JPH1026692A - Repair welding method at inside of reactor pressure vessel and repair welding apparatus used for it - Google Patents

Repair welding method at inside of reactor pressure vessel and repair welding apparatus used for it

Info

Publication number
JPH1026692A
JPH1026692A JP8201195A JP20119596A JPH1026692A JP H1026692 A JPH1026692 A JP H1026692A JP 8201195 A JP8201195 A JP 8201195A JP 20119596 A JP20119596 A JP 20119596A JP H1026692 A JPH1026692 A JP H1026692A
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor pressure
yag laser
reactor
repair welding
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
JP8201195A
Other languages
Japanese (ja)
Inventor
Akira Sato
彰 佐藤
Toru Ozaki
徹 小崎
Toshio Kojima
敏雄 小嶋
Yuji Nagasawa
裕二 長澤
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.)
IHI Corp
Original Assignee
IHI 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 IHI Corp filed Critical IHI Corp
Priority to JP8201195A priority Critical patent/JPH1026692A/en
Publication of JPH1026692A publication Critical patent/JPH1026692A/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

  • Laser Beam Processing (AREA)

Abstract

PROBLEM TO BE SOLVED: To provide a repair welding method, inside a reactor pressure vessel, in which there is no fear of radiation exposure to an operator, in which an approach can be made easily to a narrow part or a part in a complicated shape so as to perform a welding operation while reactor water is filled and in which the operation can be performed in a short construction period and to provide a repair welding apparatus used for it. SOLUTION: A welding-operation mechanism part 10 to which a YAG laser beam is transmitted via an optical fiber cable 41 from a YAG laser oscillator 32 arranged and installed at the outside of a reactor pressure vessel 1, to which a shield gas and a filler wire are supplied from the outside of the reactor pressure vessel 1 and which is provided with a YAG laser torch is sunk inside the reactor pressure vessel 1 filled with reactor water so as to be fixed to a prescribed position, the water is cut off by the shield gas by a remote control operation from the outside of the reactor pressure vessel 1, and a repair welding operation is performed inside the reactor water.

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、原子炉圧力容器内
の溶接箇所に対して補修溶接を行う原子炉圧力容器内の
補修溶接方法及びそれに用いる補修溶接装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a repair welding method in a reactor pressure vessel for performing repair welding on a welding location in a reactor pressure vessel, and a repair welding apparatus used therefor.

【0002】[0002]

【従来の技術】原子力発電所における原子炉圧力容器内
部は、安全のために定期的な点検を行うが、その際に溶
接箇所に不具合が発見された場合には、補修溶接を行う
必要がある。
2. Description of the Related Art The inside of a reactor pressure vessel in a nuclear power plant is regularly inspected for safety. If a defect is found in a welded portion at that time, repair welding must be performed. .

【0003】このような補修溶接の作業方法としては、
炉水を排出した後に作業者が炉内に入って行う方法、炉
水を張ったままで局部遮水によって行う方法、トーチ周
りをシールドガスで遮蔽して行う水中TIG溶接によっ
て行う方法、等が考えられている。
[0003] Such repair welding work methods include:
Possible methods include a method in which an operator enters the furnace after discharging the reactor water, a method in which local water shielding is performed while the reactor water is stretched, and a method in which underwater TIG welding in which the area around the torch is shielded with a shielding gas is used. Have been.

【0004】[0004]

【発明が解決しようとする課題】しかしながら、上記の
ごとき方法では、下記のごとき種々問題点がある。
However, the above method has various problems as described below.

【0005】即ち、原子炉圧力容器内部に満たされた炉
水を排出した後に作業者が炉内に入って行うものでは、
放射線レベルの高い炉内で作業しなければならないた
め、作業者の被ばくを防ぐ手段を講ずる必要があると共
に、炉水の排水や徐染作業等の付帯工事に時間を要し、
工事期間が長期化する。
[0005] That is, in a system in which an operator enters the reactor after draining the reactor water filled in the reactor pressure vessel,
Since it is necessary to work in furnaces with high radiation levels, it is necessary to take measures to prevent workers from being exposed, and it takes time to perform additional work such as drainage of furnace water and slow dyeing work.
Construction period is prolonged.

【0006】また、炉水を張ったままで局部遮水によっ
て行うものでは、遮水装置が必要であるため、狭い箇所
や複雑な形状の箇所等の遮水装置を配設できない場所で
は溶接作業ができないという問題がある。
[0006] Further, in the case of performing local water blocking while maintaining reactor water, a water blocking device is required. Therefore, welding work is performed in a place where a water blocking device such as a narrow portion or a complicated shape cannot be provided. There is a problem that can not be.

【0007】更に、トーチ周りをシールドガスで遮蔽し
て行う水中TIG溶接では、トーチの小型化に限界があ
ると共に、溶接に大電力が必要となるために太く重いケ
ーブルを引き回さなければならず、狭い箇所や複雑な形
状の箇所に接近して溶接作業することは困難なものであ
る。
Further, in underwater TIG welding performed by shielding the periphery of the torch with a shielding gas, there is a limit to downsizing of the torch, and a large and heavy cable must be routed because a large amount of power is required for welding. However, it is difficult to perform welding work in a narrow place or a place having a complicated shape.

【0008】本発明は、上記問題に鑑みてなされたもの
であって、作業者に被ばくの虞がなく、炉水を張ったま
ま狭い箇所や複雑な形状の箇所にも容易に接近して溶接
作業ができ、短い工事期間で作業できる原子炉圧力容器
内の補修溶接方法及びそれに用いる補修溶接装置を提供
することを目的とする。
SUMMARY OF THE INVENTION The present invention has been made in view of the above problems, and has no danger of exposure to an operator. An object of the present invention is to provide a repair welding method in a reactor pressure vessel, which can perform work in a short construction period, and a repair welding apparatus used therefor.

【0009】[0009]

【課題を解決するための手段】上記目的を達成する本発
明に係る原子炉圧力容器内の補修溶接方法は、原子炉圧
力容器外に配設されたYAGレーザー発振器から光ファ
イバーケーブルを介してYAGレーザー光が伝送される
と共に前記原子炉圧力容器外からシールドガスと溶加ワ
イヤーが供給されるYAGレーザートーチを、炉水が張
られた原子炉圧力容器内に沈降させて所定位置に固定
し、前記原子炉圧力容器外から遠隔操作によって前記シ
ールドガスで遮水しつつ前記炉水内で補修溶接を行うこ
とを特徴とする。
According to the present invention, there is provided a method for repairing and welding a reactor pressure vessel inside a reactor pressure vessel according to the present invention, comprising the steps of: providing a YAG laser from a YAG laser oscillator provided outside the reactor pressure vessel via an optical fiber cable; A YAG laser torch to which light is transmitted and a shielding gas and a filler wire are supplied from outside the reactor pressure vessel is settled in a reactor pressure vessel filled with reactor water and fixed at a predetermined position, The present invention is characterized in that repair welding is performed in the reactor water while shielding water with the shield gas by remote control from outside the reactor pressure vessel.

【0010】また、上記原子炉圧力容器内の補修溶接方
法を用いて補修溶接を行う補修溶接装置は、炉水が張ら
れた原子炉圧力容器内に沈降可能な溶接ヘッドと、原子
炉圧力容器外に配設された駆動・制御装置群とが、可撓
性を有する接続部材群によって結ばれて成り、前記溶接
ヘッドは、前記原子炉圧力容器内への固定手段と、移動
機構を介して移動可能に支持されたYAGレーザートー
チとを備え、前記駆動・制御装置群は、YAGレーザー
発振器と、シールドガス供給装置と、溶加ワイヤー供給
装置と、前記溶接ヘッド及び当該駆動・制御装置群全体
を制御する制御装置とを備え、前記接続部材群は、前記
駆動・制御装置群のYAGレーザー発振器から前記溶接
ヘッドのYAGレーザートーチにレーザー光を伝送する
光ファイバーケーブルと、前記シールドガス供給装置か
ら前記YAGレーザートーチへシールドガスを供給する
シールドガス供給管と、前記溶加ワイヤー供給装置から
前記YAGレーザートーチへの溶加ワイヤー供給路と、
電源及び制御信号ケーブルとを備えて構成されているこ
とを特徴とする。
A repair welding apparatus for performing repair welding using the repair welding method in a reactor pressure vessel includes a welding head capable of sinking in a reactor pressure vessel filled with reactor water, a reactor pressure vessel, A drive / control device group disposed outside is connected by a flexible connecting member group, and the welding head is fixed via a fixing means in the reactor pressure vessel and a moving mechanism. A drive / control device group comprising a YAG laser oscillator, a shield gas supply device, a filler wire supply device, the welding head and the drive / control device group as a whole. A connection device group, wherein the connection member group comprises an optical fiber cable for transmitting laser light from a YAG laser oscillator of the drive / control device group to a YAG laser torch of the welding head. Le a, and the shield gas supply device shielding gas supply tube for supplying shielding gas to the YAG laser torch from a filler wire supply path from the filler wire supply apparatus to the YAG laser torch,
It is characterized by comprising a power supply and a control signal cable.

【0011】[0011]

【発明の実施の形態】以下添付図面を参照して本発明の
実施形態について説明する。図1は本発明に係る原子炉
圧力容器内の補修溶接装置の一実施形態による原子炉圧
力容器内の補修溶接作業の概念構成斜視図,図2はその
縦断面図,図3は図2のA−A断面図に相当する上部格
子板の平面図,図4は図2のB−B断面図に相当する炉
心支持板の平面図である。尚、本構成例は、原子炉圧力
容器1の底部である下鏡1Aに溶接配設された制御棒駆
動機構を内蔵するスタブチューブ1Bの周囲角部の溶接
部位の補修溶接を行うものである。
Embodiments of the present invention will be described below with reference to the accompanying drawings. 1 is a perspective view showing a conceptual configuration of a repair welding operation in a reactor pressure vessel according to an embodiment of a repair welding apparatus in a reactor pressure vessel according to the present invention, FIG. 2 is a longitudinal sectional view thereof, and FIG. FIG. 4 is a plan view of the core support plate corresponding to a cross-sectional view taken along the line BB of FIG. 2, and FIG. In this configuration example, repair welding is performed on a welding portion at a corner portion of a stub tube 1B having a built-in control rod driving mechanism which is welded to a lower mirror 1A, which is a bottom portion of the reactor pressure vessel 1. .

【0012】図示補修溶接装置は、原子炉圧力容器1内
で溶接作業を行う溶接作業機構部10と、原子炉圧力容
器1の外部に配設される駆動・制御装置群30とが、接
続部材群としての接続ケーブル40によって結合されて
構成されている。
In the illustrated repair welding apparatus, a welding operation mechanism unit 10 for performing a welding operation in the reactor pressure vessel 1 and a drive / control device group 30 disposed outside the reactor pressure vessel 1 are connected by connecting members. They are connected by connecting cables 40 as a group.

【0013】溶接作業機構部10は、図5にその拡大図
を示すように、上端に固定治具11を備えた所定長さの
パイプ12の下端に溶接ヘッド20が設けられて構成さ
れている。
As shown in an enlarged view of FIG. 5, the welding operation mechanism section 10 has a welding head 20 provided at a lower end of a pipe 12 of a predetermined length provided with a fixing jig 11 at an upper end. .

【0014】パイプ12及び溶接ヘッド20は原子炉圧
力容器1に設けられた炉心支持板3の燃料棒支持孔3A
を通過可能な径に設定される一方、上端の固定治具11
は燃料棒支持孔3Aより大きく設定されており、これに
より、当該溶接作業機構部10を炉心支持板3の燃料棒
支持孔3Aに挿置することで、溶接作業機構部10はス
タブチューブ1Bの配設位置に一致すると共に、固定治
具11が炉心支持板3に係合し、下端の溶接ヘッド20
はスタブチューブ1Bに対して所定の上下位置関係とな
るようになっている。
The pipe 12 and the welding head 20 are provided in the fuel rod support holes 3A of the core support plate 3 provided in the reactor pressure vessel 1.
The fixing jig 11 at the upper end
Is set larger than the fuel rod support hole 3A, whereby the welding operation mechanism unit 10 is inserted into the fuel rod support hole 3A of the core support plate 3 so that the welding operation mechanism unit 10 is connected to the stub tube 1B. At the same time, the fixing jig 11 is engaged with the core support plate 3 and the welding head 20 at the lower end is fixed.
Has a predetermined vertical positional relationship with the stub tube 1B.

【0015】溶接ヘッド20は、図6に拡大斜視図,図
7にスタブチューブ1Bに装着された状態の拡大断面図
を示すように、概略円柱状のケース21の下端部に回転
体22が設けられると共にこの回転体22にアーム23
を介してYAGレーザートーチ24とCCDカメラ25
とが支持されて構成されている。
As shown in an enlarged perspective view of FIG. 6 and an enlarged sectional view of the welding head 20 mounted on the stub tube 1B, a rotary body 22 is provided at the lower end of a substantially cylindrical case 21. Arm 23 is attached to the rotating body 22
YAG laser torch 24 and CCD camera 25 via
Are supported and configured.

【0016】回転体22は、略円盤状であってその中心
に配置された回転軸22Aで回転可能に設けられ、回転
駆動モーター26によって回転駆動されるようになって
いる。また、下面にはスタブチューブ1Bに貫通装着さ
れた制御棒駆動機構のハウジング1Cに嵌合して当該溶
接ヘッド20を位置決め固定する位置決め嵌合凹部22
Bが形成されている。
The rotating body 22 has a substantially disk shape, is rotatably provided on a rotating shaft 22A disposed at the center thereof, and is rotatably driven by a rotation driving motor 26. Further, on the lower surface, a positioning fitting concave portion 22 that fits into the housing 1C of the control rod driving mechanism that is mounted through the stub tube 1B and positions and fixes the welding head 20.
B is formed.

【0017】アーム23は、溶接ヘッド20内に設けら
れたスライド駆動モーター27によって回転体22に対
してスライド移動駆動可能となっていると共に、拡大図
である図8に示すようにその先端部には回転体22の回
転軸22Aを含む同一平面内で屈曲する二つの関節(第
一関節23A,第二関節23B)がそれぞれ内蔵された
図示しない屈曲駆動モーターによって屈曲駆動可能に設
けられている。また、図示しないがアーム23は中空で
あってその内部に後述する光ファイバーケーブル41,
溶加ワイヤー,フレキシブルガスパイプ及びCCDカメ
ラ25の信号ケーブルが挿通されると共に、第一関節2
3Aから溶加ワイヤーガイド23Cが分岐配設されてい
る。
The arm 23 can be slidably moved with respect to the rotating body 22 by a slide drive motor 27 provided in the welding head 20. The arm 23 has a distal end as shown in FIG. Is provided so that two joints (first joint 23A and second joint 23B) that bend in the same plane including the rotation axis 22A of the rotating body 22 can be driven to bend by a bending drive motor (not shown), respectively. Although not shown, the arm 23 is hollow and has an optical fiber cable 41,
The filler wire, the flexible gas pipe and the signal cable of the CCD camera 25 are inserted and the first joint 2
A filler wire guide 23C branches from 3A.

【0018】アーム23に内挿された光ファイバーケー
ブル41とフレキシブルガスパイプはYAGレーザート
ーチ24に接続され、溶加ワイヤー43は溶加ワイヤー
ガイド23CによってYAGレーザートーチ24の先端
部に向けて案内されるようになっている。
The optical fiber cable 41 and the flexible gas pipe inserted in the arm 23 are connected to the YAG laser torch 24, and the filler wire 43 is guided toward the tip of the YAG laser torch 24 by the filler wire guide 23C. It has become.

【0019】CCDカメラ25は第二関節23Bから支
持部材25Aを介して支持されてYAGレーザートーチ
24による溶接部位を撮像し得るように設けられてお
り、YAGレーザートーチ24の移動に伴って移動する
ようになっている。
The CCD camera 25 is supported by the second joint 23B via a support member 25A and is provided so as to be able to image the welding site by the YAG laser torch 24. The CCD camera 25 moves with the movement of the YAG laser torch 24. It has become.

【0020】上記のごとき構成の溶接ヘッド20では、
YAGレーザートーチ24は、アーム23のスライド移
動によって上下に移動可能であると共に、二つの関節2
3A,23Bの屈曲によって回転体22の回転中心に対
して離接可能であり、更に、回転体22の回転によって
回転体22の回転軸22Aを中心とする円弧を描いて移
動可能となっているものである。
In the welding head 20 configured as described above,
The YAG laser torch 24 can be moved up and down by sliding movement of the arm 23, and the two joints 2
By bending the 3A and 23B, the rotating body 22 can be separated from and contacted with the rotation center of the rotating body 22. Further, the rotation of the rotating body 22 can be moved by drawing an arc around the rotating shaft 22A of the rotating body 22. Things.

【0021】各駆動モーター(回転駆動モーター26,
スライド駆動モーター27,屈曲駆動モーター)は、後
述する信号ケーブル及び電源ケーブルが接続された制御
・電源ユニット28に接続されて後述する制御装置31
によって駆動制御されるようになっており、従って、Y
AGレーザートーチ24は、制御装置31による駆動制
御によって上下左右の位置及び向き(姿勢)が変位し、
その姿勢を保って回転体22の回転軸22Aを中心に周
回移動するようになっているものである。
Each drive motor (rotary drive motor 26,
The slide drive motor 27 and the bending drive motor) are connected to a control / power supply unit 28 to which a signal cable and a power cable described later are connected, and are connected to a control device 31 described later.
Is controlled by the
The AG laser torch 24 is vertically and horizontally displaced in position and orientation (posture) by drive control by the control device 31,
The rotating body 22 rotates around the rotation axis 22A of the rotating body 22 while maintaining the posture.

【0022】駆動・制御装置群30は、制御装置31,
YAGレーザー発振器32,シールドガス供給装置3
3,溶加ワイヤー供給装置34とから成っている。
The drive / control device group 30 includes a control device 31,
YAG laser oscillator 32, shield gas supply device 3
3, a filler wire supply device 34.

【0023】制御装置31,YAGレーザー発振器32
及びシールドガス供給装置33はそれぞれ原子炉圧力容
器1の開口床面に配設され、溶加ワイヤー供給装置34
は原子炉圧力容器1の開口部上に架設された支持梁4上
に設けられている。
Control device 31, YAG laser oscillator 32
And a shield gas supply device 33 are disposed on the open floor of the reactor pressure vessel 1, respectively.
Is provided on a support beam 4 laid over the opening of the reactor pressure vessel 1.

【0024】制御装置31は、当該補修溶接装置全体の
駆動制御を行うと共にCCDカメラ25による撮像を受
像するモニターを備えている。
The control device 31 is provided with a monitor that controls the driving of the entire repair welding device and receives an image captured by the CCD camera 25.

【0025】支持梁4は、原子炉圧力容器1の開口部を
挟んで平行に設けられた一対のガイド4A,4Aの間に
架設され、このガイド4Aに案内されてその延説方向に
移動可能となっており、その上に溶加ワイヤー供給装置
34と、固定台35が配設されている。
The support beam 4 is installed between a pair of guides 4A, 4A provided in parallel with the opening of the reactor pressure vessel 1 interposed therebetween, and is guided by the guide 4A to be movable in the extension direction. And a filler wire supply device 34 and a fixing base 35 are disposed thereon.

【0026】固定台35は、支持梁4に沿って移動可能
であり、溶接ヘッド20を吊り下げる吊り下げワイヤー
50を支持すると共に、溶接ヘッド20と可撓性を有す
る接続チューブ40によって接続されている。
The fixed base 35 is movable along the support beam 4, supports a suspension wire 50 for suspending the welding head 20, and is connected to the welding head 20 by a flexible connection tube 40. I have.

【0027】接続チューブ40には、YAGレーザー発
振器32からのYAGレーザーを伝送する光ケーブル4
1と,制御装置31からの制御信号やCCDカメラの画
像信号を伝送する信号ケーブルと,電源ケーブルと,シ
ールドガス供給装置33からシールドガスを供給するフ
レキシブルガスパイプと,溶加ワイヤー供給装置34か
らの溶加ワイヤーが集束されて固定台35を介して内挿
・配索されており、これらケーブル類はそれぞれ溶接ヘ
ッド20の所定部位に接続されている。
An optical cable 4 for transmitting a YAG laser from a YAG laser oscillator 32 is connected to the connection tube 40.
1, a signal cable for transmitting a control signal from the control device 31 and an image signal of the CCD camera, a power cable, a flexible gas pipe for supplying a shield gas from the shield gas supply device 33, and a signal from the filler wire supply device. The filler wires are bundled and inserted and routed through a fixing base 35, and these cables are connected to predetermined portions of the welding head 20, respectively.

【0028】而して、上記のごとく構成された補修溶接
装置は、下記のごとくして原子炉圧力容器1の下鏡1A
に溶接配設されたスタブチューブ1Bの周囲角部の溶接
部位の補修溶接を行う。
Thus, the repair welding apparatus constructed as described above is used for the lower mirror 1A of the reactor pressure vessel 1 in the following manner.
Repair welding is performed on the welded portion at the peripheral corner of the stub tube 1B that is welded and disposed.

【0029】まず、図9(A)に示すように、原子炉建
屋の天井クレーン5を用い、吊り下げワイヤー50を介
して溶接作業機構部10を吊り下げ、炉水を張ったまま
の原子炉圧力容器1内に下ろし、上部格子板2及び炉心
支持板3を通して沈下させる。
First, as shown in FIG. 9 (A), the welding operation mechanism 10 is suspended via the suspension wire 50 by using the overhead crane 5 of the reactor building, and the reactor water is maintained while the reactor water is being stretched. It is lowered into the pressure vessel 1 and is lowered through the upper lattice plate 2 and the core support plate 3.

【0030】これにより、溶接作業機構部10はスタブ
チューブ1Bの真上から降下することになり、図9
(B)に示すように上端の固定治具11が炉心支持板3
に係合することで上下方向の位置が決まり、更に、溶接
ヘッド20の下面の位置決め嵌合凹部22Bが制御棒駆
動機構のハウジング1Cに嵌合して左右方向が位置決め
される。つまり、本構成では、固定治具11と位置決め
嵌合凹部22Bが固定手段を構成しているものである。
As a result, the welding operation mechanism section 10 descends from just above the stub tube 1B, and as shown in FIG.
As shown in (B), the fixing jig 11 at the upper end is
, The position in the vertical direction is determined, and the positioning fitting concave portion 22B on the lower surface of the welding head 20 is fitted to the housing 1C of the control rod drive mechanism, and the position in the horizontal direction is determined. That is, in the present configuration, the fixing jig 11 and the positioning fitting concave portion 22B constitute the fixing means.

【0031】その後、CCDカメラ25による撮像で観
察しつつスライド駆動モーター27を駆動してアーム2
3をスライドさせると共に関節23A,23Bを屈曲さ
せてYAGレーザートーチ24の位置及び角度(姿勢)
を、補修溶接部位(スタブチューブ1Bの周囲角部)と
対応するように設定し、補修溶接を行う。即ち、シール
ドガス供給装置33からアルゴンガス等の不活性ガスを
溶接部位に供給して遮水しつつYAGレーザー発振器3
2からのYAGレーザー光を光ファイバーケーブル41
を介して伝送すると共に溶加ワイヤー供給装置34から
溶加ワイヤーを供給し、回転駆動モーター26の駆動に
よって回転体22を回転させてYAGレーザートーチ2
4を溶接部位に沿って移動させて補修溶接を行うもので
ある。その際、溶接状況をCCDカメラ25による撮像
でモニターすることができる。
Thereafter, the slide drive motor 27 is driven while observing the image by the CCD camera 25 and the arm 2 is driven.
3 and the joints 23A and 23B are bent to position and angle (posture) the YAG laser torch 24.
Is set to correspond to the repair welding site (the peripheral corner of the stub tube 1B), and repair welding is performed. That is, an inert gas such as an argon gas is supplied from the shielding gas supply device 33 to the welding portion to block water, and the YAG laser oscillator 3
Optical fiber cable 41 from YAG laser light from
And a filler wire is supplied from a filler wire supply device 34, and the rotating body 22 is rotated by the drive of the rotary drive motor 26 to rotate the YAG laser torch 2.
4 is moved along the welding portion to perform repair welding. At this time, the welding status can be monitored by imaging with the CCD camera 25.

【0032】尚、上記構成例は、原子炉圧力容器1の下
鏡1Aに溶接配設されたスタブチューブ1Bの周囲角部
の溶接部位の補修溶接を行う例であるが、本願発明は当
該部位に限らずシュラウドサポート等他の部位の補修溶
接にも適用可能なものである。また、固定手段も上記構
成に限るものではなく、把持機構やマグネットを利用す
る等他の機構としても良いものである。
The above configuration example is an example in which repair welding is performed on a welded portion at a peripheral corner of a stub tube 1B that is welded to the lower mirror 1A of the reactor pressure vessel 1, and the present invention is applied to such a portion. The present invention can be applied not only to repair welding of other parts such as a shroud support but also to other parts. Further, the fixing means is not limited to the above-described configuration, but may be another mechanism such as a mechanism using a gripping mechanism or a magnet.

【0033】[0033]

【発明の効果】以上述べたように、本発明に係る原子炉
圧力容器内の補修溶接方法及びそれに用いる補修溶接装
置によれば、作業者が直接原子炉圧力容器内で作業する
ことなく遠隔操作によって溶接を行うため、原子炉圧力
容器内に炉水を張ったままで作業が可能であって作業者
に被ばくの虞がなく、遮蔽構造物も不要であることから
狭い箇所や複雑な形状の箇所にも容易に接近して溶接作
業ができると共に、工事期間の短縮が可能となるもので
ある。
As described above, according to the repair welding method in the reactor pressure vessel and the repair welding apparatus used therein according to the present invention, the operator can remotely operate the reactor pressure vessel without directly working in the reactor pressure vessel. Since the welding is performed by welding, it is possible to work while the reactor water is kept in the reactor pressure vessel, there is no risk of exposure to workers, and no shielding structure is required, so narrow places or places with complicated shapes The welding work can be easily performed by approaching the work, and the construction period can be shortened.

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

【図1】本発明に係る原子炉圧力容器内の補修溶接装置
の一実施形態による原子炉圧力容器内の補修溶接作業の
概念構成斜視図である。
FIG. 1 is a conceptual configuration perspective view of a repair welding operation in a reactor pressure vessel according to an embodiment of a repair pressure welding apparatus in a reactor pressure vessel according to the present invention.

【図2】図1の縦断面図に相当する図である。FIG. 2 is a view corresponding to the longitudinal sectional view of FIG.

【図3】図2のA−A断面図に相当する上部格子板の平
面図である。
FIG. 3 is a plan view of an upper lattice plate corresponding to a cross-sectional view taken along the line AA of FIG. 2;

【図4】図2のB−B断面図に相当する炉心支持板の平
面図である。
FIG. 4 is a plan view of a core support plate corresponding to the BB cross-sectional view of FIG. 2;

【図5】溶接作業機構部の拡大図である。FIG. 5 is an enlarged view of a welding operation mechanism.

【図6】溶接ヘッドの下面を示す斜視図である。FIG. 6 is a perspective view showing a lower surface of the welding head.

【図7】溶接ヘッドのスタブチューブへの装着状態にお
ける縦断面図である。
FIG. 7 is a longitudinal sectional view in a state where the welding head is mounted on a stub tube.

【図8】YAGレーザートーチ部分の拡大図である。FIG. 8 is an enlarged view of a YAG laser torch part.

【図9】(A),(B)は補修溶接の際における溶接作
業機構部の設置手順を説明する図である。
FIGS. 9A and 9B are diagrams illustrating a procedure for installing a welding operation mechanism during repair welding.

【符号の説明】[Explanation of symbols]

1 原子炉圧力容器 10 溶接作業機構部 11 固定治具(固定手段) 20 溶接ヘッド 22 回転体(移動機構) 22A 回転軸(移動機構) 22B 位置決め嵌合凹部(固定手段) 23 アーム(移動機構) 23A 第一関節(移動機構) 23B 第二関節(移動機構) 24 YAGレーザートーチ 26 回転駆動モーター(移動機構) 27 スライド移動モーター(移動機構) 30 駆動・制御装置群 31 制御装置 32 YAGレーザー発振器 33 シールドガス供給装置 34 溶加ワイヤー供給装置 40 接続チューブ(接続部材群) 41 光ファイバーケーブル 43 溶加ワイヤー DESCRIPTION OF SYMBOLS 1 Reactor pressure vessel 10 Welding work mechanism part 11 Fixing jig (fixing means) 20 Welding head 22 Rotating body (moving mechanism) 22A Rotating shaft (moving mechanism) 22B Positioning fitting recess (fixing means) 23 Arm (moving mechanism) 23A First joint (moving mechanism) 23B Second joint (moving mechanism) 24 YAG laser torch 26 Rotary drive motor (moving mechanism) 27 Slide moving motor (moving mechanism) 30 Drive / control device group 31 Controller 32 YAG laser oscillator 33 Shield gas supply device 34 filler wire supply device 40 connection tube (connection member group) 41 optical fiber cable 43 filler wire

───────────────────────────────────────────────────── フロントページの続き (72)発明者 小嶋 敏雄 神奈川県横浜市磯子区新中原町1番地 石 川島播磨重工業株式会社横浜エンジニアリ ングセンター内 (72)発明者 長澤 裕二 神奈川県横浜市磯子区新中原町1番地 石 川島播磨重工業株式会社横浜エンジニアリ ングセンター内 ──────────────────────────────────────────────────の Continuing on the front page (72) Inventor Toshio Kojima 1 Shin-Nakahara-cho, Isogo-ku, Yokohama-shi, Kanagawa Ishikawashima-Harima Heavy Industries, Ltd. Inside the Yokohama Engineering Center (72) Inventor Yuji Nagasawa Isogo-ku, Yokohama-shi, Kanagawa 1 Shin-Nakaharacho Ishi Kawashima-Harima Heavy Industries, Ltd. Yokohama Engineering Center

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 原子炉圧力容器外に配設されたYAGレ
ーザー発振器から光ファイバーケーブルを介してYAG
レーザー光が伝送されると共に前記原子炉圧力容器外か
らシールドガスと溶加ワイヤーが供給されるYAGレー
ザートーチを、炉水が張られた原子炉圧力容器内に沈降
させて所定位置に固定し、前記原子炉圧力容器外から遠
隔操作によって前記シールドガスで遮水しつつ前記炉水
内で補修溶接を行うことを特徴とする原子炉圧力容器内
の補修溶接方法。
1. A YAG laser oscillator disposed outside a reactor pressure vessel is connected to a YAG laser oscillator via an optical fiber cable.
A laser beam is transmitted and a YAG laser torch to which a shielding gas and a filler wire are supplied from outside the reactor pressure vessel is settled in a reactor pressure vessel filled with reactor water and fixed at a predetermined position, A repair welding method in a reactor pressure vessel, wherein repair welding is performed in the reactor water while shielding water with the shield gas by remote control from outside the reactor pressure vessel.
【請求項2】 炉水が張られた原子炉圧力容器内に沈降
可能な溶接ヘッドと、原子炉圧力容器外に配設された駆
動・制御装置群とが、可撓性を有する接続部材群によっ
て結ばれて成り、 前記溶接ヘッドは、前記原子炉圧力容器内への固定手段
と、移動機構を介して移動可能に支持されたYAGレー
ザートーチとを備え、 前記駆動・制御装置群は、YAGレーザー発振器と、シ
ールドガス供給装置と、溶加ワイヤー供給装置と、前記
溶接ヘッド及び当該駆動・制御装置群全体を制御する制
御装置とを備え、 前記接続部材群は、前記駆動・制御装置群のYAGレー
ザー発振器から前記溶接ヘッドのYAGレーザートーチ
にレーザー光を伝送する光ファイバーケーブルと、前記
シールドガス供給装置から前記YAGレーザートーチへ
シールドガスを供給するシールドガス供給管と、前記溶
加ワイヤー供給装置から前記YAGレーザートーチへの
溶加ワイヤー供給路と、電源及び制御信号ケーブルとを
備えて構成されていることを特徴とする請求項1に記載
の原子炉圧力容器内の補修溶接方法に用いる補修溶接装
置。
2. A connecting member group comprising: a welding head capable of sinking into a reactor pressure vessel filled with reactor water; and a drive / control device group disposed outside the reactor pressure vessel, comprising a flexible connecting member group. Wherein the welding head comprises: means for fixing the reactor head inside the reactor pressure vessel; and a YAG laser torch movably supported via a moving mechanism. A laser oscillator, a shield gas supply device, a filler wire supply device, and a control device that controls the welding head and the entire drive / control device group, wherein the connection member group is a drive / control device group. An optical fiber cable for transmitting laser light from a YAG laser oscillator to a YAG laser torch of the welding head; and a shielding gas from the shielding gas supply device to the YAG laser torch. 2. The apparatus according to claim 1, further comprising a shield gas supply pipe for supplying, a filler wire supply path from the filler wire supply device to the YAG laser torch, and a power and control signal cable. A repair welding apparatus used for the repair welding method in a reactor pressure vessel described in the above.
JP8201195A 1996-07-11 1996-07-11 Repair welding method at inside of reactor pressure vessel and repair welding apparatus used for it Pending JPH1026692A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP8201195A JPH1026692A (en) 1996-07-11 1996-07-11 Repair welding method at inside of reactor pressure vessel and repair welding apparatus used for it

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP8201195A JPH1026692A (en) 1996-07-11 1996-07-11 Repair welding method at inside of reactor pressure vessel and repair welding apparatus used for it

Publications (1)

Publication Number Publication Date
JPH1026692A true JPH1026692A (en) 1998-01-27

Family

ID=16436927

Family Applications (1)

Application Number Title Priority Date Filing Date
JP8201195A Pending JPH1026692A (en) 1996-07-11 1996-07-11 Repair welding method at inside of reactor pressure vessel and repair welding apparatus used for it

Country Status (1)

Country Link
JP (1) JPH1026692A (en)

Cited By (7)

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EP0977207A1 (en) * 1998-07-27 2000-02-02 Kabushiki Kaisha Toshiba Maintenance system for a reactor incore piping section
JP2005227218A (en) * 2004-02-16 2005-08-25 Toshiba Corp In-furnace maintenance/repair apparatus
JP2009014741A (en) * 2008-10-06 2009-01-22 Toshiba Corp Furnace interior inspecting and repairing device
JP2011085508A (en) * 2009-10-16 2011-04-28 Toshiba Corp Device and method for remote welding
JP2013244498A (en) * 2012-05-24 2013-12-09 Toshiba Corp Device and method for welding
JP2018171657A (en) * 2017-03-31 2018-11-08 日本精工株式会社 Laser welding device, laser processing device, laser welding method, bearing manufacturing method, machine manufacturing method, vehicle manufacturing method, bearing, machine, and vehicle
US11213916B2 (en) 2017-03-31 2022-01-04 Nsk Ltd. Laser machining method

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0977207A1 (en) * 1998-07-27 2000-02-02 Kabushiki Kaisha Toshiba Maintenance system for a reactor incore piping section
US6259759B1 (en) 1998-07-27 2001-07-10 Kabushiki Kaisha Toshiba Incore piping section maintenance system of reactor
US6549602B2 (en) 1998-07-27 2003-04-15 Kabushiki Kaisha Toshiba Incore piping section maintenance system of reactor
JP2005227218A (en) * 2004-02-16 2005-08-25 Toshiba Corp In-furnace maintenance/repair apparatus
JP2009014741A (en) * 2008-10-06 2009-01-22 Toshiba Corp Furnace interior inspecting and repairing device
JP4599443B2 (en) * 2008-10-06 2010-12-15 株式会社東芝 In-furnace inspection device
JP2011085508A (en) * 2009-10-16 2011-04-28 Toshiba Corp Device and method for remote welding
JP2013244498A (en) * 2012-05-24 2013-12-09 Toshiba Corp Device and method for welding
JP2018171657A (en) * 2017-03-31 2018-11-08 日本精工株式会社 Laser welding device, laser processing device, laser welding method, bearing manufacturing method, machine manufacturing method, vehicle manufacturing method, bearing, machine, and vehicle
US11213916B2 (en) 2017-03-31 2022-01-04 Nsk Ltd. Laser machining method
JP2022118112A (en) * 2017-03-31 2022-08-12 日本精工株式会社 Laser processing apparatus, method of manufacturing bearing, method of manufacturing machine, method of manufacturing vehicle, bearing, machine, and vehicle
US11794279B2 (en) 2017-03-31 2023-10-24 Nsk Ltd. Laser machining method

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