JPH068809B2 - Ultrasonic flaw detector - Google Patents
Ultrasonic flaw detectorInfo
- Publication number
- JPH068809B2 JPH068809B2 JP61086102A JP8610286A JPH068809B2 JP H068809 B2 JPH068809 B2 JP H068809B2 JP 61086102 A JP61086102 A JP 61086102A JP 8610286 A JP8610286 A JP 8610286A JP H068809 B2 JPH068809 B2 JP H068809B2
- Authority
- JP
- Japan
- Prior art keywords
- shroud
- probe unit
- rpv
- horizontal arm
- movement mechanism
- 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 - Lifetime
Links
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2291/00—Indexing codes associated with group G01N29/00
- G01N2291/02—Indexing codes associated with the analysed material
- G01N2291/028—Material parameters
- G01N2291/02872—Pressure
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2291/00—Indexing codes associated with group G01N29/00
- G01N2291/04—Wave modes and trajectories
- G01N2291/044—Internal reflections (echoes), e.g. on walls or defects
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2291/00—Indexing codes associated with group G01N29/00
- G01N2291/26—Scanned objects
- G01N2291/269—Various geometry objects
- G01N2291/2695—Bottles, containers
-
- 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
- Investigating Or Analyzing Materials By The Use Of Ultrasonic Waves (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
〔発明の技術分野〕 本発明は原子炉圧力容器の溶接部及び炉内構造物の健全
性を確認するために原子炉圧力容器の内側から超音波探
傷検査を行う装置に関する。 〔発明の技術的背景とその問題点〕 一般に原子力発電所では原子炉圧力容器(以下RPVと
略す)の溶接部に対し、その供用期間中に超音波探傷検
査(以下UTと略す)を行うことが義務付けられてい
る。したがって例えば加圧水型原子力発電所では、内
部装置の取出しが可能なこと、沸騰水型原子炉(以下
BWRと略す)のRPVに比べ大きさが小さいこと、
RPV外側からの接近が構造上不可能である等の理由に
より、第8図に示すようなUT装置を用いてRPVの内
側からUTを行っている。 このUT装置は加圧水型原子炉(以下PWRと略す)専
用のもので、サポートリング101の中心に支柱102
を有し、この支柱102に水平方向に伸縮自在な探傷ア
ーム103を回転かつ上下動自在に設けて構成されてい
る。そして、探傷アーム103の先端には超音波トラン
スデューサ104が設けられており、この超音波トラン
スデューサ104を探傷アーム103によってRPVの
内面に押付けることによりUTを行うように構成されて
いる。また、このUT装置はRPVのフランジ面にサポ
ートレグ105を固定することにより位置決めされるよ
うになっている。 一方、沸騰水型原子力発電所ではRPV外側からの接近
が可能であるため、検査部に対応した小型のUT装置を
用いてRPVの外側からUTを行っているが、ISI
(供用期間中検査)が導入される以前に建設されたプラ
ントについてはRPVの外面に保温材が密着しているた
め外側からのUTが困難であり、第8図に示したUT装
置を用いてRPV内側からUTを行う方法が考えられて
いる。 しかしながら、BWRではRPV下部の炉心領域にシュ
ラウドやジェットポンプなどの外部へ取出すことのでき
ない炉内構造物があるため、第8図に示したPWR専用
のUT装置を用いてUTを行うことは事実極めて困難で
ある。また、 BWRのRPVはPWRに比べ長大(例えば、110万
kw級のPWRでRPVのフランジボトム間は約10m
であるのに対し50万kw級のBWRでは10数mもあ
る)であり、しかも検査部が炉心領域のように狭い場所
(RPVとシュラウドの間が最大で約400mm程度)
にあるような場合、前記のフランジ面支持による方式で
は装置本体の精度上問題がある。さらに第8図のUT装
置は大型のためプラント内への搬出入および組立作業が
大変で、かなりの組立スペースも必要とする。また、R
PVのフランジ面全周を覆ってしまう構造のため他のオ
ペフロ作業と干渉し、これがクリティカルパスとなって
他のオペフロ作業を遅らせる原因ともなる。 〔発明の目的〕 本発明の目的はこのような事情に鑑みてなされたもの
で、外側からの接近が困難なBWRのRPVに対して内
側からUTを行うことができ、しかも検査部が炉心領域
のように狭い場所にある場合でも安定した高精度なUT
が可能コンパクトで操作性のよいUT装置を提供するこ
とにある。 〔発明の概要〕 すなわち本発明の超音波探傷装置は、沸騰水型原子炉の
炉心を形成するシュラウドの上端部に載置される装置本
体と、この装置本体の両側にジョイントアームを介して
連結され前記シュラウドの周方向に移動可能な周方向移
動機構と、前記装置本体から下方に垂設され上下方向に
伸縮自在であってかつ軸回りに回転自在な多段式ロッド
と、この多段式ロッドの下端に設けられた水平アーム
と、この水平アームを水平方向にスライドさせる水平方
向スライド機構と、上記水平アームの両端部に回転自在
に設けられた探触子ユニットと、この探触子ユニットを
原子炉圧力容器の内面に押付ける押付機構とを具備し、
前記周方向移動機構は前記シュラウドの上端部を挟持す
る一対のローラを有し、これらのローラのうち少なくと
も一方のローラを回転させてシュラウドの周方向に移動
することを特徴とするものである。 〔発明の実施例〕 以下、本発明の一実施例を第1図〜第7図を参照して説
明する。 第1図は本発明によるUT装置の構成示す図で、(a)は
正面図、(b)は側面図、(c)は平面図である。このUT装
置はRPV内のシュラウド30の上端にセットされる装
置本体1と、この装置本体1をRPVの周方向(図中矢
印α)に移動させる周方向移動機構2と、上記装置本体
1に回転自在に垂設されRPVの軸方向(図中矢印X)
に伸縮自在な多段式ロッド3と、この多段式ロッド3の
下端に設けられた水平アーム4と、この水平アーム4を
水平方向(図中矢印Y)にスライドさせる水平方向スラ
イド機構5と、上記水平アーム4の両端部に設けられた
探触子ユニット部6A,6Bと、これらの探触子ユニッ
ト部6A,6Bを水平アーム4とともにRPVの内面に
押付ける押付機構7から構成されている。 上記装置本体1は上面にフック11を有し、ワイヤロー
プ等によりシュウラウド30の上端に吊り下されるよう
になっている。そして、装置本体1の内部には第2図に
示すように多段式ロッド駆動用のステッピングモータ1
2が設けら、このステッピングモータ12で駆動ギア1
3を介して多段式ロッド3の上端に設けられた回転用ギ
ア14を駆動するように構成されている。 上記周方向移動機構2は第3図および第4図に示すよう
に駆動ローラ16とガイドローラ17よりなり、駆動ロ
ーラ16は水圧タービン18により歯車機構19を介し
て駆動されるように構成されている。そして、ガイドロ
ーラ17はバネ20によりシュラウド30の内壁側へ押
付けられており、駆動ローラ16との間にシュラウド3
0の上端部をガタが生じないように挟み込む構造となっ
ている。なお、周方向移動機構2は第1図に示すように
ジョイントアーム15を介して装置本体1に連結されて
いる。 また、前記水平方向スライド機構5は第1図および第5
図に示すように水平アーム4を支持する支持ローラ21
a,21b,21c,21dと駆動用モータ22より構
成され、支持ローラ21a〜21dは水平アーム4の上
下面に形成されたガイド溝23内を摺動するように設け
られている。また、モータ22は駆動ギヤ24を介して
水平アーム4の後部に設けられたラック部25を駆動す
るように設けられている。 前記探触子ユニット部6A,6Bは第5図に示すように
探触子ユニット8と探触子ユニット回転機構9よりな
り、探触子ユニット8は被検面に対し各々0゜,45
゜,60゜の入射角度を持つ3つの探触子10a,10
b,10cから構成されている。そして、探触子ユニッ
ト回転機構9は探触子ユニット8を270゜以上回転さ
せる機能を持ち、エンコーダ(図示せず)によりその回
転角度を検出できるようになっている。なお、前記周方
向移動機構2、多段式ロッド3、水平方向スライド機構
5、押付機構7、探触子ユニット回転機構9等はRPV
外に設置されたコントローラ(図示せず)により駆動制
御されるようになっている。 次に本実施例の作用について説明する。 RPVの溶接部を検査する場合は、第6図に示す如く熱
量交換機等を利用して装置本体1をシュラウド30の上
端にセットし、周方向移動機構2により装置本体1を被
検面近傍へ移動させる。このとき多段式ロッド3はジェ
ットポンプ31(第7図参照)との干渉を防ぐために縮
小した状態にしておく。装置本体1が被検面近傍に到達
したならば周方向移動機構2の駆動を停止し、多段式ロ
ッド3を伸長して検査箇所に導き探触子ユニット部6
A,6Bを被検面に対向させる。そして、押付機構7に
より探触子ユニット部6A,6Bを第7図(a)に示す
如くRPV32の内面に押付けてUTを行う。なお、こ
のときの探触子ユニット部6A,6Bの垂直方向走査は
多段式ロッド3で行い、水平方向走査は水平スライド機
構5または周方向移動機構2で行う。また、シュラウド
部を検査する場合は第7図(b)に示す如くモータ12
により多段式ッド3を180゜回転させた後、上記と同
様の操作を行えばよい。 〔発明の効果〕 以上説明したように本発明によれば、シュラウドの上端
部に取付けられた装置本体をシュラウドの周方向に移動
させると、探触子ユニットが原子炉圧力容器の内周面に
沿って移動し、また多段式ロッドを上下方向に伸縮させ
ると、探触子ユニットが原子炉圧力容器内を上下方向に
移動するので、検査部がBWRの炉心領域のように狭い
場所にある場合でも原子炉圧力容器の溶接部を内側から
超音波探傷をすることができる。また、装置本体をシュ
ラウドの上端部に取付けることにより、本体から検査部
までの距離が短くなり、検査における探触子ユニットの
位置制御の精度をより向上させることができる。TECHNICAL FIELD OF THE INVENTION The present invention relates to an apparatus for performing ultrasonic flaw detection from the inside of a reactor pressure vessel in order to confirm the soundness of a welded portion of the reactor pressure vessel and the internal structure of the reactor. [Technical background of the invention and its problems] Generally, in a nuclear power plant, an ultrasonic flaw detection (hereinafter abbreviated as UT) is performed on a welded portion of a reactor pressure vessel (hereinafter abbreviated as RPV) during its service period. Is obligatory. Therefore, for example, in a pressurized water nuclear power plant, the internal equipment can be taken out, and the size is smaller than the RPV of a boiling water reactor (hereinafter abbreviated as BWR),
UT is performed from the inside of the RPV by using a UT device as shown in FIG. 8 because it is structurally impossible to approach from the outside of the RPV. This UT device is exclusively for a pressurized water reactor (hereinafter abbreviated as PWR), and has a support ring 101 at the center of which a support 102 is provided.
The column 102 is provided with a flaw detection arm 103 that is horizontally expandable and contractable and is rotatable and vertically movable. An ultrasonic transducer 104 is provided at the tip of the flaw detection arm 103, and UT is configured to be performed by pressing the ultrasonic transducer 104 against the inner surface of the RPV by the flaw detection arm 103. Further, the UT device is positioned by fixing the support leg 105 to the flange surface of the RPV. On the other hand, in a boiling water nuclear power plant, it is possible to approach from the outside of the RPV, so UT is performed from the outside of the RPV using a small UT device compatible with the inspection unit.
In the plant constructed before the (in-service inspection) was introduced, it was difficult to UT from the outside because the heat insulating material was in close contact with the outer surface of the RPV. Therefore, using the UT device shown in FIG. A method of performing UT from the inside of RPV has been considered. However, in the BWR, since there are core internal structures such as shrouds and jet pumps that cannot be taken out to the outside in the core region below the RPV, it is true that UT is performed using the PUT dedicated UT device shown in FIG. It's extremely difficult. In addition, the RPV of BWR is longer than that of PWR (for example, 1.1 million kw class PWR, and the distance between the flange bottoms of RPV is about 10 m).
However, in the case of a BWR of 500,000 kW class, it is 10 meters or more), and the inspection part is a narrow place like the core area (the maximum distance between the RPV and the shroud is about 400 mm).
In such a case, the method of supporting the flange surface has a problem in accuracy of the apparatus body. Further, since the UT device shown in FIG. 8 is large, it is difficult to carry it in and out of the plant and the assembling work, and a considerable assembling space is also required. Also, R
Because the structure covers the entire circumference of the flange surface of the PV, it interferes with other operation work, which becomes a critical path and causes another operation flow to be delayed. [Object of the Invention] The object of the present invention has been made in view of such circumstances, and it is possible to perform UT from the inside to the RPV of the BWR that is difficult to approach from the outside, and further, the inspection unit has a core region. Stable and highly accurate UT even in a narrow place like
It is to provide a UT device that is compact and has good operability. [Summary of the Invention] That is, an ultrasonic flaw detector of the present invention is an apparatus body mounted on the upper end of a shroud forming the core of a boiling water nuclear reactor, and is connected to both sides of the apparatus body via joint arms. A circumferential movement mechanism that is movable in the circumferential direction of the shroud, a multi-stage rod that is hung downward from the device body and is vertically expandable and contractible, and rotatable about an axis, and a multi-stage rod of this multi-stage rod. A horizontal arm provided at the lower end, a horizontal slide mechanism for horizontally sliding the horizontal arm, a probe unit rotatably provided at both ends of the horizontal arm, and an atomic unit for the probe unit. And a pressing mechanism for pressing against the inner surface of the furnace pressure vessel,
The circumferential movement mechanism has a pair of rollers that sandwich an upper end portion of the shroud, and at least one of the rollers is rotated to move in the circumferential direction of the shroud. [Embodiment of the Invention] An embodiment of the present invention will be described below with reference to FIGS. 1 to 7. FIG. 1 is a diagram showing a configuration of a UT device according to the present invention, (a) is a front view, (b) is a side view, and (c) is a plan view. This UT device includes a device body 1 set on the upper end of a shroud 30 in the RPV, a circumferential movement mechanism 2 for moving the device body 1 in the circumferential direction of the RPV (arrow α in the figure), and the device body 1 described above. It is rotatably installed vertically and in the RPV axial direction (arrow X in the figure).
A multi-stage rod 3 that is extendable and retractable, a horizontal arm 4 provided at the lower end of the multi-stage rod 3, a horizontal slide mechanism 5 that slides the horizontal arm 4 in the horizontal direction (arrow Y in the figure), and The horizontal arm 4 includes probe unit portions 6A and 6B provided at both ends thereof, and a pressing mechanism 7 for pressing the probe unit portions 6A and 6B together with the horizontal arm 4 onto the inner surface of the RPV. The apparatus body 1 has a hook 11 on the upper surface, and is hung from the upper end of the shroud 30 by a wire rope or the like. As shown in FIG. 2, the stepping motor 1 for driving the multistage rod is provided inside the apparatus main body 1.
2 is provided, and the driving gear 1 is driven by this stepping motor 12.
The rotary gear 14 provided at the upper end of the multi-stage rod 3 is driven via the motor 3. As shown in FIGS. 3 and 4, the circumferential moving mechanism 2 comprises a driving roller 16 and a guide roller 17, and the driving roller 16 is driven by a hydraulic turbine 18 via a gear mechanism 19. There is. The guide roller 17 is pressed against the inner wall side of the shroud 30 by the spring 20, and the guide roller 17 and the drive roller 16 are pressed against each other.
It has a structure in which the upper end portion of 0 is sandwiched so that there is no play. The circumferential movement mechanism 2 is connected to the apparatus main body 1 via a joint arm 15 as shown in FIG. The horizontal slide mechanism 5 is shown in FIGS.
As shown in the figure, a support roller 21 that supports the horizontal arm 4
a, 21b, 21c and 21d and a drive motor 22. Support rollers 21a to 21d are provided so as to slide in guide grooves 23 formed in the upper and lower surfaces of the horizontal arm 4. Further, the motor 22 is provided so as to drive a rack portion 25 provided at a rear portion of the horizontal arm 4 via a drive gear 24. As shown in FIG. 5, the probe unit portions 6A and 6B are composed of a probe unit 8 and a probe unit rotating mechanism 9, and the probe unit 8 is 0 ° and 45 ° with respect to the surface to be inspected, respectively.
Three probes 10a, 10 having an incident angle of °, 60 °
b, 10c. The probe unit rotating mechanism 9 has a function of rotating the probe unit 8 by 270 ° or more, and the rotation angle can be detected by an encoder (not shown). The circumferential movement mechanism 2, the multistage rod 3, the horizontal slide mechanism 5, the pressing mechanism 7, the probe unit rotating mechanism 9 and the like are the RPV.
The drive is controlled by a controller (not shown) installed outside. Next, the operation of this embodiment will be described. When inspecting the welded part of the RPV, as shown in FIG. 6, the device body 1 is set on the upper end of the shroud 30 by using a heat exchanger or the like, and the device 1 is moved to the vicinity of the surface to be inspected by the circumferential movement mechanism 2. To move. At this time, the multistage rod 3 is kept in a contracted state in order to prevent interference with the jet pump 31 (see FIG. 7). When the apparatus body 1 reaches the vicinity of the surface to be inspected, the driving of the circumferential movement mechanism 2 is stopped, the multistage rod 3 is extended and guided to the inspection location, and the probe unit 6
A and 6B are opposed to the surface to be inspected. Then, the pressing unit 7 presses the probe unit portions 6A and 6B against the inner surface of the RPV 32 as shown in FIG. At this time, the probe units 6A and 6B are scanned in the vertical direction by the multistage rod 3, and the horizontal scan is performed by the horizontal slide mechanism 5 or the circumferential movement mechanism 2. When inspecting the shroud portion, the motor 12 is used as shown in FIG. 7 (b).
After rotating the multistage pad 3 by 180 °, the same operation as described above may be performed. As described above, according to the present invention, when the apparatus main body attached to the upper end of the shroud is moved in the circumferential direction of the shroud, the probe unit moves to the inner peripheral surface of the reactor pressure vessel. When the inspection unit is located in a narrow space such as the core region of the BWR, the probe unit moves up and down in the reactor pressure vessel when the multi-stage rod is expanded and contracted in the vertical direction. However, ultrasonic flaw detection can be performed from the inside of the welded portion of the reactor pressure vessel. Further, by mounting the apparatus main body on the upper end portion of the shroud, the distance from the main body to the inspection unit is shortened, and the position control accuracy of the probe unit in the inspection can be further improved.
第1図〜第7図は本発明の一実施例を示す図で、第1図
(a)はUT装置の正面図、同図(b)はその側面図、
同図(c)はその平面図、第2図は第1図のII−II矢視
図、第3図は第1図のIII−III矢視図、第4図は第3図
の、IV−IV矢視図、第5図は第1図のV−V矢視図、第
6図はUT装置をシュラウド上端にセットした状態を示
す斜視図、第7図は探触子ユニットを被検面に押付けた
状態を示す説明図、第8図は従来のUT装置を示す斜視
図である。 1…装置本体、2…周方向移動機構、3…多段式ロッ
ド、4…水平アーム、5…水平方向スライド機構、7…
押付機構、8…探触子ユニット、9…探触子ユニット回
転機構、10a〜10c…探触子。1 to 7 are views showing an embodiment of the present invention, FIG. 1 (a) is a front view of the UT device, and FIG. 1 (b) is a side view thereof.
2C is a plan view thereof, FIG. 2 is a view taken along the line II-II of FIG. 1, FIG. 3 is a view taken along the line III-III of FIG. 1, and FIG. -IV arrow view, FIG. 5 is a VV arrow view of FIG. 1, FIG. 6 is a perspective view showing a state in which the UT device is set on the upper end of the shroud, and FIG. 7 is a probe unit to be inspected. FIG. 8 is an explanatory view showing a state of being pressed against a surface, and FIG. 8 is a perspective view showing a conventional UT device. 1 ... Device body, 2 ... Circumferential movement mechanism, 3 ... Multistage rod, 4 ... Horizontal arm, 5 ... Horizontal slide mechanism, 7 ...
Pressing mechanism, 8 ... Probe unit, 9 ... Probe unit rotating mechanism, 10a-10c ... Probe.
Claims (1)
ドの上端部に載置される装置本体と、この装置本体の両
側にジョイントアームを介して連結され前記シュラウド
の周方向に移動可能な周方向移動機構と、前記装置本体
から下方に垂設され上下方向に伸縮自在であってかつ軸
回りに回転自在な多段式ロッドと、この多段式ロッドの
下端に設けられた水平アームと、この水平アームを水平
方向にスライドさせる水平方向スライド機構と、上記水
平アームの両端部に回転自在に設けられた探触子ユニッ
トと、この探触子ユニットを原子炉圧力容器の内面に押
付ける押付機構とを具備し、前記周方向移動機構は前記
シュラウドの上端部を挟持する一対のローラを有し、こ
れらのローラのうち少なくとも一方のローラを回転させ
てシュラウドの周方向に移動することを特徴とする超音
波探傷装置。1. An apparatus body mounted on an upper end portion of a shroud forming a core of a boiling water reactor, and connected to both sides of the apparatus body via joint arms and movable in the circumferential direction of the shroud. A circumferential movement mechanism, a multi-stage rod vertically extending downward from the main body of the apparatus and rotatable in the vertical direction, and a horizontal arm provided at the lower end of the multi-stage rod, A horizontal slide mechanism that horizontally slides the horizontal arm, a probe unit that is rotatably provided at both ends of the horizontal arm, and a pressing mechanism that presses the probe unit against the inner surface of the reactor pressure vessel. The circumferential movement mechanism has a pair of rollers that sandwich the upper end of the shroud, and at least one of the rollers is rotated to rotate the shroud around the shroud. Ultrasonic flaw detection apparatus characterized by moving countercurrent.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61086102A JPH068809B2 (en) | 1986-04-16 | 1986-04-16 | Ultrasonic flaw detector |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61086102A JPH068809B2 (en) | 1986-04-16 | 1986-04-16 | Ultrasonic flaw detector |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62245153A JPS62245153A (en) | 1987-10-26 |
| JPH068809B2 true JPH068809B2 (en) | 1994-02-02 |
Family
ID=13877342
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61086102A Expired - Lifetime JPH068809B2 (en) | 1986-04-16 | 1986-04-16 | Ultrasonic flaw detector |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH068809B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10008297B2 (en) | 2014-05-15 | 2018-06-26 | Korea Plant Service & Engineering Co., Ltd. | Nuclear reactor equipment transfer apparatus |
Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3485984B2 (en) * | 1995-01-20 | 2004-01-13 | 株式会社東芝 | Furnace inspection system and furnace inspection method |
| US7464596B2 (en) | 2004-09-24 | 2008-12-16 | The Boeing Company | Integrated ultrasonic inspection probes, systems, and methods for inspection of composite assemblies |
| US7640810B2 (en) | 2005-07-11 | 2010-01-05 | The Boeing Company | Ultrasonic inspection apparatus, system, and method |
| JP5398474B2 (en) * | 2009-10-23 | 2014-01-29 | 株式会社東芝 | In-reactor piping work apparatus and in-reactor piping work method |
| CN107688084B (en) * | 2017-05-26 | 2020-11-24 | 山东瑞谱检测技术有限公司 | Metal detector |
| CN110040218A (en) * | 2019-04-30 | 2019-07-23 | 上海海事大学 | Boom type body section weld seam detection vehicle |
| JP7523747B2 (en) * | 2020-07-13 | 2024-07-29 | 株式会社Ihi | Non-destructive Inspection Equipment |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61130867A (en) * | 1984-11-30 | 1986-06-18 | Toshiba Corp | Remote-controlled automatic ultrasonic flaw detector |
| JPH0752181B2 (en) * | 1985-06-26 | 1995-06-05 | バブコツク日立株式会社 | Pressure vessel inspection device |
-
1986
- 1986-04-16 JP JP61086102A patent/JPH068809B2/en not_active Expired - Lifetime
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10008297B2 (en) | 2014-05-15 | 2018-06-26 | Korea Plant Service & Engineering Co., Ltd. | Nuclear reactor equipment transfer apparatus |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS62245153A (en) | 1987-10-26 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EXPY | Cancellation because of completion of term |