JPH11125688A - Reactor vibration monitor - Google Patents
Reactor vibration monitorInfo
- Publication number
- JPH11125688A JPH11125688A JP9291241A JP29124197A JPH11125688A JP H11125688 A JPH11125688 A JP H11125688A JP 9291241 A JP9291241 A JP 9291241A JP 29124197 A JP29124197 A JP 29124197A JP H11125688 A JPH11125688 A JP H11125688A
- Authority
- JP
- Japan
- Prior art keywords
- ultrasonic
- reactor
- pulse signal
- vibration
- signal
- 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.)
- Granted
Links
- 230000005540 biological transmission Effects 0.000 claims abstract description 8
- 238000012806 monitoring device Methods 0.000 claims description 18
- 238000012544 monitoring process Methods 0.000 claims description 8
- 238000004458 analytical method Methods 0.000 claims description 4
- 230000003111 delayed effect Effects 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 8
- 238000005259 measurement Methods 0.000 description 19
- 238000000034 method Methods 0.000 description 13
- 238000010586 diagram Methods 0.000 description 10
- 230000002093 peripheral effect Effects 0.000 description 6
- 230000004907 flux Effects 0.000 description 2
- 238000005070 sampling Methods 0.000 description 2
- 230000005856 abnormality Effects 0.000 description 1
- 230000001133 acceleration Effects 0.000 description 1
- 230000003321 amplification Effects 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 238000003199 nucleic acid amplification method Methods 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 230000000644 propagated effect Effects 0.000 description 1
- 230000002123 temporal effect Effects 0.000 description 1
- 238000001845 vibrational spectrum Methods 0.000 description 1
Classifications
-
- 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
Landscapes
- Measurement Of Mechanical Vibrations Or Ultrasonic Waves (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、原子炉などの圧力
容器内の構造物の振動を測定する原子炉振動監視装置に
関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor vibration monitoring device for measuring the vibration of a structure in a pressure vessel such as a nuclear reactor.
【０００２】[0002]
【従来の技術】一般に、原子炉における炉内構造物の振
動を測定するには、測定対象となる機器、例えばジェッ
トポンプ，ジェットポンプ計装配管などに加速度計を取
り付けて直接振動を計測したり、炉外に加速度計を取り
付けて、その加速度計の出力信号に基づいて炉内の振動
振幅や振動周波数の推定を行っている。2. Description of the Related Art In general, in order to measure the vibration of a reactor internal structure in a nuclear reactor, an accelerometer is attached to a device to be measured, such as a jet pump or a jet pump instrumentation pipe, and the vibration is directly measured. In addition, an accelerometer is attached outside the furnace, and a vibration amplitude and a vibration frequency in the furnace are estimated based on an output signal of the accelerometer.
【０００３】また、従来では、炉内に設置された中性子
束検出器の出力信号の揺らぎから間接的に炉内構造物の
振動を推定する方法が採用されている。[0003] Conventionally, a method of indirectly estimating the vibration of the furnace internal structure from the fluctuation of the output signal of the neutron flux detector installed in the furnace has been adopted.
【０００４】[0004]
【発明が解決しようとする課題】しかしながら、上述し
た従来の技術において、加速度計により直接振動を計測
する場合には、測定対象となる機器、例えばジェットポ
ンプ，ジェットポンプ計装配管に直接加速度計を取り付
ける必要があり、測定箇所が多い場合には、加速度計の
数が多くなるばかりでなく、加速度計の出力信号を伝送
するケーブルの本数も多くなり、コスト高になるという
課題、また原子炉から信号を取り出すための信号ぺネト
レーション（信号取出口）でのケーブルの本数が増加す
るという課題があった。However, in the above-mentioned prior art, when the vibration is directly measured by the accelerometer, the accelerometer is directly mounted on a device to be measured, for example, a jet pump or a jet pump instrumentation pipe. If it is necessary to attach the sensor and there are many measurement points, not only the number of accelerometers will increase, but also the number of cables that transmit the output signals of the accelerometer will increase, which will increase the cost. There is a problem that the number of cables at a signal penetration (signal outlet) for extracting a signal increases.
【０００５】また、加速度計や中性子束検出器の出力信
号に基づいて炉外から振動を推定する方法は、間接的な
計測であるため、測定精度が低いという課題があった。Further, the method of estimating the vibration from outside the furnace based on the output signals of the accelerometer and the neutron flux detector has a problem that the measurement accuracy is low because it is an indirect measurement.
【０００６】本発明は上述した事情を考慮してなされた
もので、原子炉圧力容器の外側に超音波トランスジュー
サを設置して、加速度計およびケーブルの数量の削減を
図るとともに、炉内構造物の振動を直接計測可能な原子
炉振動監視装置を提供することを目的とする。The present invention has been made in view of the above-mentioned circumstances, and an ultrasonic transducer is installed outside a reactor pressure vessel to reduce the number of accelerometers and cables and to reduce the number of reactor internal structures. An object of the present invention is to provide a reactor vibration monitoring device capable of directly measuring vibration.
【０００７】[0007]
【課題を解決するための手段】上述した課題を解決する
ために、本発明の請求項１は、原子炉圧力容器の外面に
設置され超音波パルス信号の送受信が兼用可能な超音波
トランスジューサと、この超音波トランスジューサと電
気的に接続され前記超音波パルス信号を発生させる超音
波送信器と、前記超音波トランスジューサと電気的に接
続され前記超音波パルス信号を受信する超音波受信器
と、前記超音波トランスジューサからの超音波パルス信
号を前記原子炉圧力容器を通して原子炉内に入射させる
一方、この原子炉内の炉内構造物で反射した超音波パル
ス信号が再び前記原子炉圧力容器を通して前記超音波ト
ランスジューサを経て前記超音波受信器に受信される超
音波パルス信号を処理する信号処理装置と、この信号処
理装置により処理された前記炉内構造物の振動情報を表
示する表示装置とを備えたことを特徴とする。According to the present invention, there is provided an ultrasonic transducer installed on the outer surface of a reactor pressure vessel and capable of transmitting and receiving ultrasonic pulse signals. An ultrasonic transmitter that is electrically connected to the ultrasonic transducer and generates the ultrasonic pulse signal; an ultrasonic receiver that is electrically connected to the ultrasonic transducer and receives the ultrasonic pulse signal; The ultrasonic pulse signal from the ultrasonic transducer is made incident on the reactor through the reactor pressure vessel, and the ultrasonic pulse signal reflected by the internal structure of the reactor is again transmitted through the reactor pressure vessel. A signal processing device for processing an ultrasonic pulse signal received by the ultrasonic receiver via a transducer; and a signal processing device for processing the ultrasonic pulse signal. And characterized by comprising a display device for displaying the vibration information of the furnace structure.
【０００８】請求項２は、請求項１記載の原子炉振動監
視装置において、超音波パルス信号が無線周波数パルス
信号であることを特徴とする。A second aspect of the present invention is the reactor vibration monitoring apparatus according to the first aspect, wherein the ultrasonic pulse signal is a radio frequency pulse signal.
【０００９】請求項３は、請求項１記載の原子炉振動監
視装置において、超音波トランスジューサが１次元に複
数個配列され、信号処理装置は、これらの超音波トラン
スジューサの超音波の送信のタイミングを変化させると
ともに、受信される超音波パルス信号を時間的に遅延さ
せて加算して反射される超音波パルス信号を測定するこ
とを特徴とする。According to a third aspect of the present invention, in the reactor vibration monitoring apparatus according to the first aspect, a plurality of ultrasonic transducers are arranged one-dimensionally, and the signal processing device determines the transmission timing of the ultrasonic waves from these ultrasonic transducers. The method is characterized in that the ultrasonic pulse signal is reflected and the reflected ultrasonic pulse signal is measured by adding the received ultrasonic pulse signal while delaying the ultrasonic pulse signal in time.
【００１０】請求項４は、請求項１記載の原子炉振動監
視装置において、超音波トランスジューサが原子炉圧力
容器の外面に沿って移動可能に構成されたことを特徴と
する。A fourth aspect of the present invention is the reactor vibration monitoring device according to the first aspect, wherein the ultrasonic transducer is configured to be movable along the outer surface of the reactor pressure vessel.
【００１１】請求項５は、請求項１ないし４のいずれか
に記載の原子炉振動監視装置において、信号処理装置が
測定した信号の周波数分析を行って炉内構造物の固有振
動周波数を算出し、表示装置は前記固有振動周波数の変
化を表示することを特徴とする。According to a fifth aspect of the present invention, in the reactor vibration monitoring device according to any one of the first to fourth aspects, a frequency analysis of a signal measured by the signal processing device is performed to calculate a natural vibration frequency of the reactor internal structure. The display device displays the change of the natural vibration frequency.
【００１２】[0012]
【発明の実施の形態】以下、本発明の実施形態を図面に
基づいて説明する。Embodiments of the present invention will be described below with reference to the drawings.
【００１３】図１は本発明に係る原子炉振動監視装置の
第１実施形態を示す構成図である。図１に示すように、
本実施形態の超音波トランスジューサ１は、原子炉圧力
容器２の外周面に設置されているとともに、超音波パル
スの送受信が兼用可能である。また、超音波トランスジ
ューサ１は、ケーブル３によって原子炉格納容器４の信
号取出口４ａを経て原子炉格納容器４外（または原子炉
格納容器４内）に設置された超音波信号処理装置５に電
気的に接続されている。FIG. 1 is a configuration diagram showing a first embodiment of a reactor vibration monitoring device according to the present invention. As shown in FIG.
The ultrasonic transducer 1 of the present embodiment is installed on the outer peripheral surface of the reactor pressure vessel 2 and can also transmit and receive ultrasonic pulses. Further, the ultrasonic transducer 1 is electrically connected to the ultrasonic signal processing device 5 installed outside the reactor containment vessel 4 (or inside the reactor containment vessel 4) via the signal outlet 4a of the reactor containment vessel 4 by the cable 3. Connected.
【００１４】この超音波信号処理装置５は、超音波パル
ス信号を発生させるための超音波送信器６と、反射した
超音波パルス信号を受信する超音波受信器７と、この超
音波受信器７で受信した超音波パルス信号を処理する信
号処理装置８とから構成されている。そして、超音波信
号処理装置５は、表示装置９と電気的に接続され、この
表示装置９は超音波トランスジューサ１および超音波信
号処理装置５によって計測された振動波形や振動のスペ
クトルなどを表示する。The ultrasonic signal processing device 5 includes an ultrasonic transmitter 6 for generating an ultrasonic pulse signal, an ultrasonic receiver 7 for receiving a reflected ultrasonic pulse signal, and an ultrasonic receiver 7 for receiving the reflected ultrasonic pulse signal. And a signal processing device 8 for processing the ultrasonic pulse signal received at the step S1. The ultrasonic signal processing device 5 is electrically connected to the display device 9, and the display device 9 displays a vibration waveform, a vibration spectrum, and the like measured by the ultrasonic transducer 1 and the ultrasonic signal processing device 5. .
【００１５】次に、本実施形態の作用を図２〜図５に基
づいて説明する。Next, the operation of the present embodiment will be described with reference to FIGS.
【００１６】図２に示すように、本実施形態の超音波ト
ランスジューサ１に超音波送信器６から電気パルス信号
（ＤＣパルス信号）１０を加えると、超音波トランスジ
ューサ１内で電気パルス信号１０が超音波信号に変換さ
れ、原子炉圧力容器２内に超音波パルス信号１１が発生
する。As shown in FIG. 2, when an electric pulse signal (DC pulse signal) 10 is applied from the ultrasonic transmitter 6 to the ultrasonic transducer 1 of the present embodiment, the electric pulse signal 10 is superposed in the ultrasonic transducer 1. The ultrasonic pulse signal 11 is generated in the reactor pressure vessel 2 after being converted into an acoustic wave signal.
【００１７】この超音波パルス信号１１は、原子炉圧力
容器２内を伝搬し、炉水１２中に放射される。この炉水
１２中を伝搬した超音波パルス信号１３は、例えばジェ
ットポンプ，ジェットポンプ計装配管などの原子炉の炉
内構造物１４に当たって反射し、再び炉水１２，原子炉
圧力容器２内を伝搬して超音波トランスジューサ１に戻
ってくる。The ultrasonic pulse signal 11 propagates in the reactor pressure vessel 2 and is radiated into the reactor water 12. The ultrasonic pulse signal 13 propagated in the reactor water 12 strikes a reactor internal structure 14 such as a jet pump or a jet pump instrumentation pipe, and is reflected therefrom. The ultrasonic pulse signal 13 passes through the reactor water 12 and the reactor pressure vessel 2 again. The light propagates and returns to the ultrasonic transducer 1.
【００１８】この戻ってきた超音波パルス信号１５は、
超音波トランスジューサ１内で電気パルス信号に変換さ
れた後、超音波受信器７で信号の増幅およびフィルタリ
ングなどの信号処理が行われる。The returned ultrasonic pulse signal 15 is
After being converted into an electric pulse signal in the ultrasonic transducer 1, the ultrasonic receiver 7 performs signal processing such as signal amplification and filtering.
【００１９】さらに、超音波受信器７の信号は、例えば
マイクロコンピュータや周波数復調器（ＦΜ復調器、Ｆ
Μ：Frequency Modulation）で構成される信号処理装置
８で、ディジタル信号に変換され、その信号処理によっ
て振動情報が得られる。Further, the signal from the ultrasonic receiver 7 is output to, for example, a microcomputer or a frequency demodulator (FΜ demodulator, F
Μ: Frequency Modulation), the signal processing device 8 converts the signal into a digital signal, and the signal processing provides vibration information.
【００２０】そして、信号処理装置８により処理された
炉内構造物１４の振動情報が表示装置９に表示される。
すなわち、表示装置９では、このときの振動振幅波形１
６，振動の周波数応答や振動振幅、振動位相の変化傾向
（トレンド）が表示される。Then, the vibration information of the in-furnace structure 14 processed by the signal processing device 8 is displayed on the display device 9.
That is, in the display device 9, the vibration amplitude waveform 1
6. Changes in the frequency response, vibration amplitude, and vibration phase of the vibration (trend) are displayed.
【００２１】次に、図３に基づいて超音波パルス信号に
より振動を測定する方法を説明する。図３に示すよう
に、使用する超音波パルス信号１１は、ＤＣパルス信号
１０である。超音波トランスジューサ１から超音波パル
ス信号１１が原子炉圧力容器２を経由して炉水１２中に
放射される。この放射された超音波パルス信号１３は、
炉内構造物１４に当たって反射する。Next, a method of measuring vibration by an ultrasonic pulse signal will be described with reference to FIG. As shown in FIG. 3, the ultrasonic pulse signal 11 to be used is the DC pulse signal 10. An ultrasonic pulse signal 11 is emitted from the ultrasonic transducer 1 into the reactor water 12 via the reactor pressure vessel 2. The emitted ultrasonic pulse signal 13 is
The light impinges on the internal structure 14 and is reflected.
【００２２】この反射して戻ってきた超音波パルス信号
１５は、再び原子炉圧力容器２内を伝搬して超音波トラ
ンスジューサ１で検出される。この場合、図４に示すよ
うに、送信される超音波パルス信号１１と受信される超
音波パルス信号１５は、伝搬距離に応じて分離される。
次に、炉内構造物１４が振動している場合、受信された
超音波パルス信号１５の検出される時間は、炉内構造物
１４の振動振幅に比例して変動する。振動していないと
きの伝搬時間をＴ（秒）とすると、この伝搬時間Ｔは、
次のように表される。すなわち、The reflected ultrasonic pulse signal 15 propagates again in the reactor pressure vessel 2 and is detected by the ultrasonic transducer 1. In this case, as shown in FIG. 4, the transmitted ultrasonic pulse signal 11 and the received ultrasonic pulse signal 15 are separated according to the propagation distance.
Next, when the in-furnace structure 14 is vibrating, the time at which the received ultrasonic pulse signal 15 is detected fluctuates in proportion to the vibration amplitude of the in-furnace structure 14. Assuming that the propagation time when there is no vibration is T (second), this propagation time T is
It is expressed as follows. That is,
【数１】Ｔ＝２×（Ｄ／Ｖ1 ＋Ｌ／Ｖ2 ） …（１） ここで、Ｖ1 は原子炉圧力容器２の超音波の音速度、Ｖ
2 は炉水１２の超音波の音速度、Ｄは原子炉圧力容器２
の板厚、Ｌは原子炉圧力容器２と炉内構造物１４との間
の距離である。T = 2 × (D / V 1 + L / V 2 ) (1) where V 1 is the sound speed of the ultrasonic wave of the reactor pressure vessel 2,
2 is the sound speed of the ultrasonic wave of the reactor water 12, D is the reactor pressure vessel 2.
, L is the distance between the reactor pressure vessel 2 and the reactor internals 14.
【００２３】そして、炉内構造物１４が振動して、振動
振幅がΔＬの場合、Ｌは（Ｌ＋ΔＬ）になるので、超音
波の伝搬時間Ｔの変化分をΔｔとすると、When the furnace internal structure 14 vibrates and the vibration amplitude is ΔL, L becomes (L + ΔL). Therefore, if the change of the ultrasonic wave propagation time T is Δt,
【数２】 (Equation 2)
【数３】ΔＬ＝−２×Ｖ2 ×Δｔ …（３） のように求まることになる。したがって、信号処理装置
８で伝搬時間の変化分Δｔを測定すれば、振動振幅ΔＬ
を測定することができる。ΔL = −2 × V 2 × Δt (3) Therefore, if the signal processor 8 measures the change Δt in the propagation time, the vibration amplitude ΔL
Can be measured.
【００２４】また、超音波パルス信号を発生させる時間
間隔をＴｓ（秒）とすると、その時間間隔Ｔｓ（秒）毎
に離散的に振動振幅を測定することができるので、測定
結果は図５に示したような離散的な信号が得られる。サ
ンプリング定理を使用すれば、周波数ｆ（Ｈｚ）の振動
信号を再生するためには、超音波パルス信号を発生させ
る時間間隔Ｔｓ（秒）が（４）式のようになる。すなわ
ち、If the time interval for generating the ultrasonic pulse signal is Ts (seconds), the vibration amplitude can be measured discretely at each time interval Ts (seconds). A discrete signal as shown is obtained. If the sampling theorem is used, the time interval Ts (second) at which the ultrasonic pulse signal is generated in order to reproduce the vibration signal of the frequency f (Hz) is as shown in the following equation (4). That is,
【数４】ｆ＝１／（２×Ｔｓ） …（４） 例えば、１００Ηｚの振動振幅を再生するためには、２
００Ｈｚ（Ｔｓ＝５０ｍsec ）間隔で超音波を発生させ
ればよいことになる。F = 1 / (2 × Ts) (4) For example, to reproduce a vibration amplitude of 100 ° z, 2
Ultrasonic waves need only be generated at intervals of 00 Hz (Ts = 50 msec).
【００２５】このように本実施形態によれば、超音波ト
ランスジューサ１が原子炉圧力容器２の外周面に設置さ
れたことにより、従来のように炉内構造物１４に直接加
速度計を設置する必要がなくなる。そのため、原子炉圧
力容器２から信号を取り出すためのケーブルや信号取出
口が不要となる。その結果、ケーブル数を削減すること
が可能となり、安価な監視装置を提供することができ
る。As described above, according to the present embodiment, since the ultrasonic transducer 1 is installed on the outer peripheral surface of the reactor pressure vessel 2, it is necessary to install an accelerometer directly on the reactor internal structure 14 as in the related art. Disappears. Therefore, a cable and a signal outlet for extracting a signal from the reactor pressure vessel 2 are not required. As a result, the number of cables can be reduced, and an inexpensive monitoring device can be provided.
【００２６】図６は本発明に係る原子炉振動監視装置の
第２実施形態を示す構成図、図７（Ａ），（Ｂ）は第２
実施形態において送信ＲＦパルスと受信ＲＦパルスの時
間関係および周波数関係を示すタイミングチャートであ
る。なお、前記第１実施形態と同一の部分には同一の符
号を付して説明する。以下の各実施形態も同様である。FIG. 6 is a block diagram showing a second embodiment of the reactor vibration monitoring apparatus according to the present invention, and FIGS. 7A and 7B show the second embodiment.
5 is a timing chart showing a time relationship and a frequency relationship between a transmission RF pulse and a reception RF pulse in the embodiment. The same parts as those in the first embodiment will be described with the same reference numerals. The same applies to the following embodiments.
【００２７】第２実施形態では、超音波送信器６から発
生する超音波パルス信号として、図６および図７（Ａ）
に示すようなＲＦ（無線周波数）パルス信号１７が使用
される。すなわち、超音波トランスジューサ１に図７
（Ａ）に示すＲＦパルス信号１７を加えると、その結果
として発生する超音波パルス信号もＲＦパルス信号とな
る。この時のＲＦパルス信号の搬送波（キャリア）の周
波数をｆ（Ｈｚ）とする。このＲＦパルス信号１７が炉
水１２中を伝搬し、炉内構造物１４に当たって反射して
くると、再び超音波トランスジューサ１で受信される。In the second embodiment, as an ultrasonic pulse signal generated from the ultrasonic transmitter 6, FIGS.
An RF (radio frequency) pulse signal 17 as shown in FIG. That is, the ultrasonic transducer 1 shown in FIG.
When the RF pulse signal 17 shown in (A) is added, the resulting ultrasonic pulse signal also becomes an RF pulse signal. The frequency of the carrier of the RF pulse signal at this time is f (Hz). When this RF pulse signal 17 propagates in the reactor water 12 and hits the internal structure 14 of the furnace, and is reflected, it is received by the ultrasonic transducer 1 again.
【００２８】この受信されたＲＦパルス信号１８は、図
４に示すように送信される超音波パルス信号１１および
受信される超音波パルス信号１５と同様に、伝搬時間Ｔ
または（Ｔ＋Δｔ）の時間間隔で観測される。炉内構造
物１４の振動によって、反射するＲＦパルス信号１８は
ドップラシフトを起こすため、反射するＲＦパルス信号
１８の周波数は変化している。この場合の周波数変化量
をΔｆとすると、周波数変化量Δｆは、（５）式で計算
される。The received RF pulse signal 18 has a propagation time T like the transmitted ultrasonic pulse signal 11 and the received ultrasonic pulse signal 15 as shown in FIG.
Or it is observed at a time interval of (T + Δt). Since the reflected RF pulse signal 18 causes a Doppler shift due to the vibration of the in-furnace structure 14, the frequency of the reflected RF pulse signal 18 changes. Assuming that the amount of frequency change in this case is Δf, the amount of frequency change Δf is calculated by equation (5).
【００２９】[0029]
【数５】Δｆ＝２×ｖ×ｆ／Ｖ2 …（５） ここで、ｖ（ｍ／sec ）は、炉内構造物１４の振動速度
である。周波数変化量Δｆの測定方法は、例えば、信号
処理装置８内において、周波数復調回路を使用して測定
される。Δf = 2 × v × f / V 2 (5) where v (m / sec) is the vibration speed of the furnace internal structure 14. The method of measuring the frequency change Δf is measured, for example, in the signal processing device 8 using a frequency demodulation circuit.
【００３０】（５）式において、周波数変化量Δｆを測
定すれば、振動速度ｖ（ｍ／sec ）を逆算することがで
きる。この場合も振動速度は離散的に測定されるので、
図５に示した方法と同様に、測定値を信号処理装置８に
取り込み、サンプリング定理を利用して振動速度波形を
合成する。In the equation (5), if the frequency change Δf is measured, the vibration velocity v (m / sec) can be calculated backward. Also in this case, the vibration velocity is measured discretely,
Similar to the method shown in FIG. 5, the measured value is taken into the signal processing device 8, and the vibration velocity waveform is synthesized using the sampling theorem.
【００３１】このデータを利用することにより、振動振
幅波形１６や振動の加速度波形に変換され、これらが表
示装置９に表示される。By utilizing this data, it is converted into a vibration amplitude waveform 16 and a vibration acceleration waveform, which are displayed on the display device 9.
【００３２】このように本実施形態によれば、前記第１
実施形態で用いたＤＣパルス信号の代わりに、ＲＦパル
ス信号１６を使用したことにより、炉内構造物１４の振
動に伴って発生する超音波パルス信号のドップラシフト
を検出することができ、振動振幅および振動速度を同時
に測定することができ、測定精度を向上することができ
る。As described above, according to the present embodiment, the first
By using the RF pulse signal 16 instead of the DC pulse signal used in the embodiment, it is possible to detect the Doppler shift of the ultrasonic pulse signal generated with the vibration of the in-furnace structure 14, and to detect the vibration amplitude. And the vibration speed can be measured at the same time, and the measurement accuracy can be improved.
【００３３】図８は本発明に係る原子炉振動監視装置の
第３実施形態を示す構成図である。この第３実施形態で
は、図８に示すように複数個の超音波トランスジューサ
１ａ，１ｂ，１ｃ，１ｄ，１ｅ，…１ｎを原子炉圧力容
器２の外周面に対して１次元に配列し、信号処理装置８
によりこれらの超音波トランスジューサ１ａ，１ｂ，１
ｃ，１ｄ，１ｅ，…１ｎの超音波パルス信号１３ａ，１
３ｂ，１３ｃ，１３ｄ，１３ｅ，…１３ｎの送信タイミ
ングを変化させるとともに、受信される超音波パルス信
号１５ａ，１５ｂ，１５ｃ，１５ｄ，１５ｅ，…１５ｎ
を時間的に遅延させて加算して超音波反射パルスを測定
する。FIG. 8 is a block diagram showing a third embodiment of the reactor vibration monitoring apparatus according to the present invention. In the third embodiment, a plurality of ultrasonic transducers 1a, 1b, 1c, 1d, 1e,... 1n are one-dimensionally arranged on the outer peripheral surface of the reactor pressure vessel 2 as shown in FIG. Processing unit 8
, These ultrasonic transducers 1a, 1b, 1
The ultrasonic pulse signals 13a, 13 of c, 1d, 1e,.
.. 13n while changing the transmission timing of the ultrasonic pulse signals 15a, 15b, 15c, 15d, 15e,.
Are delayed in time and added to measure the ultrasonic reflected pulse.
【００３４】したがって、第３実施形態では、超音波ト
ランスジューサ１ａ，１ｂ，１ｃ，１ｄ，１ｅ，…１ｎ
を設置した各点での振動振幅または振動速度が測定する
ことができるので、振動分布を測定することができる。
この振動分布を信号処理装置８で処理して表示装置９に
表示することにより、監視員に分かり易い情報を提供す
ることができる。Therefore, in the third embodiment, the ultrasonic transducers 1a, 1b, 1c, 1d, 1e,.
Since the vibration amplitude or the vibration speed at each point where is installed can be measured, the vibration distribution can be measured.
By processing this vibration distribution by the signal processing device 8 and displaying it on the display device 9, it is possible to provide easy-to-understand information to the observer.
【００３５】このように第３実施形態によれば、複数個
の超音波トランスジューサ１ａ，１ｂ，１ｃ，１ｄ，１
ｅ，…１ｎの送信のタイミングを制御し、炉内に入射す
る超音波の伝搬方向を高速で制御することができるよう
になるので、測定対象物を高精度に選定することができ
るばかりでなく、炉内構造物１４の振動分布の位相も測
定可能となり、測定精度を向上させることができる。As described above, according to the third embodiment, a plurality of ultrasonic transducers 1a, 1b, 1c, 1d, 1
e,... 1n, so that the transmission direction of the ultrasonic wave incident into the furnace can be controlled at a high speed, so that not only can the measurement target be selected with high accuracy. Also, the phase of the vibration distribution of the furnace internal structure 14 can be measured, and the measurement accuracy can be improved.
【００３６】また、受信される超音波パルス信号１５
ａ，１５ｂ，１５ｃ，１５ｄ，１５ｅ，…１５ｎを時間
的に遅延させて加算するので、白色雑音は打ち消されて
減少し、信号は加算され大きくなるので、超音波信号の
ＳＮ比も向上し、測定精度を向上させることができる。The received ultrasonic pulse signal 15
a, 15b, 15c, 15d, 15e,... 15n are added with a time delay, the white noise is reduced by cancellation, and the signal is added and increased, so that the S / N ratio of the ultrasonic signal is also improved. Measurement accuracy can be improved.
【００３７】図９は本発明に係る原子炉振動監視装置の
第４実施形態を示す構成図である。この第４実施形態で
は、図９に示すように超音波トランスジューサ１が原子
炉圧力容器２の外周面に沿って移動可能に構成されてい
る。この超音波トランスジューサ１を移動させるには、
例えば原子炉圧力容器２の外周面にレールなどを敷設
し、このレールに沿って超音波トランスジューサ１を電
動または手動により移動させる。FIG. 9 is a block diagram showing a fourth embodiment of the reactor vibration monitoring apparatus according to the present invention. In the fourth embodiment, as shown in FIG. 9, the ultrasonic transducer 1 is configured to be movable along the outer peripheral surface of the reactor pressure vessel 2. To move the ultrasonic transducer 1,
For example, a rail or the like is laid on the outer peripheral surface of the reactor pressure vessel 2, and the ultrasonic transducer 1 is electrically or manually moved along the rail.
【００３８】このように第４実施形態によれば、超音波
トランスジューサ１を原子炉圧力容器２の外周面に沿っ
て移動可能に構成したことにより、超音波トランスジュ
ーサ１の移動した各点での振動振幅または振動速度を測
定することができるので、測定対象物を高精度に選定で
きるばかりでなく、炉内構造物１４の振動分布を測定す
ることができる。この振動分布を信号処理装置８により
処理して表示装置９で表示することによって、監視員に
分かりやすい情報を提供することができる。As described above, according to the fourth embodiment, since the ultrasonic transducer 1 is configured to be movable along the outer peripheral surface of the reactor pressure vessel 2, vibration at each point where the ultrasonic transducer 1 moves is described. Since the amplitude or the vibration speed can be measured, not only can the measurement target be selected with high accuracy, but also the vibration distribution of the furnace internal structure 14 can be measured. By processing this vibration distribution by the signal processing device 8 and displaying it on the display device 9, it is possible to provide easy-to-understand information to the observer.
【００３９】図１０（Ａ），（Ｂ）は本発明に係る原子
炉振動監視装置の第５実施形態において固有振動数の表
示方法を示す説明図，しきい値の設定方法を示す説明図
である。FIGS. 10A and 10B are an explanatory view showing a method of displaying a natural frequency and a method of setting a threshold value in a fifth embodiment of the reactor vibration monitoring apparatus according to the present invention. is there.
【００４０】この第５実施形態では、信号処理装置８内
で、測定した振動振幅，振動速度の信号の周波数分析を
行い、炉内構造物１４の固有振動数を算出して、この固
有振動数（Ｆ）１９ａの経時変化（ΔＦ）１９ｂのよう
に表示装置９に表示すれば、長期間の振動の変化を容易
に認識することができるので、炉内の振動異常を早期に
検出することができる。In the fifth embodiment, a frequency analysis of the measured vibration amplitude and vibration speed signals is performed in the signal processing device 8 to calculate a natural frequency of the furnace internal structure 14, and the natural frequency is calculated. (F) By displaying the change over time (ΔF) 19b of 19a on the display device 9, it is possible to easily recognize a change in vibration over a long period of time. it can.
【００４１】このように第５実施形態によれば、信号処
理装置８で図１０（Ａ）に示すように出力信号を周波数
分析を行い、表示装置９で図１０（Ｂ）に示すように炉
内構造物１４の固有振動周波数の経時変化を表示させる
ことにより、測定した振動信号に基づいて振動の変化傾
向（トレンド）を表示することができるので、振動異常
の把握が容易になり、炉内構造物１４の信頼性を向上さ
せることができる。As described above, according to the fifth embodiment, the signal processor 8 analyzes the frequency of the output signal as shown in FIG. 10A, and the display device 9 analyzes the frequency of the output signal as shown in FIG. By displaying the change over time of the natural vibration frequency of the internal structure 14, the change tendency (trend) of the vibration can be displayed based on the measured vibration signal. The reliability of the structure 14 can be improved.
【００４２】[0042]
【発明の効果】以上説明したように、本発明の請求項１
によれば、超音波トランスジューサが原子炉圧力容器の
外面に設置されたことにより、原子炉圧力容器の外側か
ら炉内構造物の振動を測定することができる。これによ
り、振動測定対象物の変更が容易となるばかりでなく、
測定の準備が容易となるため、作業工数を削減すること
ができる。また、原子炉圧力容器内にケーブルを設置す
る必要がないため、ケーブルの物量の削減が可能とな
る。As described above, according to the first aspect of the present invention,
According to the method, the vibration of the reactor internal structure can be measured from the outside of the reactor pressure vessel by installing the ultrasonic transducer on the outer surface of the reactor pressure vessel. This makes it easy to change the vibration measurement object,
Since the preparation for the measurement is facilitated, the number of work steps can be reduced. Further, since there is no need to install a cable in the reactor pressure vessel, the amount of cable can be reduced.
【００４３】請求項２によれば、請求項１記載の原子炉
振動監視装置において、超音波パルス信号が無線周波数
パルス信号であることから、炉内構造物の振動に伴って
発生する超音波パルス信号のドップラシフトを検出する
ことができ、振動振幅および振動速度を同時に測定する
ことができ、測定精度を向上することができる。According to the second aspect of the present invention, in the reactor vibration monitoring device according to the first aspect, since the ultrasonic pulse signal is a radio frequency pulse signal, the ultrasonic pulse generated due to the vibration of the internal structure of the reactor. The Doppler shift of the signal can be detected, the vibration amplitude and the vibration speed can be measured simultaneously, and the measurement accuracy can be improved.
【００４４】請求項３によれば、請求項１記載の原子炉
振動監視装置において、超音波トランスジューサが１次
元に複数個配列され、信号処理装置は、これらの超音波
トランスジューサの超音波の送信のタイミングを変化さ
せるとともに、受信される超音波パルス信号を時間的に
遅延させて加算して反射される超音波パルス信号を測定
することにより、複数個の超音波トランスジューサの送
信のタイミングを制御し、炉内に入射する超音波の伝搬
方向を高速で制御することができるようになるので、測
定対象物を高精度に選定できるばかりでなく、炉内構造
物の振動分布の位相も測定可能となり、測定精度を向上
させることができる。According to a third aspect of the present invention, in the reactor vibration monitoring device according to the first aspect, a plurality of ultrasonic transducers are arranged one-dimensionally, and the signal processing device transmits the ultrasonic waves from these ultrasonic transducers. By changing the timing, measuring the reflected ultrasonic pulse signal by adding and delaying the received ultrasonic pulse signal in time, controlling the transmission timing of the plurality of ultrasonic transducers, Since the direction of propagation of ultrasonic waves incident into the furnace can be controlled at high speed, not only can the measurement target be selected with high accuracy, but also the phase of the vibration distribution of the furnace internal structure can be measured. Measurement accuracy can be improved.
【００４５】また、受信される超音波パルス信号を時間
的に遅延させて加算するので、白色雑音は打ち消されて
減少し、信号は加算され大きくなるので、超音波信号の
ＳＮ比も向上し、測定精度の向上を図ることが可能とな
る。Further, since the received ultrasonic pulse signals are added with a time delay, the white noise is canceled and reduced, and the signals are added and increased, so that the S / N ratio of the ultrasonic signal is also improved. Measurement accuracy can be improved.
【００４６】請求項４によれば、超音波トランスジュー
サを原子炉圧力容器の外面に沿って移動させて振動測定
を行うので、測定対象物を高精度に選定できるばかりで
なく、炉内構造物の振動分布の測定も可能となり、測定
精度の向上を図ることが可能となる。According to the fourth aspect, since the vibration measurement is performed by moving the ultrasonic transducer along the outer surface of the reactor pressure vessel, not only the object to be measured can be selected with high precision, but also the structure inside the reactor can be measured. Vibration distribution can be measured, and measurement accuracy can be improved.
【００４７】請求項５によれば、信号処理装置は測定し
た信号の周波数分析を行って炉内構造物の固有振動周波
数を算出し、表示装置は固有振動周波数の変化を表示す
ることにより、測定した振動信号に基づいて振動の変化
傾向（トレンド）を表示することができるので、振動異
常の把握が容易になり、炉内構造物の信頼性を向上させ
ることができる。According to the fifth aspect, the signal processing device performs a frequency analysis of the measured signal to calculate a natural vibration frequency of the furnace internal structure, and the display device displays a change in the natural vibration frequency, thereby performing the measurement. Since the change tendency (trend) of the vibration can be displayed based on the vibration signal obtained, it is easy to grasp the vibration abnormality, and the reliability of the furnace internal structure can be improved.
【図１】本発明に係る原子炉振動監視装置の第１実施形
態を示す構成図。FIG. 1 is a configuration diagram showing a first embodiment of a reactor vibration monitoring device according to the present invention.
【図２】第１実施形態において超音波信号の伝搬状態を
示す構成図。FIG. 2 is a configuration diagram showing a propagation state of an ultrasonic signal in the first embodiment.
【図３】第１実施形態において反射超音波信号を利用し
て振動測定を行う方法を示す説明図。FIG. 3 is an explanatory view showing a method of performing vibration measurement using a reflected ultrasonic signal in the first embodiment.
【図４】第１実施形態において送信される超音波パルス
信号と受信される超音波パルス信号を示すタイミングチ
ャート。FIG. 4 is a timing chart showing an ultrasonic pulse signal transmitted and an ultrasonic pulse signal received in the first embodiment.
【図５】第１実施形態において離散的な振動振幅の測定
値から実際の振動波形を再構成する方法を示す図。FIG. 5 is a diagram showing a method of reconstructing an actual vibration waveform from discrete vibration amplitude measurement values in the first embodiment.
【図６】本発明に係る原子炉振動監視装置の第２実施形
態を示す構成図。FIG. 6 is a configuration diagram showing a second embodiment of the reactor vibration monitoring device according to the present invention.
【図７】（Ａ），（Ｂ）は第２実施形態において送信Ｒ
Ｆパルスと受信ＲＦパルスの時間関係および周波数関係
を示すタイミングチャート。FIGS. 7A and 7B show transmission R in the second embodiment;
6 is a timing chart showing a time relationship and a frequency relationship between an F pulse and a received RF pulse.
【図８】本発明に係る原子炉振動監視装置の第３実施形
態を示す構成図。FIG. 8 is a configuration diagram showing a third embodiment of the reactor vibration monitoring device according to the present invention.
【図９】本発明に係る原子炉振動監視装置の第４実施形
態を示す構成図。FIG. 9 is a configuration diagram showing a fourth embodiment of the reactor vibration monitoring device according to the present invention.
【図１０】（Ａ），（Ｂ）は本発明に係る原子炉振動監
視装置の第５実施形態において固有振動数の表示方法を
示す説明図，しきい値の設定方法を示す説明図。FIGS. 10A and 10B are an explanatory view showing a method of displaying a natural frequency and a method of setting a threshold value in a reactor vibration monitoring apparatus according to a fifth embodiment of the present invention.
１ 超音波トランスジューサ ２ 原子炉圧力容器 ３ ケーブル ４ 原子炉格納容器 ４ａ 信号取出口 ５ 超音波信号処理装置 ６ 超音波送信器 ７ 超音波受信器 ８ 信号処理装置 ９ 表示装置 １０ 電気パルス信号（ＤＣパルス信号） １１ 超音波パルス信号 １２ 炉水 １３ 超音波パルス信号 １４ 炉内構造物 １５ 超音波パルス信号 １６ 振動振幅波形 １７ ＲＦパルス信号 １８ ＲＦパルス信号 １９ａ 固有振動数 １９ｂ 経時変化 DESCRIPTION OF SYMBOLS 1 Ultrasonic transducer 2 Reactor pressure vessel 3 Cable 4 Reactor containment vessel 4a Signal outlet 5 Ultrasonic signal processing device 6 Ultrasonic transmitter 7 Ultrasonic receiver 8 Signal processing device 9 Display device 10 Electric pulse signal (DC pulse 11) Ultrasonic pulse signal 12 Reactor water 13 Ultrasonic pulse signal 14 Furnace internal structure 15 Ultrasonic pulse signal 16 Vibration amplitude waveform 17 RF pulse signal 18 RF pulse signal 19a Natural frequency 19b Temporal change
───────────────────────────────────────────────────── フロントページの続き (72)発明者 佐久間 正剛 神奈川県横浜市磯子区新杉田町８番地 株 式会社東芝横浜事業所内 (72)発明者 兼本 茂 神奈川県横浜市磯子区新杉田町８番地 株 式会社東芝横浜事業所内 ──────────────────────────────────────────────────続 き Continuing from the front page (72) Inventor Masatake Sakuma 8th Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Inside the Toshiba Yokohama Office (72) Inventor Shigeru Kanemoto 8th Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Toshiba Yokohama Office
Claims (5)
パルス信号の送受信が兼用可能な超音波トランスジュー
サと、この超音波トランスジューサと電気的に接続され
前記超音波パルス信号を発生させる超音波送信器と、前
記超音波トランスジューサと電気的に接続され前記超音
波パルス信号を受信する超音波受信器と、前記超音波ト
ランスジューサからの超音波パルス信号を前記原子炉圧
力容器を通して原子炉内に入射させる一方、この原子炉
内の炉内構造物で反射した超音波パルス信号が再び前記
原子炉圧力容器を通して前記超音波トランスジューサを
経て前記超音波受信器に受信される超音波パルス信号を
処理する信号処理装置と、この信号処理装置により処理
された前記炉内構造物の振動情報を表示する表示装置と
を備えたことを特徴とする原子炉振動監視装置。An ultrasonic transducer installed on an outer surface of a reactor pressure vessel and capable of transmitting and receiving an ultrasonic pulse signal, and an ultrasonic transmitter electrically connected to the ultrasonic transducer to generate the ultrasonic pulse signal An ultrasonic receiver electrically connected to the ultrasonic transducer and receiving the ultrasonic pulse signal; and causing the ultrasonic pulse signal from the ultrasonic transducer to enter the reactor through the reactor pressure vessel. On the other hand, the ultrasonic pulse signal reflected by the internal structure of the reactor is again processed by the ultrasonic pressure transducer through the ultrasonic transducer through the ultrasonic pressure transducer and the ultrasonic pulse signal received by the ultrasonic receiver. And a display device for displaying vibration information of the furnace internals processed by the signal processing device. Reactor vibration monitoring device.
いて、超音波パルス信号は、無線周波数パルス信号であ
ることを特徴とする原子炉振動監視装置。2. The reactor vibration monitoring device according to claim 1, wherein the ultrasonic pulse signal is a radio frequency pulse signal.
いて、超音波トランスジューサは、１次元に複数個配列
され、信号処理装置は、これらの超音波トランスジュー
サの超音波の送信のタイミングを変化させるとともに、
受信される超音波パルス信号を時間的に遅延させて加算
して反射される超音波パルス信号を測定することを特徴
とする原子炉振動監視装置。3. The reactor vibration monitoring device according to claim 1, wherein a plurality of ultrasonic transducers are arranged one-dimensionally, and the signal processing device changes the transmission timing of the ultrasonic waves from these ultrasonic transducers. With
A reactor vibration monitoring device characterized in that a received ultrasonic pulse signal is delayed in time and added to measure a reflected ultrasonic pulse signal.
いて、超音波トランスジューサは、原子炉圧力容器の外
面に沿って移動可能に構成されたことを特徴とする原子
炉振動監視装置。4. The reactor vibration monitoring device according to claim 1, wherein the ultrasonic transducer is configured to be movable along an outer surface of the reactor pressure vessel.
子炉振動監視装置において、信号処理装置は、測定した
信号の周波数分析を行って炉内構造物の固有振動周波数
を算出し、表示装置は前記固有振動周波数の変化を表示
することを特徴とする原子炉振動監視装置。5. The reactor vibration monitoring device according to claim 1, wherein the signal processing device performs frequency analysis of the measured signal to calculate a natural vibration frequency of the reactor internal structure, and displays the calculated natural vibration frequency. A device for monitoring a reactor vibration, wherein the device displays a change in the natural vibration frequency.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP29124197A JP3782559B2 (en) | 1997-10-23 | 1997-10-23 | Reactor vibration monitoring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP29124197A JP3782559B2 (en) | 1997-10-23 | 1997-10-23 | Reactor vibration monitoring device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH11125688A true JPH11125688A (en) | 1999-05-11 |
| JP3782559B2 JP3782559B2 (en) | 2006-06-07 |
Family
ID=17766314
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP29124197A Expired - Lifetime JP3782559B2 (en) | 1997-10-23 | 1997-10-23 | Reactor vibration monitoring device |
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| Country | Link |
|---|---|
| JP (1) | JP3782559B2 (en) |
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