is just to comprise so that a warning, an investigation request, etc. may be automatically emitted when it is used for monitoring of the present reactor state.
  • FIG. 3 is a block diagram showing the control rod monitoring system 20 of the second embodiment.
  • the control rod monitoring system 20 is additionally provided with a sensor distribution database 400 and a control rod position detection module 500.
  • the sensor distribution database 400 stores known sensor distribution position information indicating physical position coordinates of the individual LPRMs 101 to 10n (or individual LPRM detectors when more accurately obtained).
  • This sensor distribution position information indicates which sensor is physically located at which position in the reactor pressure containment vessel, and two-dimensional information (three-dimensional when more accurately obtained) included.
  • the control rod position detection module 500 is configured so that, when the relationship breakdown is output by the relationship verification module 300, the relationship mismatch (information such as the sensor number that has been mismatched) and the known sensor appearing in the relationship breakdown.
  • the control rod that causes the relationship collapse that appears in the collapse method is specified based on the distribution of LPRM or the like included in the collapse. This process is deeply related to the internal structure in the nuclear reactor, and cannot be determined simply as a control rod at the center position of the LPRM group included in the collapse.
  • FIG. 4 is a flowchart illustrating the processing operation of the control rod monitoring system 20 of the second embodiment.
  • the operation up to S104 is the same as the processing operation of the first embodiment.
  • the control rod position detection module 500 identifies that the relationship breakdown has occurred (S205).
  • the control rod position detection module 500 identifies LPRMs (LPRM detectors for more accurate execution) related to the collapse of the relationship (S206).
  • LPRMs LPRM detectors for more accurate execution
  • the control rod position detection module 500 selects a pattern similar to the relationship collapse pattern from the relationship model database 200, and determines the movement of the control rod found from the selected pattern (S207).
  • the determined control rod position is presented together with a visible drawing included in the sensor distribution database 400, or the control rod number is notified to other systems. In the extraction of the similar pattern, it is desirable to search for a matching pattern including the time axis.
  • FIG. 5 is a flowchart illustrating another processing operation of the control rod monitoring system 20 of the second embodiment. As shown in the figure, when it is identified that a relationship breakdown has occurred (S205), the control rod position detection module 500 is included in each LPRM together with the identification (S208) of the LPRM related to the relationship breakdown.
  • the number of sensors such as LPRM detectors related to the broken relationship is added (S209).
  • the control rod position detection module 500 performs ordering by comparing the magnitudes of the relationship breakdowns for each LPRM related to the added relationship breakdown (S210), and identifies the control rods that have moved from the pattern reflecting the ordering. (S211).
  • the control rod can be specified by mainly handling the position of LPRM or the like having a larger number of collapses than a transitional change has occurred.
  • the control rod that has been operated is specified when the broken relationship is output.
  • the control rod that is considered to have moved constantly may be monitored. When used to monitor the current reactor status, it can notify the control rods that are considered to have moved, along with warnings and survey requests.
  • FIG. 6 is a block diagram showing a control rod monitoring system 30 of the third embodiment.
  • the control rod monitoring system 30 is additionally provided with an averaging processing module 600. Further, the control rod monitoring system 30 acquires measured values of various sensors from the pressure vessel outside sensor group 700. In this embodiment, a correlation model is used as the relationship model.
  • the averaging processing module 600 averages individual observation data obtained from the LPRM detector 111 to 1 nm. In the averaging process, the observation data immediately before may be used in consideration of the time series change.
  • the relationship verification module 300 uses the data from which the noise has been removed by the averaging processing module 600 to model the measurement values of the LPRM detectors 111 to 1 nm to be monitored, and the correlation model as a relationship model for the monitoring target. Is generated.
  • the relationship verification module 300 acquires the in-pressure vessel sensor known correlation model recorded in the relationship model database 200, and compares the generated correlation model of the monitoring target with the in-pressure vessel sensor known relationship model.
  • the measurement values obtained from the pressure vessel outside sensor group 700 may be added and the accuracy of the relationship analysis or the correlation analysis may be performed more precisely.
  • the relationship verification module 300 extracts a mismatched portion of the correlation found by comparing the correlation models, and calculates whether or not there is a correlation failure.
  • the control rod position detection module 500 refers to the correlation mismatch point that appears in the correlation breakage and the known sensor distribution position information when the correlation breakage is output.
  • the control rod is identified based on the distribution of LPRM detectors and the like included in the collapse.
  • FIG. 7 is a flowchart illustrating the processing operation of the control rod monitoring system 30 according to the third embodiment. As shown in the figure, if the processing is performed in the same manner as in the first and second embodiments except that the preprocessing is performed and the correlation model is used, FIG. 7 corresponds to FIG. However, the invariant relationship analysis processing shown in FIG. 4 may be performed.
  • a control rod that is considered to have moved is notified along with an alarm or survey request. it can.
  • operations and phenomena captured by other sensors can be associated with movements of individual control rods based on the time axis.
  • the state of the control rod can be identified from both the information obtained from the existing control rod position monitoring device and the information obtained from the sensor in the furnace.
  • the moved control rod can be identified with higher accuracy from the measurement value obtained from LPRM or the like.
  • FIG. 8 is an explanatory diagram showing a power plant facility including a control rod monitoring system according to the present invention.
  • the power plant equipment includes a reactor vessel, a number of LPRM groups installed in the reactor vessel, a plurality of control rods, a core (fuel assembly), and a monitor that collects sensor values. It includes a device and a measured value storage database that accumulates and stores a number of collected sensor values.
  • the power plant equipment is provided with a relationship model generation device together with the control rod monitoring system according to the present invention.
  • the monitoring device collects measurement values from the in-reactor sensors including the LPRM group in association with time and accumulates them in the measurement value storage database. Measurement values (current observation data) as shown in FIG. 9 are collected from the individual LPRM detectors. The monitoring device collects the measurement values of each sensor in association with time. As illustrated in FIG. 10, the relationship model generation apparatus acquires measurement values (previous observation data) in a predetermined section from a measurement value storage database, and derives and models the relationship between the acquired measurement values. .
  • a relationship model representing the in-furnace situation is generated in advance.
  • the relationship model generated by this processing is recorded in the relationship storage database. If the relationship model is the brute force correlation of various sensors in the pressure vessel, a large number of parameters can be acquired as values indicating the correlation.
  • the relevance may be indicated by a prediction formula (formula) or may be indicated by a list table showing the relevance.
  • the prediction formula here may indicate each interrelationship as a function.
  • the list table may show the mutual relationships that have occurred between the measured values in association with the individual sensors in the descending order of correlation.
  • control rod monitoring system may perform comparison, comparison between models as described in the above embodiments, and perform monitoring, verification, notification, notification, etc. based on the number of broken relationships.
  • correlation fluctuations are learned in advance, and the allowable correlation fluctuations such as normal are defined as criteria, and then the current relationship model obtained from real-time measurement data and the past
  • the control rod monitoring system counts the number of difference points by associating the known relationship model in the pressure vessel and the list table data of the current relationship model with each other.
  • the control rod monitoring system may use, as a list table, data arranged in association with individual LPRM detectors in descending order of correlation between the individual LPRM detectors.
  • the number of difference points is aggregated by associating the list table data of the known relationship model with the current relationship model, and based on the threshold for the number of difference points or the threshold for increasing or decreasing the number of difference points.
  • the control rod monitoring system outputs the moved control rod, its current position, displacement, and the like.
  • FIG. 11 is an explanatory diagram of an example of a display interface that graphs the collapse of relevance regarding the LPRM group in the pressure vessel.
  • This data is an interface used for the verification of the movable test of the control rod using the measurement data collected and accumulated in the past.
  • the brute force correlation of the LPRM detectors (4 each) included in the 31 LPRMs is used.
  • the control rod is moved from 33 minutes to 2 minutes and from 58 minutes to 1 minute by the movable test.
  • the number of disruptions in the relationship between the relationship model of the operation state generated at this time and the relationship model generated in real time from the measurement data is counted. As shown in the graph, the relationship between the models collapses during the movement, and the collapse disappears after the movement.
  • a control rod monitoring program is developed in the RAM, and each unit is realized as various means by operating hardware such as a control unit (CPU) based on the program.
  • the program may be recorded in a fixed manner on a storage medium and distributed.
  • the program recorded on the recording medium is read into a memory via a wired, wireless, or recording medium itself, and operates a control unit or the like.
  • the recording medium examples include an optical disk, a magnetic disk, a semiconductor memory device, and a hard disk.
  • the information processing apparatus operating as the control rod monitoring system is based on the service reorganization evaluation program developed in the RAM, the relationship verification means, the control rod position detection means, etc. Can be realized by operating the control unit.
  • the information processing apparatus to which the present invention is applied determines the correctness of the position change of the control rod, the moved control rod, and the moved control rod position from the measured values obtained from the sensors in the pressure vessel. Can provide control rod monitoring system to identify.

Abstract

La présente invention porte sur un système de surveillance de barre de commande ayant disposé dans celui-ci : une base de données de modèle de relation stockant des modèles de relation connus de capteur interne de récipient sous pression indiquant les relations mutuelles entre des valeurs de sortie pour des moyens de capteur de mesure de rayon neutronique individuels, pour une pluralité de moyens de capteur de mesure de rayon neutronique disposés à l'intérieur d'un récipient sous pression de réacteur nucléaire ; et un moyen de vérification de relation qui compare les modèles de relation connus de capteur interne de récipient sous pression stockés dans la base de données de modèle de relation et un modèle de relation trouvé à partir de valeurs de mesure, étant la cible de surveillance, obtenues à partir de la pluralité de moyens de capteur de mesure de rayon neutronique, surveille un affaissement de relation à l'aide du nombre de positions d'inadéquation de relation en tant que référence pour celui-ci, et extrait un nombre prescrit d'affaissements de relation en tant qu'événements de notification.
PCT/JP2013/082306 2012-12-14 2013-11-25 Système de surveillance de barre de commande et procédé de surveillance de barre de commande WO2014091955A1 (fr)

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JP2012-273451 2012-12-14

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JP2017021702A (ja) * 2015-07-14 2017-01-26 中国電力株式会社 故障予兆監視方法
JP2020201765A (ja) * 2019-06-11 2020-12-17 中国電力株式会社 プラント監視システムおよびプラント監視方法
JP7471985B2 (ja) 2020-10-01 2024-04-22 株式会社東芝 制御盤

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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2017021702A (ja) * 2015-07-14 2017-01-26 中国電力株式会社 故障予兆監視方法
JP2020201765A (ja) * 2019-06-11 2020-12-17 中国電力株式会社 プラント監視システムおよびプラント監視方法
JP7358791B2 (ja) 2019-06-11 2023-10-11 中国電力株式会社 プラント監視システムおよびプラント監視方法
JP7471985B2 (ja) 2020-10-01 2024-04-22 株式会社東芝 制御盤

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