JPH04235390A - Abnormality diagonostic device for nuclear plant piping systems - Google Patents

Abnormality diagonostic device for nuclear plant piping systems

Info

Publication number
JPH04235390A
JPH04235390A JP3001438A JP143891A JPH04235390A JP H04235390 A JPH04235390 A JP H04235390A JP 3001438 A JP3001438 A JP 3001438A JP 143891 A JP143891 A JP 143891A JP H04235390 A JPH04235390 A JP H04235390A
Authority
JP
Japan
Prior art keywords
signal
nuclear power
apparatuses
power plant
valves
Prior art date
Legal status (The legal status 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 status listed.)
Pending
Application number
JP3001438A
Other languages
Japanese (ja)
Inventor
Noboru Saito
登 斎藤
Hiroshi Miyano
宮野 廣
Yukio Watabe
幸夫 渡部
Katsuhiko Naruse
成瀬 克彦
Hideaki Takahashi
秀明 高橋
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP3001438A priority Critical patent/JPH04235390A/en
Publication of JPH04235390A publication Critical patent/JPH04235390A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Indication Of The Valve Opening Or Closing Status (AREA)
  • Emergency Alarm Devices (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Testing And Monitoring For Control Systems (AREA)

Abstract

PURPOSE:To detect abnormal symptoms of apparatuses such as valves and pipings hear the apparatuses, which are attached to piping systems of a nuclear power plant. CONSTITUTION:Apparatuses 19 such as valves, having driving mechanism 24 thereof, are attached to pipings 20 of a nuclear power plant. Also, sensors 25 such as acceleration sensors or sonic sensors are attached to the apparatuses 19 or pipings 20 near the equipments 19. A signal judgment device 36 is provided for processing signal of the sensors 25. The signal judgment device 36 is so designed as to select electrical signal representing acceleration or sound with a specific frequency range by a filter 33, to counts the number of the signals exceeding a limiting valve per unit time using a counter 35 through a comparator 34, and to generate an alarm when the preset number is exceeded. In this way, operating conditions of the apparatuses such as valves under normal operation of the nuclear power plant can be accurately monitored.

Description

【発明の詳細な説明】[Detailed description of the invention]

【0001】[発明の目的][Object of the invention]

【0002】0002

【産業上の利用分野】本発明は原子力プラントの配管系
に取着された弁等の機器またはその機器近傍の配管の異
常発生兆候を検出するための原子力プラントの配管系の
異常診断装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an abnormality diagnosis apparatus for a piping system of a nuclear power plant for detecting signs of abnormality in equipment such as valves attached to the piping system of a nuclear power plant or piping in the vicinity of the equipment.

【0003】0003

【従来の技術】沸騰水型原子力発電プラントにおいて原
子炉の定常運転中、常時作動している主な配管系統を図
6に概略的に示す。なお、これらの配管系は原子炉格納
容器5内に格納されているものである。
2. Description of the Related Art FIG. 6 schematically shows the main piping systems that are constantly in operation during steady operation of a nuclear reactor in a boiling water nuclear power plant. Note that these piping systems are stored within the reactor containment vessel 5.

【0004】原子炉の出力は原子炉圧力容器1内の炉心
2を流れる炉水の流量で主に制御している。再循環ルー
プ系は原子炉圧力容器1に取り付けられた再循環ループ
3と再循環ポンプ4からなり原子炉圧力容器1内の流れ
を起こしている。また、原子炉圧力容器1内で発生した
蒸気は主蒸気管6を通りタービン7へ、タービン7から
復水器8に流れ、その後復水器8で蒸気から水に戻り給
水ポンプ9、給水管10を経由して原子炉圧力容器1へ
戻る。原子炉圧力容器1内を流れる水の浄化系は再循環
ループ3から分岐し脱塩ポンプ12,濾過脱塩器11を
経由して給水管10に合流する。
[0004] The output of a nuclear reactor is mainly controlled by the flow rate of reactor water flowing through a reactor core 2 within a reactor pressure vessel 1 . The recirculation loop system includes a recirculation loop 3 attached to the reactor pressure vessel 1 and a recirculation pump 4, and generates a flow within the reactor pressure vessel 1. In addition, the steam generated in the reactor pressure vessel 1 flows through the main steam pipe 6 to the turbine 7, from the turbine 7 to the condenser 8, and then returns from steam to water in the condenser 8, passing through the water supply pump 9 and the water supply pipe. 10 to return to the reactor pressure vessel 1. A purification system for water flowing inside the reactor pressure vessel 1 branches off from the recirculation loop 3, passes through a desalination pump 12, a filtration desalination device 11, and joins a water supply pipe 10.

【0005】これらの配管系には配管内の流動を駆動す
るためのポンプ、流量を制御するための流量制御弁、万
一の事故時の炉水流出を防ぐ隔離弁等の機器が数多く存
在する。従来の原子炉ではこれらの配管内で駆動部を有
する機器の常時異常監視機構としては、再循環ポンプ4
のモータ頂部に加速度計を取り付け、その信号からモー
タの振動振幅を求め制限値を超えると警告が発せられる
ように設定されている。また、弁の作動においては通常
、異常の監視は行っておらず、一部の弁では毎年の定期
検査時に分解点検,作動確認を行っている。
[0005] These piping systems include many devices such as pumps to drive the flow in the piping, flow control valves to control the flow rate, and isolation valves to prevent reactor water from flowing out in the event of an accident. . In conventional nuclear reactors, the recirculation pump 4 is used as a constant abnormality monitoring mechanism for devices with drive parts in these pipings.
An accelerometer is attached to the top of the motor, and the vibration amplitude of the motor is determined from the signal, and the system is set to issue a warning if the vibration amplitude exceeds a limit value. In addition, normal valve operation is not monitored for abnormalities, and some valves are overhauled and checked for operation during annual inspections.

【0006】[0006]

【発明が解決しようとする課題】しかしながら、配管内
の流れの中に何等かの駆動部分が曝されると必ず配管内
の流動を駆動するポンプによる圧力脈動、配管系統の流
路構造に起因する流れの乱れ、駆動部の後流に発生する
カルマン渦及び流れの剥離による力の影響を受け振動が
生じる。この振動が大きくなると弁体と弁箱との接合部
に損傷を与え、弁体が駆動し難くなる。最悪の場合は弁
体が作動しなくなり、弁棒が破損する等の課題がある。
[Problem to be Solved by the Invention] However, when any driving part is exposed to the flow in the piping, pressure pulsations caused by the pump that drives the flow in the piping and due to the flow path structure of the piping system occur. Vibration occurs due to the influence of force due to flow turbulence, Karman vortices generated in the wake of the drive unit, and flow separation. When this vibration becomes large, it damages the joint between the valve body and the valve body, making it difficult to drive the valve body. In the worst case, the valve body may stop working and the valve stem may be damaged.

【0007】本発明は上記課題を解決するためになされ
たもので、原子力プラントの配管系に駆動部を有する弁
等の機器にセンサを取り付け、そのセンサの信号を処理
することにより通常運転時の弁等の状況を監視でき、且
つ制限値を超える状態になった場合は警告を発しさせ、
原子炉の通常運転中の安全性の向上を図ると共に、定期
検査時の不必要な分解点検を防ぎ、以て作業の効率化及
び経済性の向上を図ることができる原子力プラントの配
管系の異常診断装置を提供することにある。 [発明の構成]
The present invention has been made to solve the above-mentioned problems, and by attaching a sensor to equipment such as a valve having a driving part in the piping system of a nuclear power plant, and processing the signal of the sensor, It can monitor the status of valves, etc., and issue a warning if the limit value is exceeded.
Abnormalities in the piping system of nuclear power plants that can improve safety during normal operation of the nuclear reactor, prevent unnecessary overhaul during periodic inspections, and improve work efficiency and economic efficiency. The objective is to provide diagnostic equipment. [Structure of the invention]

【0008】[0008]

【課題を解決するための手段】本発明は原子力プラント
の配管系に取着された駆動部を有する弁等の機器または
その機器近傍の配管に加速度センサまたは音響センサを
取着し、このセンサ信号を処理する信号判断装置を設け
てなり、前記信号判断装置は加速度または音の電気信号
をフィルタで特定の周波数範囲を選定し、単位時間当り
の制限値を超える回数をカウンタでカウントし、設定回
数を超えると警告を発するように構成されていることを
特徴とする。
[Means for Solving the Problems] The present invention attaches an acceleration sensor or an acoustic sensor to equipment such as a valve having a driving part attached to the piping system of a nuclear power plant or to piping in the vicinity of the equipment. The signal determining device selects a specific frequency range by filtering the electric signal of acceleration or sound, counts the number of times the limit value is exceeded per unit time with a counter, and calculates the set number of times. It is characterized in that it is configured to issue a warning when the limit is exceeded.

【0009】[0009]

【作用】原子力プラントの配管系に弁等の駆動部を有す
る機器に常時センサ,信号処理,判断機構を稼働させる
ことにより通常運転時の弁等の状況を監視する。また、
信号処理系に信号判断機能を持たせ制限値を超える状態
になった場合は警告を発しさせる。原子炉の通常運転中
の安全性の向上を図ると共に、定期検査時の不必要な分
解点検を防ぎ作業の効率化,経済性の向上を図ることが
できる。
[Operation] The status of valves, etc. during normal operation is monitored by constantly operating sensors, signal processing, and judgment mechanisms on devices that have driving parts such as valves in the piping system of nuclear power plants. Also,
The signal processing system is equipped with a signal judgment function to issue a warning if the limit value is exceeded. In addition to improving safety during normal operation of a nuclear reactor, it is possible to prevent unnecessary disassembly and inspection during periodic inspections, thereby improving work efficiency and economic efficiency.

【0010】0010

【実施例】本発明に係る原子力プラントの配管系の異常
診断装置の第1から第3の実施例について図面を参照し
て説明する。
DESCRIPTION OF THE PREFERRED EMBODIMENTS First to third embodiments of the apparatus for diagnosing abnormalities in piping systems of nuclear power plants according to the present invention will be described with reference to the drawings.

【0011】図1は本発明に係る原子力プラントの配管
系に取着されている弁等の機器の異常診断装置の第1の
実施例を示す概略フロー図である。このフロー図は機器
の1例として弁の場合を記載している。
FIG. 1 is a schematic flow diagram showing a first embodiment of an abnormality diagnosis apparatus for equipment such as valves attached to a piping system of a nuclear power plant according to the present invention. This flow diagram describes the case of a valve as an example of a device.

【0012】図1中、符号20は原子力プラントの配管
系の配管であり、その配管20に弁体21,弁棒22,
弁箱23,弁体を駆動する機構24からなる弁が機器1
9として設置されている。弁近傍の配管20の表面及び
弁箱23の表面に加速度または音を捕える複数個のセン
サ25が固定されており、センサ25からの信号は増幅
器26に連結されている。 増幅器26の出力は並行にデータレコーダ等の記録器2
7,時刻歴波形表示器28,音響増幅器29及びスピー
カ30,周波数分析器31とその出力の表示器32,フ
ィルタ33,比較器34及びカウンタ35からなる信号
判断装置36に繋がっている。時刻歴波形表示は一般的
に加速度信号を表示し、運転時の弁体の挙動を監視する
ものである。一般的に正常運転時の時刻歴波形は図2に
示すような形状を呈しており、異常時には衝撃加速度も
捕えられるため図3に示すような形状となる。また、音
響増幅器29を介して信号処理しスピーカ30で出力し
た場合も同様に異常時には衝撃音,摺動音が聞き取れ弁
体の挙動が監視される。周波数分析器31及びその出力
表示器では正常時及び異常時の加速度及び音の周波数特
性を確認し、信号判断装置36のフィルタ33の周波数
帯域の検討を行うものである。信号判断装置36では、
フィルタ33によって異常兆候を的確に捕えることがで
きる周波数帯域の信号のみを弁別し、比較器34では設
定値が設けられており、設定値以上の信号が入力される
と出力され後段のカウンタ35に信号が送られる。カウ
ンタ35では単位時間当りの信号の回数をカウント,表
示し回数設定値を超えると警告が発せられるようになっ
ている。
In FIG. 1, reference numeral 20 indicates a piping system of a nuclear power plant, and the piping 20 has a valve body 21, a valve rod 22,
The device 1 is a valve consisting of a valve box 23 and a mechanism 24 that drives the valve body.
It is set as 9. A plurality of sensors 25 that capture acceleration or sound are fixed on the surface of the pipe 20 and the surface of the valve box 23 near the valve, and signals from the sensors 25 are connected to an amplifier 26. The output of the amplifier 26 is sent to a recorder 2 such as a data recorder in parallel.
7, connected to a signal judgment device 36 consisting of a time history waveform display 28, an acoustic amplifier 29 and a speaker 30, a frequency analyzer 31 and its output display 32, a filter 33, a comparator 34 and a counter 35. The time history waveform display generally displays an acceleration signal and monitors the behavior of the valve body during operation. Generally, the time history waveform during normal operation has a shape as shown in FIG. 2, and when an abnormality occurs, since impact acceleration is also captured, the time history waveform has a shape as shown in FIG. 3. Similarly, when the signal is processed through the acoustic amplifier 29 and outputted from the speaker 30, impact sounds and sliding sounds can be heard in the event of an abnormality, and the behavior of the valve body can be monitored. The frequency analyzer 31 and its output display are used to check the frequency characteristics of acceleration and sound during normal and abnormal conditions, and to examine the frequency band of the filter 33 of the signal judgment device 36. In the signal judgment device 36,
The filter 33 discriminates only signals in a frequency band that can accurately capture abnormal signs, and the comparator 34 is provided with a set value, and when a signal exceeding the set value is input, it is output to the counter 35 at the subsequent stage. A signal is sent. The counter 35 counts and displays the number of signals per unit time, and if the number of times exceeds a set value, a warning is issued.

【0013】次に図4によって第2の実施例を説明する
。なお、図中図1と同一部分には同一符号を付し重複す
る部分の説明は省略する。
Next, a second embodiment will be explained with reference to FIG. Note that the same parts in the figure as in FIG. 1 are denoted by the same reference numerals, and the explanation of the overlapping parts will be omitted.

【0014】図4のフロー図を示すように、センサの第
1段増幅信号によって信号判断装置の入力とするのでは
なく、再度音響増幅器によって増幅された信号を信号判
断装置の入力とする。装置の基本動作は前記実施例と同
様である。
As shown in the flowchart of FIG. 4, instead of inputting the first stage amplified signal of the sensor to the signal determining device, the signal amplified by the acoustic amplifier again is input to the signal determining device. The basic operation of the device is the same as in the previous embodiment.

【0015】次に図5によって本発明の第3の実施例を
説明する。
Next, a third embodiment of the present invention will be explained with reference to FIG.

【0016】図5には特定のフィルタ33を通した後、
信号を信号判断装置36aに入力する例を示している。 この時、衝撃や摺動の現象のみが音響増幅器29を通し
てスピーカ30へ、また直接比較器34に入力されカウ
ンタ35でカウントされている。この実施例によれば現
象が容易に判断される効果がある。
FIG. 5 shows that after passing through a specific filter 33,
An example is shown in which a signal is input to the signal determining device 36a. At this time, only the impact and sliding phenomena are input to the speaker 30 through the acoustic amplifier 29 and directly to the comparator 34, and are counted by the counter 35. This embodiment has the effect that the phenomenon can be easily determined.

【0017】[0017]

【発明の効果】本発明によれば原子炉内の弁等の配管系
に駆動部を有する機構に常時センサ,信号処理,判断機
構を稼働させることにより通常運転時の弁等の機器の状
況を監視できる。また、信号処理系に信号判断機能を持
たせ制限値を超える状態になった場合には警告を発しさ
せ、原子炉の通常運転中の安全性の向上を図ると共に、
定期検査時の不必要な分解点検を防ぎ作業の効率化,経
済性の向上を図ることができる。
[Effects of the Invention] According to the present invention, the status of equipment such as valves during normal operation can be monitored by constantly operating sensors, signal processing, and judgment mechanisms in a mechanism that has a driving part in a piping system such as valves in a nuclear reactor. Can be monitored. In addition, the signal processing system is equipped with a signal judgment function to issue a warning when the limit value is exceeded, improving safety during normal operation of the reactor.
It is possible to prevent unnecessary disassembly and inspection during periodic inspections, improving work efficiency and economic efficiency.

【図面の簡単な説明】[Brief explanation of the drawing]

【図1】本発明に係る原子力プラントの配管系の異常診
断装置の第1の実施例を示すフロー図。
FIG. 1 is a flow diagram showing a first embodiment of an abnormality diagnosis device for a piping system of a nuclear power plant according to the present invention.

【図2】図1における正常時の信号を示す時刻歴波形図
FIG. 2 is a time history waveform diagram showing normal signals in FIG. 1;

【図3】図2における異常時の信号を示す時刻歴波形図
FIG. 3 is a time history waveform diagram showing signals at abnormal times in FIG. 2;

【図4】本発明の第2の実施例を示すフロー図。FIG. 4 is a flow diagram showing a second embodiment of the present invention.

【図5】本発明の第3の実施例を示すフロー図。FIG. 5 is a flow diagram showing a third embodiment of the present invention.

【図6】従来例を説明するための原子力プラントの主配
管系を示す系統図。
FIG. 6 is a system diagram showing a main piping system of a nuclear power plant to explain a conventional example.

【符号の説明】[Explanation of symbols]

19…機器、20…配管、21…弁体、22…弁棒、2
3…弁箱、24…駆動機構、25…センサ、26…増幅
器、27…記録器、28…波形表示器、29…音響増幅
器、30…スピーカ、31…周波数分析器、32…周波
数分布表示器、33…フィルタ、34…比較器、35…
カウンタ、36…信号判断装置。
19...Equipment, 20...Piping, 21...Valve body, 22...Valve stem, 2
3...Valve box, 24...Drive mechanism, 25...Sensor, 26...Amplifier, 27...Recorder, 28...Waveform display, 29...Acoustic amplifier, 30...Speaker, 31...Frequency analyzer, 32...Frequency distribution display , 33... Filter, 34... Comparator, 35...
Counter, 36...Signal judgment device.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】  原子力プラントの配管系に取着された
駆動部を有する弁等の機器またはその機器近傍の配管に
加速度センサまたは音響センサを取着し、このセンサ信
号を処理する信号判断装置を設けてなり、前記信号判断
装置は加速度または音の電気信号をフィルタで特定の周
波数範囲を選定し、単位時間当りの制限値を超える回数
をカウンタでカウントし、設定回数を超えると警告を発
するように構成されていることを特徴とする原子力プラ
ントの配管系の異常診断装置。
Claim 1: An acceleration sensor or an acoustic sensor is attached to a device such as a valve having a drive unit attached to a piping system of a nuclear power plant, or to piping near the device, and a signal judgment device that processes the sensor signal is provided. The signal determining device selects a specific frequency range by filtering the electric signal of acceleration or sound, counts the number of times the limit value is exceeded per unit time with a counter, and issues a warning when the set number of times is exceeded. An abnormality diagnosis device for a piping system of a nuclear power plant, characterized in that it is configured as follows.
JP3001438A 1991-01-10 1991-01-10 Abnormality diagonostic device for nuclear plant piping systems Pending JPH04235390A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3001438A JPH04235390A (en) 1991-01-10 1991-01-10 Abnormality diagonostic device for nuclear plant piping systems

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3001438A JPH04235390A (en) 1991-01-10 1991-01-10 Abnormality diagonostic device for nuclear plant piping systems

Publications (1)

Publication Number Publication Date
JPH04235390A true JPH04235390A (en) 1992-08-24

Family

ID=11501448

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3001438A Pending JPH04235390A (en) 1991-01-10 1991-01-10 Abnormality diagonostic device for nuclear plant piping systems

Country Status (1)

Country Link
JP (1) JPH04235390A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2001025662A3 (en) * 1999-09-30 2001-10-25 Siemens Ag Diagnostic system and method, especially for a valve
JP2015522821A (en) * 2012-06-27 2015-08-06 フィッシャー コントロールズ インターナショナル リミテッド ライアビリティー カンパニー Method and apparatus for using vibration data to determine the state of a process controller
JP2022038500A (en) * 2020-08-26 2022-03-10 日立Geニュークリア・エナジー株式会社 Abnormality sign diagnostic device and diagnosis method thereof

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2001025662A3 (en) * 1999-09-30 2001-10-25 Siemens Ag Diagnostic system and method, especially for a valve
US6637267B2 (en) 1999-09-30 2003-10-28 Siemens Aktiengesellschaft Diagnostic system and method, especially for a valve
JP2015522821A (en) * 2012-06-27 2015-08-06 フィッシャー コントロールズ インターナショナル リミテッド ライアビリティー カンパニー Method and apparatus for using vibration data to determine the state of a process controller
JP2022038500A (en) * 2020-08-26 2022-03-10 日立Geニュークリア・エナジー株式会社 Abnormality sign diagnostic device and diagnosis method thereof

Similar Documents

Publication Publication Date Title
KR100798006B1 (en) Integrated monitoring/diagnosis method for nuclear device and system using the same
US6480793B1 (en) Flow condition monitor
JPS609759Y2 (en) Online shock monitoring device for pressurized water reactors
CN102494894A (en) Audio monitoring and fault diagnosis system for wind generating set and audio monitoring and fault diagnosis method for same
JP3128832B2 (en) Plant diagnostic apparatus and plant diagnostic method
JPH05142033A (en) Monitoring device of plant equipment
US4570489A (en) Apparatus for detecting the evolution of an acoustic signal
CN202836861U (en) Analog quantity differential pressure transducer and blocking alarm system
JPH04235390A (en) Abnormality diagonostic device for nuclear plant piping systems
CN114485921A (en) Method and system for monitoring vibration of reactor equipment element
JP4658743B2 (en) Vibration monitoring system
KR102488613B1 (en) Monitoring and alarm system of biological life inflow prediction for plant
CN110533891A (en) Hydroenergy storage station water-turbine top cover spiral shell operating condition Realtime Alerts method and system
JPS58184542A (en) System for detecting acoustic abnormality
Gopal et al. Experiences with diagnostic instrumentation in nuclear power plants
Au-Yang Acoustic and ultrasonic signals as diagnostic tools for check valves
JPH01321397A (en) Monitor for loose parts
JP2003074307A (en) Turbine vibration monitoring device
RU2046407C1 (en) Safety system of pressure-tube reactor
JPH01302132A (en) Apparatus for detecting valve seat leak
US20230265871A1 (en) Detection of an anomaly in a fluid power system
JPH05172625A (en) Failure detection method in plant
JPS5868581A (en) Abnormality detector for fluid circuit
JPH02307023A (en) Equipment abnormal sound diagnostic system
Kim et al. An automatic diagnosis method for loose parts monitoring system