JPH11190790A - Welding bevel inspection device of reactor shroud - Google Patents

Welding bevel inspection device of reactor shroud

Info

Publication number
JPH11190790A
JPH11190790A JP9360191A JP36019197A JPH11190790A JP H11190790 A JPH11190790 A JP H11190790A JP 9360191 A JP9360191 A JP 9360191A JP 36019197 A JP36019197 A JP 36019197A JP H11190790 A JPH11190790 A JP H11190790A
Authority
JP
Japan
Prior art keywords
shroud
inspection device
groove
welding
welding groove
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
JP9360191A
Other languages
Japanese (ja)
Inventor
Yoshiro Matsui
芳郎 松井
Shuji Tamura
秀志 田村
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to JP9360191A priority Critical patent/JPH11190790A/en
Publication of JPH11190790A publication Critical patent/JPH11190790A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Length Measuring Devices By Optical Means (AREA)

Abstract

PROBLEM TO BE SOLVED: To confirm integrity of a welding bevel part by measuring the root gap size of the welding bevel part of a shroud and a shroud support set in a reactor pressure vessel and the crossing size of a welding joint face. SOLUTION: A duct for welding bevel drying 12 is provided inside a shroud 1, a turn rail 13 is provided on the duct 12, and a bevel inspection device body 10 is attached through a turn device 11 on the rail 13. The bevel inspection device body 10 is provided with a laser type shape measuring sensor 14 and a laser range finder 15. In addition, the bevel inspection device body is connected through the electric cable 17 of a controller 16, which is set on an operation floor, and calculator processing of measured data and display of a measured result are performed by remote control.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は原子炉内シュラウド
取替時において新シュラウドとシュラウドサポートとの
溶接開先部寸法を遠隔自動で測定する原子炉内シュラウ
ドの開先検査装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an apparatus for inspecting a groove of a shroud in a reactor for automatically and remotely measuring a groove size of a welding portion between a new shroud and a shroud support when replacing the shroud in the reactor.

【0002】[0002]

【従来の技術】沸騰水型原子炉では原子炉圧力容器内に
炉心支持板と上部格子板を保持し、燃料集合体全体を包
んで炉心を形成するためのシュラウドが設置されてい
る。このシュラウドは円筒状で、上中下部のシュラウド
胴からなっている。
2. Description of the Related Art In a boiling water reactor, a shroud for holding a core support plate and an upper lattice plate in a reactor pressure vessel and surrounding the entire fuel assembly to form a core is provided. The shroud has a cylindrical shape and includes upper, middle and lower shroud bodies.

【0003】長年使用した原子炉では原子炉内のシュラ
ウドの溶接部やその近傍の材料に割れ等の欠陥が生じる
ことがあり、欠陥が生じたシュラウドは状況により新し
いシュラウドに交換する必要が出てくる。このシュラウ
ド交換時に新シュラウドとそれを載せるシュラウドサポ
ートとの溶接が行われ、溶接作業開始前の溶接開先の健
全性を確認するため開先寸法検査を行わなければならな
い。
In a reactor that has been used for many years, a defect such as a crack may occur in a welded portion of a shroud in the reactor or in a material in the vicinity thereof, and the shroud having the defect needs to be replaced with a new shroud depending on circumstances. come. When the shroud is replaced, welding is performed between the new shroud and the shroud support on which the new shroud is mounted, and a groove dimension inspection must be performed to check the soundness of the weld groove before starting the welding operation.

【0004】従来の技術を使用するとシュラウド内側よ
り機械的計測器具を使ってルート間隔、すなわち開先間
の隙間を計測し、また別の機械的計測器具を使って継手
面の食い違いすなわち継手面の段差を計測しなければな
らなかった。
Using the conventional technique, the route interval, ie, the gap between the grooves, is measured from the inside of the shroud using a mechanical measuring instrument, and the gap between the joint faces, ie, the joint surface is measured using another mechanical measuring instrument. I had to measure the steps.

【0005】図3と図4は従来の開先検査装置を使用し
た場合の概略断面図である。図3においてシュラウド1
とシュラウドサポート2で構成される溶接開先部8のル
ート間隔を、ルート間隔検査装置3に付属する厚さゲー
ジ4を開先部に差し込んで水中テレビ5で目視して検査
する。ルート間隔検査装置3は原子炉圧力容器の上方か
らマスト9に吊り下げられ、溶接開先部8の近傍にアク
セスされる。
FIGS. 3 and 4 are schematic cross-sectional views when a conventional groove inspection device is used. In FIG. 3, shroud 1
The route interval of the welding groove portion 8 composed of the groove and the shroud support 2 is visually inspected with the underwater television 5 by inserting the thickness gauge 4 attached to the route interval inspection device 3 into the groove portion. The route interval inspection device 3 is hung on the mast 9 from above the reactor pressure vessel, and is accessed near the welding groove 8.

【0006】また、図4においてシュラウド1とシュラ
ウドサポート2で構成される溶接開先部8の上下部継手
面の食い違いを、食い違い検査装置6に付属する2個の
リニアゲージ7をシュラウド1の内面とシュラウドサポ
ート2の内面に接触させて、各リニアゲージ7の計測値
の差により検査する。食い違い検査装置6は原子炉圧力
容器の上方からマスト9に吊り下げられ、溶接開先部8
の近傍にアクセスされる。
In FIG. 4, the difference between the upper and lower joint surfaces of the welding groove portion 8 composed of the shroud 1 and the shroud support 2 is determined by using two linear gauges 7 attached to the difference inspection device 6 to the inner surface of the shroud 1. And the inner surface of the shroud support 2, and the inspection is performed based on the difference between the measured values of the linear gauges 7. The misalignment inspection device 6 is suspended from above the reactor pressure vessel on the mast 9, and the welding groove 8 is provided.
Is accessed in the vicinity of

【0007】[0007]

【発明が解決しようとする課題】しかしながら、シュラ
ウド1の取替作業では高放射線下の作業となるので、検
査時間は短くしなければならないが、図3および図4の
場合、厚さゲージ5やリニアゲージ7による検査位置が
不連続であるため、別の検査位置への段取替に時間がか
かり、検査時間を短くすることは難しいという課題があ
る。
However, since the replacement work of the shroud 1 is performed under high radiation, the inspection time must be shortened. However, in the case of FIGS. 3 and 4, the thickness gauge 5 or the like is required. Since the inspection position by the linear gauge 7 is discontinuous, it takes time to change over to another inspection position, and there is a problem that it is difficult to shorten the inspection time.

【0008】本発明は、上記課題を解決するためになさ
れたもので、1種類の検査装置で必要な寸法計測を一度
に行い、検査位置を連続的に行うことができ、しかも計
測応答性の良好な検査時間の短い開先検査装置およびそ
の方法を提供することを目的とする。
SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and it is possible to perform necessary dimension measurement at a time with one type of inspection apparatus at a time, and to continuously perform inspection positions, and furthermore, it is possible to obtain measurement responsiveness. An object of the present invention is to provide a groove inspection apparatus and a method thereof that have a good short inspection time.

【0009】[0009]

【課題を解決するための手段】請求項1の発明は、原子
炉圧力容器内に設置したシュラウドとシュラウドサポー
トとの溶接開先部の寸法を測定するレーザー方式の形状
測定器およびレーザー方式の距離計を内蔵した開先検査
装置本体と、この開先検査装置本体に接続するオペレー
ションフロア上に設置したコントローラに接続してなる
ことを特徴とする。
A first aspect of the present invention is a laser type shape measuring instrument for measuring the dimension of a welding groove between a shroud and a shroud support installed in a reactor pressure vessel, and a laser type distance measuring apparatus. It is characterized in that it is connected to a groove inspection device main body containing a gauge and a controller installed on an operation floor connected to the groove inspection device main body.

【0010】請求項1に対応する発明によれば、シュラ
ウド内側から遠隔自動で検査する装置で、開先寸法計測
のためレーザー式形状測定センサヘッドとコントローラ
を有し、レーザー式形状測定センサヘッドはレーザー光
の高速スキャン操作および光位置検出素子により開先部
の形状を短時間で計測し、必要なルート間隔および継手
面の食い違いの検査を同時に行い、コントローラは計測
データの計算機処理および計測結果の表示を行う。
According to the first aspect of the present invention, there is provided an apparatus for remotely and automatically inspecting from the inside of a shroud, comprising a laser type shape measuring sensor head and a controller for measuring a groove dimension. The shape of the groove portion is measured in a short time by the high-speed scanning operation of the laser beam and the optical position detection element, the required route interval and the joint surface are checked at the same time, and the controller performs the computer processing of the measurement data and the measurement result Display.

【0011】請求項2の発明は、前記開先検査装置本体
は前記シュラウドの内周を旋回する旋回装置に取着され
前記旋回装置は旋回レールに懸架されて走行し、前記旋
回レールは開先部乾燥用ダクトに設けられていることを
特徴とする。
According to a second aspect of the present invention, the groove inspection device main body is attached to a turning device that turns around the inner periphery of the shroud, and the turning device runs while being suspended on a turning rail. It is characterized in that it is provided in a drying duct.

【0012】請求項2に対応する発明によれば、シュラ
ウド取替時にシュラウド内に必要で溶接開先部に全周に
わたって沿っている溶接開先部乾燥用ダクトを利用し
て、その下部にレールを設置し、開先検査装置本体と旋
回装置をレールに取り付け、開先検査装置をシュラウド
内全周にわたって旋回させる。
According to the second aspect of the present invention, when the shroud is replaced, the welding groove drying duct which is necessary in the shroud and extends along the entire circumference of the welding groove is used, and a rail is provided below the drying groove. Is installed, the groove inspection device main body and the turning device are attached to the rail, and the groove inspection device is turned around the entire inside of the shroud.

【0013】請求項3の発明は、前記開先検査装置本体
には前記形状測定器のセンサヘッドと前記溶接開先部と
の距離が変化し、形状測定データの精度が低下するのを
防止し、前記形状測定センサヘッドから新シュラウド内
壁にレーザー光を発し距離の変化を検出して前記形状測
定データを自動補正する機能を有することを特徴とす
る。
According to a third aspect of the present invention, the distance between the sensor head of the shape measuring device and the welding groove portion is prevented from being reduced in the groove inspection device main body, thereby preventing the accuracy of the shape measurement data from being reduced. A laser beam is emitted from the shape measurement sensor head to the inner wall of the new shroud to detect a change in distance and automatically correct the shape measurement data.

【0014】次に、請求項3に対応する発明によれば、
レーザー式形状測定において形状測定センサヘッドと開
先部との距離が変化し形状測定データの精度が低下する
のを防止するため、形状測定センサヘッドからシュラウ
ド内壁にレーザー光を発し距離の変化を検出して形状測
定データを自動補正する機能を有する。
Next, according to the invention corresponding to claim 3,
In order to prevent the distance between the shape measurement sensor head and the groove part from changing in the laser type shape measurement, the accuracy of the shape measurement data is reduced, the laser beam is emitted from the shape measurement sensor head to the inner wall of the shroud and the change in distance is detected. And automatically corrects the shape measurement data.

【0015】[0015]

【発明の実施の形態】図1および図2により本発明に係
る原子炉内シュラウドの開先検査装置の実施の形態を説
明する。図1は本実施の形態に係る開先検査装置を一部
ブロックで示す縦断面図であり、図2は本実施の形態の
開先検査装置を原子炉圧力容器内に設置してシュラウド
とシュラウドサポートとの開先部を検査している状態を
示している。
1 and 2, an embodiment of a groove inspection apparatus for a shroud in a nuclear reactor according to the present invention will be described. FIG. 1 is a longitudinal sectional view partially showing a groove inspection device according to the present embodiment in a block diagram. FIG. 2 is a diagram illustrating a groove shroud and a shroud obtained by installing the groove inspection device according to the present embodiment in a reactor pressure vessel. This shows a state where the groove with the support is being inspected.

【0016】すなわち、図1において、シュラウド1と
シュラウドサポート2との溶接開先部8の寸法を測定す
るレーザー方式の形状測定器14とレーザー方式の距離計
15を内蔵した開先検査装置本体10を前記溶接開先部8の
前方に配置する。開先検査装置本体10には旋回装置11が
取着され、旋回装置11は開先部乾燥用ダクト12に取着さ
れている旋回レール13に嵌め込むことにより旋回する。
That is, in FIG. 1, a laser type shape measuring device 14 for measuring the dimensions of a welding groove 8 between the shroud 1 and the shroud support 2 and a laser type distance meter
A groove inspection device main body 10 having a built-in groove 15 is disposed in front of the welding groove 8. A turning device 11 is attached to the groove inspection device main body 10, and the turning device 11 turns by being fitted into a turning rail 13 attached to a groove drying duct 12.

【0017】開先検査装置本体10のレーザー方式の形状
測定器14とレーザー方式の距離計15および旋回装置11は
コントローラ16に電気ケーブル17を介して接続される。
コントローラ16はオペレーションフロア(図示せず)に
設置され、開先検査装置を遠隔操作する。形状測定器14
はセンサヘッドを溶接開先部8に対向するように構成
し、センサヘッドを複数個設けておくことが望ましい。
The laser type shape measuring device 14, the laser type distance meter 15 and the turning device 11 of the groove inspection device main body 10 are connected to a controller 16 via an electric cable 17.
The controller 16 is installed on an operation floor (not shown) and remotely controls the groove inspection device. Shape measuring instrument 14
Preferably, the sensor head is configured to face the welding groove 8 and a plurality of sensor heads are provided.

【0018】つぎに、図2により上記構成の開先検査装
置により原子炉内シュラウドの溶接開先部8の検査方法
を説明する。図2において、符号18は原子炉圧力容器
で、上蓋を取り外した状態で示している。符号19は天井
クレーンで、オペレーションフロア(図示せず)を走行
する燃料交換機(図示せず)から吊り下げられている。
天井クレーン19にはシュラウド1を原子炉圧力容器18内
に吊り込むためのシュラウド保持具20が取着されてお
り、シュラウド保持具20には開先検査装置を溶接開先部
8にアクセスさせるためのマスト9が取着されている。
マスト9には開先部乾燥用ダクト12が取着されている。
Next, a method of inspecting the weld groove 8 of the shroud in the reactor by the groove inspection apparatus having the above-mentioned configuration will be described with reference to FIG. In FIG. 2, reference numeral 18 denotes a reactor pressure vessel with an upper lid removed. Reference numeral 19 denotes an overhead crane, which is suspended from a refueling machine (not shown) running on an operation floor (not shown).
A shroud holder 20 for hanging the shroud 1 into the reactor pressure vessel 18 is attached to the overhead crane 19. The shroud holder 20 allows a groove inspection device to access the welding groove 8. Mast 9 is attached.
The mast 9 has a groove drying duct 12 attached thereto.

【0019】なお、図2中、符号21はジェットポンプ,
22はディフューザ,23はバッフルプレート,24はライザ
ー管,25はライザーブレースアーム,26は給水ノズル,
27は主蒸気ノズル,28は制御棒案内管群である。
In FIG. 2, reference numeral 21 denotes a jet pump,
22 is a diffuser, 23 is a baffle plate, 24 is a riser tube, 25 is a riser brace arm, 26 is a water supply nozzle,
27 is a main steam nozzle and 28 is a control rod guide tube group.

【0020】シュラウド取替作業においては図2のよう
にシュラウド1を原子炉圧力容器18内に天井クレーン19
を用いて吊り込み、シュラウドサポート2の端面の上に
設置するが、図1に示すようにシュラウド1とシュラウ
ドサポート2の溶接開先部8を検査するため、開先検査
装置本体10および旋回装置11を溶接開先部乾燥用ダクト
12の下面に取り付けた旋回レール13に取り付ける。開先
検査装置本体10にレーザー式形状測定センサ14と自動補
正用レーザー距離計15を予め組み込んでおく必要があ
る。
In the shroud replacement operation, the shroud 1 is placed in the reactor pressure vessel 18 as shown in FIG.
And is installed on the end face of the shroud support 2. As shown in FIG. 1, the groove inspection device body 10 and the turning device are used to inspect the welding groove 8 of the shroud 1 and the shroud support 2. 11 for welding groove drying duct
Attach it to the turning rail 13 attached to the lower surface of 12. It is necessary to previously incorporate a laser-type shape measurement sensor 14 and a laser distance meter 15 for automatic correction into the groove inspection device body 10.

【0021】次に検査の方法を説明する。開先検査装置
本体10は旋回装置11により旋回レール13に沿ってシュラ
ウド1の内周を移動する。移動しながらレーザー式形状
測定センサ14はシュラウド1とシュラウドサポート2の
溶接開先部8の形状を短時間に計測し、表示器を兼ねた
コントローラ16にデータを送る。
Next, an inspection method will be described. The groove inspection device main body 10 is moved on the inner periphery of the shroud 1 along the turning rail 13 by the turning device 11. While moving, the laser type shape measuring sensor 14 measures the shape of the welding groove 8 of the shroud 1 and the shroud support 2 in a short time, and sends data to the controller 16 which also functions as a display.

【0022】自動補正用レーザー距離計15は移動しなが
ら同時にシュラウド1と開先検査装置本体10との距離を
短時間に計測し、コントローラ16にデータを送る。コン
トローラ16は両者のデータを計算機処理し、距離補正し
た正確な溶接開先部8の寸法、すなわちルート間隔およ
び継手面の食い違いの検査結果を全周にわたって連続的
に表示し、また記憶する。
The laser distance meter 15 for automatic correction measures the distance between the shroud 1 and the groove inspection apparatus body 10 in a short time while moving, and sends data to the controller 16. The controller 16 performs computer processing on both data, and continuously displays and stores the exact dimensions of the weld groove 8 with the distance corrected, that is, the inspection results of the route interval and the misalignment of the joint surface over the entire circumference.

【0023】旋回装置11はポテンショメータを内蔵し位
置検出ができる。予め設定した寸法公差から外れた場合
はその旨を表示することも可能である。これらは遠隔操
作によって行われ、全周の計測位置を連続的に計測で
き、計測の応答性が良好なので検査時間を短くすること
ができる。
The turning device 11 has a built-in potentiometer and can detect the position. If the dimensional tolerance deviates from the preset dimensional tolerance, it is also possible to display that fact. These operations are performed by remote control, and the measurement positions on the entire circumference can be continuously measured. Since the measurement response is good, the inspection time can be shortened.

【0024】[0024]

【発明の効果】本発明によれば水中、気中を問わず遠隔
操作で溶接開先部の健全性確認の検査ができ、レーザー
方式形状測定センサを組み込んでいることにより、ルー
ト間隔と継手面の食い違いを同時に短時間で計測でき、
旋回装置によりシュラウドの内周を全周にわたって連続
的に検査できる。したがって、検査作業が容易で、検査
時間を短縮できる。
According to the present invention, the integrity of the weld groove can be inspected by remote control regardless of whether it is in the water or in the air. By incorporating a laser type shape measuring sensor, the route interval and the joint surface can be checked. Can be measured simultaneously in a short time,
The swirl device allows the inner circumference of the shroud to be inspected continuously over the entire circumference. Therefore, the inspection work is easy and the inspection time can be reduced.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明に係る原子炉内シュラウドの開先検査装
置の実施の形態を一部ブロックで示す縦断面図。
FIG. 1 is a longitudinal sectional view showing an embodiment of a groove inspection apparatus for a shroud in a nuclear reactor according to the present invention by partial blocks.

【図2】本発明に係る開先検査装置を原子炉圧力容器内
に設置して検査する方法を説明するための概略図。
FIG. 2 is a schematic view for explaining a method of installing and inspecting a groove inspection apparatus according to the present invention in a reactor pressure vessel.

【図3】従来の開先検査装置の第1の例を一部ブロック
で示す縦断面図。
FIG. 3 is a vertical cross-sectional view showing a first example of a conventional groove inspection device in partial blocks.

【図4】従来の開先検査装置の第2の例を一部ブロック
で示す縦断面図。
FIG. 4 is a longitudinal sectional view showing a second example of a conventional groove inspection device in a partial block.

【符号の説明】[Explanation of symbols]

1…シュラウド、2…シュラウドサポート、3…ルート
間隔検査装置、4…厚さゲージ、5…水中テレビ、6…
食い違い検査装置、7…リニアゲージ、8…開先部、9
…マスト、10…開先検査装置本体、11…旋回装置、12…
開先部乾燥用ダクト、13…旋回レール、14…レーザー方
式形状測定器、15…レーザー距離計、16…コントロー
ラ、17…電気ケーブル、18…原子炉圧力容器、19…天井
クレーン、20…シュラウド保持具、21…ジェットポン
プ、22…ディフューザ、23…バッフルプレート、24…ラ
イザー管、25…ライザーブレースアーム、26…給水ノズ
ル、27…主蒸気ノズル、28…制御棒案内管群。
DESCRIPTION OF SYMBOLS 1 ... Shroud, 2 ... Shroud support, 3 ... Route interval inspection device, 4 ... Thickness gauge, 5 ... Underwater television, 6 ...
Discrepancy inspection device, 7: linear gauge, 8: groove, 9
… Mast, 10… groove inspection device body, 11… turning device, 12…
Groove drying duct, 13 turning rail, 14 laser shape measuring device, 15 laser range finder, 16 controller, 17 electric cable, 18 reactor pressure vessel, 19 overhead crane, 20 shroud Holder, 21: Jet pump, 22: Diffuser, 23: Baffle plate, 24: Riser tube, 25: Riser brace arm, 26: Water supply nozzle, 27: Main steam nozzle, 28: Control rod guide tube group.

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】 原子炉圧力容器内に設置したシュラウド
とシュラウドサポートとの溶接開先部の寸法を測定する
レーザー方式の形状測定器およびレーザー方式の距離計
を内蔵した開先検査装置本体と、この開先検査装置本体
に接続するオペレーションフロア上に設置したコントロ
ーラに接続してなることを特徴とする原子炉内シュラウ
ドの溶接開先検査装置。
1. A groove inspection apparatus main body including a laser type shape measuring device and a laser type distance meter for measuring a dimension of a welding groove portion between a shroud and a shroud support installed in a reactor pressure vessel; A welding groove inspection apparatus for a shroud in a nuclear reactor, wherein the apparatus is connected to a controller installed on an operation floor connected to the groove inspection apparatus body.
【請求項2】 前記開先検査装置本体は前記シュラウド
の内周を旋回する旋回装置に取着され前記旋回装置は旋
回レールに懸架されて走行し、前記旋回レールは開先部
乾燥用ダクトに設けられていることを特徴とする請求項
1記載の原子炉内シュラウドの溶接開先検査装置。
2. The groove inspection device main body is attached to a turning device that turns around the inner periphery of the shroud, and the turning device runs while being suspended on a turning rail. The turning rail is connected to a groove portion drying duct. The welding groove inspection device for a shroud in a nuclear reactor according to claim 1, wherein the welding groove inspection device is provided.
【請求項3】 前記開先検査装置本体には前記形状測定
器のセンサヘッドと前記溶接開先部との距離が変化し、
形状測定データの精度が低下するのを防止し、前記形状
測定センサヘッドから新シュラウド内壁にレーザー光を
発し距離の変化を検出して前記形状測定データを自動補
正する機能を有することを特徴とする請求項2記載の原
子炉内シュラウドの溶接開先検査装置。
3. The distance between the sensor head of the shape measuring instrument and the welding groove portion changes in the groove inspection device body,
Prevents the accuracy of the shape measurement data from deteriorating, and has a function of emitting a laser beam from the shape measurement sensor head to the inner wall of the new shroud, detecting a change in distance, and automatically correcting the shape measurement data. The welding groove inspection device for a shroud in a nuclear reactor according to claim 2.
JP9360191A 1997-12-26 1997-12-26 Welding bevel inspection device of reactor shroud Pending JPH11190790A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP9360191A JPH11190790A (en) 1997-12-26 1997-12-26 Welding bevel inspection device of reactor shroud

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP9360191A JPH11190790A (en) 1997-12-26 1997-12-26 Welding bevel inspection device of reactor shroud

Publications (1)

Publication Number Publication Date
JPH11190790A true JPH11190790A (en) 1999-07-13

Family

ID=18468305

Family Applications (1)

Application Number Title Priority Date Filing Date
JP9360191A Pending JPH11190790A (en) 1997-12-26 1997-12-26 Welding bevel inspection device of reactor shroud

Country Status (1)

Country Link
JP (1) JPH11190790A (en)

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