JPS60219592A - Abnormality detector for fuel bucket in nuclear power fuel transfer facility - Google Patents

Abnormality detector for fuel bucket in nuclear power fuel transfer facility

Info

Publication number
JPS60219592A
JPS60219592A JP59076339A JP7633984A JPS60219592A JP S60219592 A JPS60219592 A JP S60219592A JP 59076339 A JP59076339 A JP 59076339A JP 7633984 A JP7633984 A JP 7633984A JP S60219592 A JPS60219592 A JP S60219592A
Authority
JP
Japan
Prior art keywords
fuel
packet
fuel transfer
slope
detector
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
JP59076339A
Other languages
Japanese (ja)
Inventor
秀昭 森下
北島 晟
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.)
Central Research Institute of Electric Power Industry
Kawasaki Heavy Industries Ltd
Kawasaki Motors Ltd
Original Assignee
Central Research Institute of Electric Power Industry
Kawasaki Heavy Industries Ltd
Kawasaki Jukogyo KK
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 Central Research Institute of Electric Power Industry, Kawasaki Heavy Industries Ltd, Kawasaki Jukogyo KK filed Critical Central Research Institute of Electric Power Industry
Priority to JP59076339A priority Critical patent/JPS60219592A/en
Publication of JPS60219592A publication Critical patent/JPS60219592A/en
Pending legal-status Critical Current

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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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 本発明は、原子力燃料移送設備に於ける燃料パケットの
移動時の異常を検出する装置に関する0 原子力燃料移送設備は、第1図に示す如く原子炉容器l
の炉心1aと炉外燃料貯蔵槽2との間の上方に燃料移送
セル3を設け、この燃料移送セル3から原子炉容器lの
炉心1a及び炉外燃料貯蔵槽2へ夫々斜道4.5を設け
、斜道4゜5内には燃料パケット6を配し、チェーン7
にて燃料移送セル3内に設けた巻上装置8に連結し、前
記燃料移送セル3内には前記斜道4,5の延長上の間を
スイングする可動斜道9を設けたものである。゛ 原子炉容器lの炉心1aに於いて使用済みになった燃料
は、燃料交換装置lOによって把持され、図示の位置に
待機している。一方燃料パケット6は巻上装置8によっ
て巻降され、燃料交換装@10の直下まで斜道4内を滑
降し、燃料バケット6内に使用済み燃料が収納される。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a device for detecting an abnormality during the movement of fuel packets in nuclear fuel transfer equipment.
A fuel transfer cell 3 is provided above between the reactor core 1a and the ex-core fuel storage tank 2, and ramps 4.5 are installed from the fuel transfer cell 3 to the core 1a and the ex-core fuel storage tank 2 of the reactor vessel l, respectively. A fuel packet 6 is placed within the inclined path 4°5, and a chain 7 is placed.
The fuel transfer cell 3 is connected to a hoisting device 8 provided in the fuel transfer cell 3, and a movable ramp 9 swinging between the extensions of the ramps 4 and 5 is provided in the fuel transfer cell 3. .゛The spent fuel in the core 1a of the reactor vessel 1 is held by the fuel exchange device 1O and is waiting at the position shown in the figure. On the other hand, the fuel packet 6 is lowered by the hoisting device 8 and slides down the ramp 4 to just below the fuel exchange device @10, and the spent fuel is stored in the fuel bucket 6.

使用済み燃料を収納した燃料パケット6は巻上装置8に
よって可動斜道9内迄引揚げられ、次に可動斜道9がス
イングせしめられて斜道5に連結される。この状態で燃
料パケット6を滑降し、使用済み燃料を炉外燃料貯蔵槽
2に貯蔵する0 炉外燃料貯蔵槽2に貯蔵さnている新燃料は燃料交換装
置ioによ多燃料パケット6に収納し、前記と同じ経路
を逆にたどって原子炉容器lの炉心1aに装荷する。こ
のようにして新旧の燃料の移送交換が終了すると、可動
斜道9内に燃料パケット6を引揚げ、斜道4,5を図示
せぬボート弁にて閉じ、可動斜道9を鉛直状態にし、次
の燃料交換時期が来るまで待機する。
The fuel packet 6 containing the spent fuel is lifted up into the movable slope 9 by the hoisting device 8, and then the movable slope 9 is swung and connected to the slope 5. In this state, the fuel packet 6 is slid down, and the spent fuel is stored in the extra-core fuel storage tank 2.The new fuel stored in the extra-core fuel storage tank 2 is transferred to the fuel exchange device IO and transferred to the multi-fuel packet 6. It is then loaded into the core 1a of the reactor vessel 1 by retracing the same route as above. When the transfer and exchange of old and new fuel is completed in this way, the fuel packet 6 is pulled up into the movable ramp 9, the ramps 4 and 5 are closed with a boat valve (not shown), and the movable ramp 9 is brought into a vertical state. , wait until the next fuel change time comes.

ところで、前記の原子力燃料移送設備とシわけ斜道4.
5内は、高放射性雰囲気であシ且つ非常に狭い為、内部
を直接監視することができず、燃料移送中の燃料パケッ
ト6の異常、即ち斜道4,5内のレールとこnに清って
走行する燃料パケット60車輪との摩摺(レールのフラ
ンジと車輪のフランジとの擦過摺動)や車輪の軸受部の
故障等による車輪の転勤不調等の異常は、巻上装置8の
モータの駆動軸のトルク検出によって判定していた。
By the way, the above-mentioned nuclear fuel transfer equipment and dividing slope 4.
Because the inside of 5 has a highly radioactive atmosphere and is very narrow, it is not possible to directly monitor the inside. Abnormalities such as friction with the wheels of the fuel packet 60 (friction and sliding between the rail flange and the wheel flange) or poor wheel transfer due to failure of the wheel bearings, etc. This was determined by detecting the torque of the drive shaft.

この燃料パケット6の異常判定方法は、燃料パケット6
から、モータまでの間に減速機などの伝動機器が配設さ
れる為、微弱な異常の検出が困難で、燃料パケット6の
異常の早期発見や燃料パケット6の位置の正確な判定が
困難であったO 本発明は斯かる問題を解決すべくなされたもので、斜道
内を上下動する燃料パケットの微弱な異常でも簡単、確
実且つ正確に検出でき、また燃料パケットの位置を正確
に判定することのできる原子力燃料移送設備に於ける燃
料パケットの異常検出装置を提供せんとするものである
This fuel packet 6 abnormality determination method is based on the fuel packet 6 abnormality determination method.
Since transmission equipment such as a speed reducer is installed between the engine and the motor, it is difficult to detect slight abnormalities, and it is difficult to detect abnormalities in the fuel packet 6 early or to accurately determine the position of the fuel packet 6. The present invention was made to solve this problem, and it is possible to easily, reliably, and accurately detect even a slight abnormality in a fuel packet moving up and down on a slope, and to accurately determine the position of the fuel packet. The present invention aims to provide an abnormality detection device for fuel packets in nuclear fuel transfer equipment that is capable of detecting abnormalities in fuel packets in nuclear fuel transfer equipment.

以下本発明による燃料パケットの異常検出装置の一実施
例全第2図によって説明すると、3は燃料移送セルで、
この燃料移送セル3から原子炉容器lの炉心1a及び炉
外燃料貯威檜2(第1図参照)に斜道4及び5が設けら
扛ている。
Hereinafter, one embodiment of the fuel packet abnormality detection device according to the present invention will be explained with reference to FIG. 2. Reference numeral 3 denotes a fuel transfer cell;
Slopes 4 and 5 are provided from the fuel transfer cell 3 to the core 1a of the reactor vessel 1 and the external fuel storage cypress 2 (see FIG. 1).

11は斜道4及び5の本体である円形の案内管で、この
案内管11内に燃料パケット6が車輪6aにて走行する
チャンネル形のレール12が相対向して設けらnている
。13は案内管itの外周に設けら扛た斜道冷却設備、
14は斜道4及び5の熱膨張を吸収可能にその上端部を
燃料移送セル3の床側に支持したベローズである。
Reference numeral 11 denotes a circular guide tube which is the main body of the ramps 4 and 5, and within this guide tube 11 are provided opposing channel-shaped rails 12 on which the fuel packets 6 run on wheels 6a. 13 is a slope cooling equipment installed on the outer periphery of the guide pipe IT;
Reference numeral 14 denotes a bellows whose upper end is supported on the floor side of the fuel transfer cell 3 so as to be able to absorb the thermal expansion of the ramps 4 and 5.

15は異常検出装置の超音波用音響検出器で、斜道4及
び50案内管itの上端部外周面に取付けらnている。
Reference numeral 15 denotes an ultrasonic acoustic detector of the abnormality detection device, which is attached to the outer circumferential surface of the upper end of the slope 4 and guide pipe 50.

この超音波用音響検出器15t−取付けた案内管11の
内面位置とレール12との間には導波棒16が結合して
設けらnている。超音波用音響検出器15には斜道4及
び5から離れた位置のフィルタ・アンプ17が接続さ扛
、該フィルタ・アンプ17には信号処理装置18が接続
され、該信号処理装置18には警報器19が接続されて
いる0 かように構成さrt、*上記実施例の燃料パケットの異
常検出装置によしは、燃料パケット6が車輪6aにて斜
道4及び5のレール12を走行する音響が減衰すること
なく導波$16.案内管11全通して直接超音波用貴書
検出器15に確実且つ正確に検出されその音V侶号がフ
ィルタ・アンプ17に送られて濾過・増幅され、その濾
過・増幅された音響信号が信号処理装置L8に送ら牡、
ここで予め設定さnた燃料パケット正常時の通過音の音
響信号と比較演算さし、フィルタ・アンプ17から送ら
扛てきた音響信号のレベルが高いときや音響波形が通常
時と異なるときには、燃料パケット6の異常、即ち燃料
パケット6の車輪6aとレール12との摩摺や一車輪6
aの軸受部の故障等による車輪6aの転勤不調等の異常
が生じているものと判定さ扛、その判定結果の異當倍号
が警報器19に送ら扛て警報器19から警報が発せら扛
る〇 また燃料パケット6が斜道4及び5内に入って走行して
いる間中その走行音の音響が前記と同様に超音波用音響
検出器15に確実に検出さ扛るのであるから、信号処理
装置18での時間の経過に伴う音響レベルの変化によっ
て燃料パケット60位f1に、全正確に判定できる。同
、超音波用音響検出器15i案内管11の外周の数ケ所
に取付ければ、燃料バクット6の位置をよυ正確に判定
することができる。
A waveguide rod 16 is coupled between the rail 12 and the inner surface of the guide tube 11 to which the ultrasonic acoustic detector 15t is attached. A filter amplifier 17 located away from the slopes 4 and 5 is connected to the ultrasonic acoustic detector 15, and a signal processing device 18 is connected to the filter amplifier 17. According to the fuel packet abnormality detection device of the above embodiment, the fuel packet 6 runs on the rails 12 of the slopes 4 and 5 with the wheels 6a. Waveguide without sound attenuation $16. The sound is detected reliably and accurately by the ultrasonic book detector 15 directly through the guide tube 11, and the sound is sent to the filter amplifier 17 where it is filtered and amplified, and the filtered and amplified acoustic signal is Sent to signal processing device L8,
Here, a comparison calculation is made with the preset acoustic signal of the passing sound of the fuel packet when it is normal. When the level of the acoustic signal sent from the filter amplifier 17 is high or the acoustic waveform is different from normal, An abnormality in the packet 6, that is, friction between the wheel 6a of the fuel packet 6 and the rail 12, or one wheel 6
It is determined that an abnormality such as poor transfer of wheel 6a is occurring due to failure of the bearing part of a, etc., the abnormal number of the determination result is sent to the alarm 19, and the alarm 19 issues an alarm. Also, while the fuel packet 6 enters the ramps 4 and 5 and travels, the sound of the traveling sound is reliably detected and detected by the ultrasonic acoustic detector 15 as described above. , it is possible to accurately determine that the fuel packet is in the 60th position f1 based on the change in the sound level over time in the signal processing device 18. Similarly, by attaching the ultrasonic acoustic detectors 15i at several locations on the outer periphery of the guide tube 11, the position of the fuel bag 6 can be determined more accurately.

この実施例の燃料パケットの異常検出装置は、超音波用
音響検出器15がカバーガスバウンダリを貫通せず、斜
道冷却設備13との干渉もなく、故障時の交換が可能で
あるので、メンテナンス性に優れている。
In the fuel packet abnormality detection device of this embodiment, the ultrasonic acoustic detector 15 does not penetrate the cover gas boundary, does not interfere with the slope cooling equipment 13, and can be replaced in the event of failure, so maintenance is easy. Excellent in sex.

次に本発明による燃料パケットの異常検出装置の他の実
施例を第3図によって説明する。図中第2図と同一符号
は同一物を示すのでその説明を省略する。この実施例は
レール12の一側外面に凹部20を有する支持具21を
一体に設け、超音波用音響検出器15を内部下端附近に
取付は上端屈曲部側面の開口に自動脱着プラグ22を取
付けた細長いケース23を、レール12の上端−側外方
に設けられた透孔24よシレール12の一側外面に沿っ
て案内管11内に入れ、ケース23の下端を前記支持具
21の凹部20に嵌入支持せしめたもので、自動脱着プ
ラグ22ニハフイルタ・アンプ17のケーブルを接続す
るようにしたものである。
Next, another embodiment of the fuel packet abnormality detection device according to the present invention will be described with reference to FIG. Since the same reference numerals in the figure as in FIG. 2 indicate the same parts, the explanation thereof will be omitted. In this embodiment, a support 21 having a recess 20 is integrally provided on the outer surface of one side of the rail 12, and an ultrasonic acoustic detector 15 is attached near the inner lower end, and an automatic detachable plug 22 is attached to the opening on the side surface of the upper bent part. The elongated case 23 is inserted into the guide tube 11 along the outer surface of one side of the rail 12 through a through hole 24 provided on the outer side of the upper end of the rail 12, and the lower end of the case 23 is inserted into the recess 20 of the support 21. The cable of the automatic detachable plug 22 and the Ni-filter amplifier 17 is connected to the automatic detachable plug 22.

この燃料パケットの異常検出装置によれば、燃料パケッ
ト6がレール12を走行する音響がレール12から直か
に超音波用音響検出器15に確実、正確に検出され、そ
の音響信号がフィルタ・アンプに送られて濾過・増幅さ
れ、その濾過・増幅さnた音響信号が14号処理装置1
8に送らnて前記実施例の場合と同様に燃料パケット6
の正常或いは異常が判定さn1異常の場合は異常信号が
警報器19に送ら扛て警報器19から警報が発せられる
。また燃料パケット6の斜道4及び5内の走行中の位置
は、前記実施例の場合と同様に、信号処理装置18での
時間の経過に伴う音響レベルの変化によって正確に判定
できる。
According to this fuel packet abnormality detection device, the sound of the fuel packet 6 running on the rail 12 is reliably and accurately detected directly from the rail 12 by the ultrasonic sound detector 15, and the sound signal is transmitted to the filter amplifier. The filtered and amplified acoustic signal is sent to processing unit 14, where it is filtered and amplified.
The fuel packet 6 is sent to the fuel packet 8 as in the previous embodiment.
If it is determined whether n1 is normal or abnormal, an abnormality signal is sent to the alarm device 19, and the alarm device 19 issues an alarm. Further, the position of the fuel packet 6 while traveling on the slopes 4 and 5 can be accurately determined by the change in the sound level with the passage of time in the signal processing device 18, as in the case of the previous embodiment.

この実施例の燃料パケットの異常検出装置は、超音波用
音響検出器15がケース23毎出し入れ可能なカートリ
ッジ方式であシ、自動脱層プラグ22にてケーブルの接
続ができ、斜道4及び5のボート弁との干渉もないので
、メンテナンス性に曖扛、その上超音波用音響検出器1
5は斜道4及び5の熱膨張を逃けることができ、さらに
は低温の為ナトリワムベーパの影響が小さい。
The fuel packet abnormality detection device of this embodiment is of a cartridge type in which the ultrasonic acoustic detector 15 can be taken in and out of each case 23, and the cable can be connected using the automatic delayering plug 22. Since there is no interference with the boat valve, maintenance is difficult, and ultrasonic acoustic detector 1
5 can escape the thermal expansion of slopes 4 and 5, and furthermore, because of the low temperature, the influence of sodium vapor vapor is small.

以上の説明で判るように本発明による燃料パケットの異
常検出装置は、超音波用音響検へ器を斜道の途中に設け
、該検出器にフィルタ・アンプを接続し、該フィルタ・
アンプに信号処理装置を接続し、該信号処理装置に警報
器を接続して、燃料パケット走行時の音響を検出し、判
定するのであるから、燃料パケットの車輪と斜道のレー
ルとの摩摺や車輪軸受部の故障等による車輪の転勤不調
等の異常が生じると、音響レベルが通常の燃料パケット
走行時の音響レベルよシも著しく上昇し、音響波形が通
常時と異なるので、燃料パケットの異常が簡単、確実且
つ正確に判定することができる。また斜道内を走行する
燃料パケットの位置も経時的に変化する一It4iルベ
ルの変化によって判定できる等の効果がある。
As can be seen from the above explanation, the fuel packet abnormality detection device according to the present invention includes an ultrasonic acoustic detector installed in the middle of a slope, a filter amplifier connected to the detector, and a filter amplifier connected to the detector.
A signal processing device is connected to the amplifier, and an alarm is connected to the signal processing device to detect and judge the sound when the fuel packet is running, so it is possible to detect the friction between the wheels of the fuel packet and the slope rail. If an abnormality occurs, such as poor wheel transfer due to wheel bearing failure, the sound level will rise significantly compared to the sound level during normal fuel packet running, and the acoustic waveform will be different from normal, so the fuel packet Abnormalities can be determined simply, reliably, and accurately. Further, there is an effect that the position of a fuel packet traveling on a slope can be determined based on a change in the It4i level that changes over time.

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

第1図は燃料移送設備の全体を示す概略縦断面図、第2
図は本発明の燃料パケットの異常検出装置の一実施例を
示す図、第3図社他の実施例を示す図である。 l・・・原子炉容器 1a・・・炉心 2・・・炉外燃
料貯蔵槽 3・・・燃料移送セル 4.5・・・斜道 
6・・・燃料パケット 6a・・・車輪7・・・チェー
ン 8・・・巻上装置 9・・・可wJ斜道 lO・・
・燃料交換装置 11・・・案内管12・・・レール 
13・・・斜道冷却設備 14・・・ベローズ 15・
・・超音波用音響検出器16・・・導波棒 17・・・
フィルタ・アンプ18・・・信号処理装@ 19・・・
警報器 20・・・凹部 21・・・支持具 22・・
・自動脱着プラグ 23°・°ケース 24・・・透孔
出願人 川崎重工業株式会社 出 願人 財団法人電力中火研究所 ・代理 人 弁理士 高 雄次部
Figure 1 is a schematic longitudinal cross-sectional view showing the entire fuel transfer facility, Figure 2
The figure shows an embodiment of the fuel packet abnormality detection device of the present invention, and FIG. 3 shows an embodiment of the fuel packet abnormality detection device. l...Reactor vessel 1a...Reactor core 2...External fuel storage tank 3...Fuel transfer cell 4.5...Slope
6...Fuel packet 6a...Wheel 7...Chain 8...Hoisting device 9...Possible wJ slope lO...
・Fuel exchange device 11... Guide pipe 12... Rail
13...Slope cooling equipment 14...Bellows 15.
...Ultrasonic acoustic detector 16...Waveguide rod 17...
Filter amplifier 18... Signal processing device @ 19...
Alarm device 20... recess 21... support 22...
・Automatic detachable plug 23°・°Case 24...Through hole Applicant: Kawasaki Heavy Industries, Ltd. Applicant: Electric Power Research Institute, Inc., Agent: Patent attorney: Yujibe Taka

Claims (1)

【特許請求の範囲】[Claims] 原子炉容器の炉心から燃料移送セルへ、及び燃料移送セ
ルから炉外燃料貯蔵槽への燃料移送設備の斜道の途中に
超音波用音響検出器を設け、該検出器にフィルタ・アン
プを接続し、該フィルタ・アンプに信号処理装置を接続
し、該信号処理装置に簀報器を接続して成る原子力燃料
移送設備に於ける燃料パケットの異常検出装置。
An ultrasonic acoustic detector is installed in the middle of the slope of the fuel transfer equipment from the core of the reactor vessel to the fuel transfer cell and from the fuel transfer cell to the extra-core fuel storage tank, and a filter amplifier is connected to the detector. A fuel packet abnormality detection device in a nuclear fuel transfer facility, comprising: a signal processing device connected to the filter amplifier; and a monitor connected to the signal processing device.
JP59076339A 1984-04-16 1984-04-16 Abnormality detector for fuel bucket in nuclear power fuel transfer facility Pending JPS60219592A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59076339A JPS60219592A (en) 1984-04-16 1984-04-16 Abnormality detector for fuel bucket in nuclear power fuel transfer facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59076339A JPS60219592A (en) 1984-04-16 1984-04-16 Abnormality detector for fuel bucket in nuclear power fuel transfer facility

Publications (1)

Publication Number Publication Date
JPS60219592A true JPS60219592A (en) 1985-11-02

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Family Applications (1)

Application Number Title Priority Date Filing Date
JP59076339A Pending JPS60219592A (en) 1984-04-16 1984-04-16 Abnormality detector for fuel bucket in nuclear power fuel transfer facility

Country Status (1)

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JP (1) JPS60219592A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5060698A (en) * 1973-10-01 1975-05-24
JPS5640754A (en) * 1979-09-10 1981-04-17 Power Reactor & Nuclear Fuel Dev Corp Cavitation detecting method using ae sensor

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5060698A (en) * 1973-10-01 1975-05-24
JPS5640754A (en) * 1979-09-10 1981-04-17 Power Reactor & Nuclear Fuel Dev Corp Cavitation detecting method using ae sensor

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