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JPS6042479B2 - Coolant leakage sound simulation sound source - Google Patents
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JPS6042479B2 - Coolant leakage sound simulation sound source - Google Patents

Coolant leakage sound simulation sound source

Info

Publication number
JPS6042479B2
JPS6042479B2 JP11597579A JP11597579A JPS6042479B2 JP S6042479 B2 JPS6042479 B2 JP S6042479B2 JP 11597579 A JP11597579 A JP 11597579A JP 11597579 A JP11597579 A JP 11597579A JP S6042479 B2 JPS6042479 B2 JP S6042479B2
Authority
JP
Japan
Prior art keywords
sound
sound source
leakage
coolant
water
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.)
Expired
Application number
JP11597579A
Other languages
Japanese (ja)
Other versions
JPS5639598A (en
Inventor
兼秀 渡辺
直 内川
登志男 小川
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.)
Doryokuro Kakunenryo Kaihatsu Jigyodan
Original Assignee
Doryokuro Kakunenryo Kaihatsu Jigyodan
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 Doryokuro Kakunenryo Kaihatsu Jigyodan filed Critical Doryokuro Kakunenryo Kaihatsu Jigyodan
Priority to JP11597579A priority Critical patent/JPS6042479B2/en
Publication of JPS5639598A publication Critical patent/JPS5639598A/en
Publication of JPS6042479B2 publication Critical patent/JPS6042479B2/en
Expired legal-status Critical Current

Links

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  • Examining Or Testing Airtightness (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は、水冷却型原子炉からの冷却材漏洩音を模擬
する音源に関し、更に詳しくは冷却材漏洩をアコーステ
ィック、工ミッション、センサーを用いて検出する装置
の設計に必要な漏洩音減衰率を測定するときに用いる漏
洩音模擬音源に関するものてある。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a sound source that simulates the sound of coolant leakage from a water-cooled nuclear reactor, and more specifically to the design of a device that detects coolant leakage using acoustics, engineering, and sensors. This article relates to a leakage sound simulating sound source used when measuring the necessary leakage sound attenuation rate.

水冷却型原子炉からの冷却材微少漏洩を検出する装置
の一つとして、アコースティック・工ミッション、セン
サー(以下、ワ正センサー」と略記する)を用いた漏洩
検出装置がある。
As one of the devices for detecting small leaks of coolant from a water-cooled nuclear reactor, there is a leak detection device that uses an acoustic mechanical sensor (hereinafter abbreviated as “Wasesen”).

この装置の漏洩検出原理は、高周帯域の微弱振動を高感
度て検出できる征センサーによつて、高温高圧の冷却材
か大気中に漏洩する時に生じる原子炉構造物の高周波振
動(100KHz〜1MHz)を検知するもの−である
。 ところでこのような漏洩検出器を設計するに際して
、予め漏洩音の減衰率を求め、検出可能な範 囲を把握
しておく必要がある。
The leak detection principle of this device is to detect high-frequency vibrations (100 KHz to 1 MHz) of reactor structures that occur when high-temperature, high-pressure coolant leaks into the atmosphere using a sensor that can detect weak vibrations in the high-frequency band with high sensitivity. ). By the way, when designing such a leakage detector, it is necessary to determine the attenuation rate of leakage sound in advance and understand the detectable range.

しかし、高周波帯域の微弱振動が構造物を伝播する時の
減衰率は、構造物の形状や材質、支持構造その他様々な
ファクターに依存するため、従来はモツクアツプ(実物
大模型)を用い、実際の原子炉の運転状態の冷却材(例
えば圧力70に9/Clt)温度280℃)を流動させ
、所定の位置に漏洩孔を形成し、実際に高温高圧水を漏
洩させて、それによつて生じる高周波帯域の微弱振動を
AEセンサーを用いて漏洩箇所・までの距離を変えて測
定することにより、減衰率を求めていた。 従つて、実
際に高温高圧水を漏洩させねばならないし、しかも実測
回数(漏洩箇所数)も多く必要だから、測定は時間もか
かり、作業も極めて煩瑣となるし、安全性の点でも問題
がある。
However, the attenuation rate when weak vibrations in the high frequency band propagate through a structure depends on the structure's shape, material, support structure, and various other factors. The high frequency generated by flowing the coolant (for example, pressure 70 to 9/Clt and temperature 280°C) in the operating state of the reactor, forming a leak hole at a predetermined position, and actually leaking high temperature and high pressure water. The attenuation rate was determined by measuring the weak vibrations in the band using an AE sensor while changing the distance to the leak point. Therefore, it is necessary to actually leak high-temperature, high-pressure water, and a large number of actual measurements (number of leakage points) are required, making measurements time-consuming, extremely cumbersome, and problematic in terms of safety. .

本発明の目的は、このような従来技術の欠点を解消し
、実際に高温高圧水を漏洩させることなく安全、迅速、
かつ容易に冷却材漏洩音の減衰率を測定できるような装
置を提供することにある。
The purpose of the present invention is to eliminate the drawbacks of the prior art, and to provide safe, quick, and efficient high-temperature, high-pressure water without actually leaking water.
Another object of the present invention is to provide a device that can easily measure the attenuation rate of coolant leakage sound.

かかる目的を達成するため、本発明は実際の冷却材漏洩
音を模擬した音源を開発したものであつて、漏洩想定箇
所に取付けられる広帯域型圧電素子と、該圧電素子にラ
ンダムなパルス幅のパルスを供給するランダム信号発生
器とを組合せて構成されている。以下図面に基づき本発
明について更に詳しく説明する。
In order to achieve this object, the present invention has developed a sound source that simulates the sound of an actual coolant leak, and includes a broadband piezoelectric element that is attached to the expected leakage location, and a pulse with a random pulse width applied to the piezoelectric element. It is configured in combination with a random signal generator that supplies The present invention will be explained in more detail below based on the drawings.

冷却材漏洩音の検出対象の一例に、第1図に示すような
圧力管型原子炉がある。かかる原子炉の構造は公知であ
るが、各部の作用と共に簡単に説明しておく。原子炉本
体は、力ランドリヤタンク1、圧力管2、燃料集合体お
よび遮蔽体(図示するを省略)などで構成されている。
力ランドリヤタンク1には減速材の重水が満され、圧力
管2は正方形格子に配置された力ランドリヤ管に挿入さ
れている。燃料集合体は、圧力室2内にあり、入口管3
を通つて炉心下部より流入する軽水冷却材によつて冷却
され、冷却材は核熱によつて加熱されて沸騰し、水と蒸
気の2相流となり、上昇管4を通つて蒸気ドラム5に至
る。蒸気ドラム5は、蒸気と水を分離する気水分離器を
もち、前記2相流はそこで気水分離され、蒸気はタービ
ン系へ、水は下降管6を経て再循環ポンプ7により下部
ヘッダ8を介して各圧力管へと再び送り込まれる。実際
に高温高圧水を漏洩させて減衰率を測定する時に用いる
モツクアツプの構造は、上記原子炉とほぼ同様の構造を
もつが、モツクアツプ装置内を流動する冷却水は、圧力
管部において核熱のかわりに電気ヒータを用いて原子炉
の運転状態まで加熱される。
An example of a target for detection of coolant leakage noise is a pressure tube nuclear reactor as shown in FIG. Although the structure of such a nuclear reactor is well known, it will be briefly explained along with the function of each part. The reactor main body is composed of a power tank 1, a pressure pipe 2, a fuel assembly, a shield (not shown), and the like.
The force lander tank 1 is filled with heavy water as a moderator, and the pressure pipes 2 are inserted into the force lander tubes arranged in a square grid. The fuel assembly is located within the pressure chamber 2 and is connected to the inlet pipe 3.
The coolant is heated by nuclear heat and boils, forming a two-phase flow of water and steam, which flows through the riser pipe 4 into the steam drum 5. reach. The steam drum 5 has a steam and water separator for separating steam and water, where the two-phase flow is separated, the steam is sent to the turbine system, and the water is sent via the downcomer 6 to the lower header 8 by the recirculation pump 7. is fed back into each pressure pipe via the The structure of the mock-up used to actually measure the attenuation rate by leaking high-temperature, high-pressure water has almost the same structure as the above-mentioned nuclear reactor, but the cooling water flowing inside the motsu-up device is exposed to nuclear heat in the pressure pipe section. Instead, it is heated to reactor operating conditions using electric heaters.

しかし、本発明に係る模擬音源を用いて減衰率を測定す
る場合には、高温高圧水を流動させることなく、モツク
アツプ内に常温水を流動させるだ.けでよい。
However, when measuring the attenuation rate using the simulated sound source according to the present invention, room-temperature water is flowed into the motsukup without flowing high-temperature, high-pressure water. It's fine.

さて模擬音源は、第2図に示すように、漏洩想定箇所に
取付けられる広帯域圧電変換素子10と、ランダム信号
発生器11とからなる。
Now, as shown in FIG. 2, the simulated sound source consists of a broadband piezoelectric transducer 10 that is attached to a location where leakage is expected, and a random signal generator 11.

ランダム信号発生器11は、両極性のパルスをランダム
.なパルス幅(最小0.6マイクロ秒)で発生し、その
ランダム信号な電圧信号を前記圧電変換素子10に入力
させることにより、該圧電変換素子10にランダムな荷
重変化を生じさせることができる。この広帯域型圧電変
換素子10としては、蔀センサーを用いることができる
。というのは、AEセンサーは荷重を加えると電圧を発
生し、電圧を印加すると力を発生するという可逆変化を
する圧電素子を材料にしているからである。模擬音を検
出する装置の構成例を第3図に示す。モツクアツプの所
定の場所に取付けられた佃センサー12からの信号は、
前置増幅器13を介してフィルタを内蔵した主増幅器1
4に送られ、実効電圧計15で測定される。ランダム信
号発生器11からの信号により圧電変換素子10に生じ
るランダムな荷重変化は、モツクアツプ構造物に微弱振
動を与える。
The random signal generator 11 randomly generates bipolar pulses. By inputting a random voltage signal generated with a pulse width (minimum 0.6 microseconds) to the piezoelectric transducer 10, a random load change can be caused in the piezoelectric transducer 10. As this broadband piezoelectric transducer 10, a hip sensor can be used. This is because the AE sensor is made of a piezoelectric element that reversibly changes in that it generates a voltage when a load is applied, and a force when a voltage is applied. FIG. 3 shows an example of the configuration of a device for detecting simulated sounds. The signal from the Tsukuda sensor 12 installed at a predetermined location on the Motsukuup is
Main amplifier 1 with built-in filter via preamplifier 13
4 and measured by an effective voltmeter 15. Random load changes generated in the piezoelectric transducer 10 by signals from the random signal generator 11 give weak vibrations to the mockup structure.

その振動は、構造物を伝播することによつて減衰して蔀
ノセンサー12に達し、そこで電気信号に変換される。
その信号は前置増幅器13および主増幅器14で増幅さ
れ、増幅された信号は実効電圧計15で測定記録される
。模擬音源からの距離の異なる複数点で減衰量を求めれ
ば、減衰率が判り、検出・可能な範囲を求めることがで
きる。次に、本発明装置を用いての実測例について述べ
る。
The vibration is attenuated by propagating through the structure and reaches the sensor 12, where it is converted into an electrical signal.
The signal is amplified by a preamplifier 13 and a main amplifier 14, and the amplified signal is measured and recorded by an effective voltmeter 15. By determining the amount of attenuation at multiple points at different distances from the simulated sound source, the attenuation rate can be determined, and the detection range can be determined. Next, an example of actual measurement using the device of the present invention will be described.

測定で用いたAEセンサーは、周波数帯域100KHz
−洲Hzに検出感度をもつ広帯域型AEセンサーであり
、主増幅器内部のバンドパスフイル・夕は300KHz
−2MHzに設定し、前置増幅器および主増幅器の利得
はそれぞれ40dB,0〜60c1Bとして測定を行な
つた。その結果を第4図に示す。曲線Bは、モツクアツ
プ内部を流動する高温高圧水(圧力70k9/Cltl
温度280゜C)を実際に漏洩させたときの減衰曲線、
曲線Aは本発明に係る模擬音源を用い、常温の冷却材を
流動させたときの減衰曲線を示している。この結果から
、両曲線はほぼ同じ減衰を示していることが判り、実際
に高温高圧水を漏洩させることなく、漏洩想定位置に模
擬音源を置くことにより、減衰率を評価できることが実
証された。本発明は上記のように構成した漏洩音模擬音
源であるから、この装置を用いることにより、実際に高
温高圧水を漏洩させることなく、安全に、しかも迅速、
容易に漏洩音の検出範囲を決める減衰率を評価てきるし
、その上、常温の冷却材を流動させるだけでよいから、
電気ヒータを使用せずにすみ、使用電力を節約てきると
いつたすぐれた効果を奏しうるものである。
The AE sensor used in the measurement has a frequency band of 100KHz.
- It is a wideband AE sensor with detection sensitivity at 300 kHz, and the bandpass filter inside the main amplifier has a detection sensitivity of 300 kHz.
-2 MHz, and the preamplifier and main amplifier gains were 40 dB and 0 to 60 c1B, respectively. The results are shown in FIG. Curve B shows high-temperature, high-pressure water (pressure 70k9/Cltl) flowing inside the motsukup.
Attenuation curve when actually leaking water (temperature 280°C),
Curve A shows an attenuation curve when a coolant at room temperature is made to flow using the simulated sound source according to the present invention. The results showed that both curves showed almost the same attenuation, and it was demonstrated that the attenuation rate could be evaluated by placing a simulated sound source at the expected leak location without actually leaking high-temperature, high-pressure water. Since the present invention is a leakage sound simulating sound source configured as described above, by using this device, high-temperature, high-pressure water can be safely and quickly removed without actually leaking.
You can easily evaluate the attenuation rate that determines the leakage sound detection range, and what's more, you only need to flow coolant at room temperature.
This can have excellent effects as it eliminates the need to use an electric heater and saves power.

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

第1図は圧力管型原子炉の説明図、第2図は本発明に係
る漏洩音模擬音源のブロック図、第3図は漏洩音検出装
置のブロック図、第4図は従来方法と本発明装置を用い
た方法の実測比較例を示すグラフである。 10・・・・・・広帯域型圧電変換素子、11・・・・
・・ランダム信号発生器、12・・・・・・AEセンサ
ー、14・・・・・・主増幅器、15・・・・・・実効
電圧計。
Fig. 1 is an explanatory diagram of a pressure tube nuclear reactor, Fig. 2 is a block diagram of a leakage sound simulating sound source according to the present invention, Fig. 3 is a block diagram of a leakage sound detection device, and Fig. 4 is a conventional method and the present invention. It is a graph showing an actual measured comparative example of a method using the device. 10...Broadband piezoelectric conversion element, 11...
... Random signal generator, 12 ... AE sensor, 14 ... Main amplifier, 15 ... Effective voltmeter.

Claims (1)

【特許請求の範囲】[Claims] 1 漏洩想定箇所に取付けるられる広帯域型圧電変換素
子と、該圧電変換素子にランダムなパルス幅のパルスを
供給するランダム信号発生器とを組合せてなる冷却材漏
洩音の模擬音源。
1. A simulated sound source for coolant leakage sound, which is formed by combining a broadband piezoelectric transducer that is installed at a predicted leakage location and a random signal generator that supplies pulses with random pulse widths to the piezoelectric transducer.
JP11597579A 1979-09-10 1979-09-10 Coolant leakage sound simulation sound source Expired JPS6042479B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP11597579A JPS6042479B2 (en) 1979-09-10 1979-09-10 Coolant leakage sound simulation sound source

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP11597579A JPS6042479B2 (en) 1979-09-10 1979-09-10 Coolant leakage sound simulation sound source

Publications (2)

Publication Number Publication Date
JPS5639598A JPS5639598A (en) 1981-04-15
JPS6042479B2 true JPS6042479B2 (en) 1985-09-21

Family

ID=14675757

Family Applications (1)

Application Number Title Priority Date Filing Date
JP11597579A Expired JPS6042479B2 (en) 1979-09-10 1979-09-10 Coolant leakage sound simulation sound source

Country Status (1)

Country Link
JP (1) JPS6042479B2 (en)

Also Published As

Publication number Publication date
JPS5639598A (en) 1981-04-15

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