JPS6254161A - Checking device for reactor vessel body part - Google Patents

Checking device for reactor vessel body part

Info

Publication number
JPS6254161A
JPS6254161A JP60195233A JP19523385A JPS6254161A JP S6254161 A JPS6254161 A JP S6254161A JP 60195233 A JP60195233 A JP 60195233A JP 19523385 A JP19523385 A JP 19523385A JP S6254161 A JPS6254161 A JP S6254161A
Authority
JP
Japan
Prior art keywords
running
guide
reactor vessel
bodies
inspection
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
JP60195233A
Other languages
Japanese (ja)
Inventor
Yoshiaki Iwao
岩男 義明
Hidekazu Kanai
金井 英一
Atsushi Shirokura
白倉 篤志
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.)
Hitachi Zosen Corp
Original Assignee
Hitachi Zosen 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 Hitachi Zosen Corp filed Critical Hitachi Zosen Corp
Priority to JP60195233A priority Critical patent/JPS6254161A/en
Publication of JPS6254161A publication Critical patent/JPS6254161A/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

  • Investigating Or Analyzing Materials By The Use Of Ultrasonic Waves (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To simplify the structure to facilitate the control of driving operation and to check a reactor vessel body part efficiently by rotating the second guide body itself. CONSTITUTION:The second guide bodies 34a and 34b are rotated. In case of checking in the peripheral direction, the second running body 35a is run and a screw rod is rotated at a prescribed speed forward and backward for every prescribed rotation number while running the first running body 33. Then, probes for transmission and reception are moved back and forth in directions opposite to each other with weld line as the boundary to scan a prescribed range. In case of checking in the axial direction, the running body 33 is run and the second running body 35b is allowed to face the weld line and a driving device for scanning is moved back and forth while running the running body 35b. A probe scans a prescribed range with the weld line as the center. The position of the running body 35a is shifted successively by length corresponding to the scanning range of the probe each time when the running body 33 is rotated once, thereby checking all of the outside peripheral surface of a reactor vessel body part 31.

Description

【発明の詳細な説明】 産業上の利用分野 本発明は、原了炉運転間始後、定Ill的に実施するこ
とが義務づCノられている供用期間中検査のために、近
接不可能な原子炉容器胴部の溶接部の超音波探傷試験を
遠隔操作で自動的に行なう、原子炉容器114部の検査
tA置に関Jるらのである。
DETAILED DESCRIPTION OF THE INVENTION Field of Industrial Application The present invention is useful for in-service inspections that are required to be carried out regularly after the start of operation of a nuclear reactor. This article concerns an inspection of 114 parts of the reactor vessel, in which an ultrasonic flaw detection test of the welded portion of the reactor vessel body is automatically performed by remote control.

従来の技術 従来の原子炉容器胴部の検査装置について、第14図お
よび第15図を用いて説明ザる。第14図は、原子炉容
器1から核燃料や炉内i込物を取出した後、原子炉容器
1内に水中駆動式の検査装置を設置し、内側から溶接部
の超音波探傷試験を行うものを示している。第14図に
おいて、2は水面、3は操作デツキ、4は電力盤、5は
データ集録盤、6は超音波探傷装置本体、7は位置制i
ll盤、8はケーブル、9は旋回架台、10は旋回駆動
装置、11はレール、12はエレベータ、13は垂直駆
動装置、14はスデンレスワイヤ、15は案内枠、16
〜21はマニピュレータ、22は案内ローラ、23は溶
接線である。
2. Description of the Related Art A conventional nuclear reactor vessel barrel inspection apparatus will be explained with reference to FIGS. 14 and 15. Figure 14 shows a system in which, after removing nuclear fuel and other items contained in the reactor from the reactor vessel 1, an underwater inspection device is installed inside the reactor vessel 1, and an ultrasonic flaw detection test is performed on the welds from the inside. It shows. In Fig. 14, 2 is the water surface, 3 is the operation deck, 4 is the power panel, 5 is the data acquisition board, 6 is the ultrasonic flaw detection device main body, and 7 is the position control i.
ll board, 8 is a cable, 9 is a rotating frame, 10 is a rotating drive device, 11 is a rail, 12 is an elevator, 13 is a vertical drive device, 14 is a stainless steel wire, 15 is a guide frame, 16
21 is a manipulator, 22 is a guide roller, and 23 is a welding line.

第15図は、原子炉容器胴部24の外周面に、溶接部に
沿って恒久設置された軌道25上を超音波探傷装置26
を駆動させて超音波探傷試験を行うものを示している。
FIG. 15 shows an ultrasonic flaw detector 26 running along a track 25 permanently installed on the outer peripheral surface of the reactor vessel body 24 along a welded part.
This shows a device that performs ultrasonic flaw detection tests by driving the

ダなわら、軸心方向及び周方向の溶接部に沿って断熱4
427の内側に恒久設置された軌道25を案内として探
傷走行するものであって、軌道25は、軸心方向に沿う
縦軸3C! 25aと周方向に沿う周軌道25bとを連
結し、原子炉遮蔽壁28によりブラケット(図示せず)
を介して支持する一体型4f4造である。縦軌道25a
と周軌道25bとの交点には、ターンデープル29を設
け、ターンテーブル29の回転操作により、超音波探傷
装@26を搭載した駆動装置30は、縦軸3a25a及
び周軌道25bを相互に乗り換えて走行する。
However, the insulation along the axial and circumferential welds is 4.
427, the track 25 is guided by a track 25 that is permanently installed inside the 427, and the track 25 runs along the vertical axis 3C! 25a and the circumferential track 25b along the circumferential direction, and a bracket (not shown) is connected by the reactor shielding wall 28.
It is a one-piece 4f4 structure that is supported through. Vertical track 25a
A turntable 29 is provided at the intersection of the vertical axis 3a25a and the circumferential orbit 25b, and by rotating the turntable 29, the drive device 30 equipped with the ultrasonic flaw detection device @26 travels by switching between the vertical axis 3a25a and the circumferential orbit 25b. do.

発明が解決しようとげる問題点 しかしながら、第14図に示す従来装置では、供用期間
中検査の都度、大型で複雑な形状をした検査装置を精度
良く取付ける必要があり、その作業時間が長くかかるこ
とから、供用期間中検査の期間を長期化させている。ま
た、検査装置の大半が原子炉冷ID水中に没するので、
検査終了後、装置の除染が必要となる。
Problems to be Solved by the Invention However, with the conventional device shown in Fig. 14, it is necessary to mount a large and complicatedly shaped inspection device with high accuracy every time an inspection is carried out during the service period, which takes a long time. , the period of in-service inspections is being extended. Also, since most of the inspection equipment is submerged in the cold reactor ID water,
After the inspection is completed, the equipment must be decontaminated.

また、第15図に示づ従来装置では、軌道25が溶接線
の数だけ必要になり、全体IIII造が複雑になり、設
置費用が高1llIiなしのになる。また探傷走査の箇
所が軌i!25に沿った溶接部に限定きれ、全域にわた
つての検査は行なえなかっl;。
Further, in the conventional device shown in FIG. 15, the number of tracks 25 equal to the number of welding lines is required, making the overall construction complicated and the installation cost extremely high. Also, the location of the flaw detection scan is i! The inspection was limited to the welded area along the line 25, and it was not possible to inspect the entire area.

本発明は上記従来の問題点を解濁した原子炉容器胸部の
検査装置を提供づることを目的とする。
SUMMARY OF THE INVENTION An object of the present invention is to provide an inspection device for the chest of a nuclear reactor vessel that solves the above-mentioned conventional problems.

問題点を解決するための手段 上記問題点を解決するため、本発明の原子炉容器1一部
の検査装置は、原子炉容器胸部の外周面近傍に周方向に
沿って設置された環状の第1の案内体と、この第1の案
内体に案内されて走行する第1の走行体と、+ifi記
原子炉容器胸部の外周面近傍に軸心方向に沿っ′C周方
向適当間隔おきに配置されかつ前記第1の走行体に連結
された複数の第2の案内体と、これら第2の案内体のう
ちの少なくとも2本の第2の案内体に各別に案内きれて
走行する少なくとも2組の第2の走行体と、これら第2
の走行体に各々設置された探触子と、前記第1および第
2の走行体を遠隔操作するための制御装置と、前記各探
触子に電気的に接続された超音波探傷装置本体とを備え
た構成としたものである。
Means for Solving the Problems In order to solve the above problems, a part of the inspection device of the reactor vessel 1 of the present invention has an annular nozzle installed along the circumferential direction near the outer peripheral surface of the chest of the reactor vessel. a first guide body, and a first traveling body guided by the first guide body, which are arranged at appropriate intervals in the circumferential direction along the axial direction near the outer peripheral surface of the chest of the reactor vessel. a plurality of second guide bodies connected to the first running body; and at least two sets of second guide bodies that travel while being individually guided by at least two of the second guide bodies. and these second running bodies.
a control device for remotely controlling the first and second traveling bodies; an ultrasonic flaw detection device main body electrically connected to each of the probes; The configuration is equipped with the following.

作用 上記構成によれば、第2の走行体を静止させて第1の走
行体を走行させることにより、周方向に沿う溶接部を検
査できる。また第1の走行体を静止させて第2の走行体
を走行さけることにより、軸心方向に沿う溶接部を検査
できる。また、第1の走行体を走行させながら第2の走
行体を微速で走行させるか、あるいは第1の走行体の1
回転毎に第2の走行体を所定距離走行させることにより
、原子炉容器胸部全体にわたって検査を行なうことがで
きる。また第2の走行体を少なくとも2飼設け、各々に
探触子を設置したので、第2の走行体を周方向の検査専
用と軸心方向の検査専用とに分けることができ、効率良
く検査を行なうことができる。
Effects According to the above configuration, by keeping the second traveling body stationary and causing the first traveling body to travel, it is possible to inspect the welded portion along the circumferential direction. Furthermore, by keeping the first traveling body stationary and avoiding the second traveling body, the welded portion along the axial direction can be inspected. Also, while the first traveling body is traveling, the second traveling body is made to travel at a slow speed, or one of the first traveling bodies is
By causing the second traveling body to travel a predetermined distance for each rotation, the entire chest of the reactor vessel can be inspected. In addition, since at least two second running bodies are provided and a probe is installed on each, the second running body can be divided into one for circumferential inspection and one for axial inspection, allowing for efficient inspection. can be done.

実施例 以下、本発明の実施例を第1図〜第13図に基づいて説
明する。
Embodiments Hereinafter, embodiments of the present invention will be explained based on FIGS. 1 to 13.

第1図は本発明の一実施例における原子炉容器胴部の検
査装置の全体構成を承り斜視図で、31は原子炉容器胴
部、32は第1の案内体、33は第1の走行体、34a
 〜34cは第2の案内体、35a、35b (よ第2
の走行体、36は離れた場所に設置されたη−Jtll
盤、37は原子炉容器スカート、38はハンドホール、
39は支持台車、40は支持リング、41は連結バー、
42は原子炉遮蔽壁、43はヒンタリング11;ルト、
45aは一方の第2の走行体35aに設置されたモニタ
ー用の層像装置、45bは他方の第2の走行体35bに
設置されたモニター用のfi5 象”A置である。
FIG. 1 is a perspective view of the overall configuration of a reactor vessel body inspection device according to an embodiment of the present invention, in which 31 is a reactor vessel body, 32 is a first guide body, and 33 is a first running member. body, 34a
- 34c are the second guide bodies, 35a, 35b (the second
36 is a η-Jtll installed at a remote location.
board, 37 is the reactor vessel skirt, 38 is the hand hole,
39 is a support cart, 40 is a support ring, 41 is a connecting bar,
42 is a reactor shielding wall, 43 is a hinting ring 11;
Reference numeral 45a denotes a layer imaging device for monitoring installed on one of the second traveling bodies 35a, and 45b denotes a fi5 image device for monitoring installed on the other second traveling body 35b.

なお図示していないが、11う記原子炉巡蔽檗42の内
面には断熱材が張設されている。
Although not shown, a heat insulating material is provided on the inner surface of the reactor enclosure box 42 described in item 11.

前記第1の案内体32は、第2図及び第3図に品τ細に
示すように、原子炉遮蔽壁42の段部に設置された環状
のレールからなり、この第1の案内体32上には、前記
第1の走行体33と支持台中39とが設置されている。
As shown in detail in FIGS. 2 and 3, the first guide body 32 consists of an annular rail installed at the step of the reactor shielding wall 42. Above, the first traveling body 33 and a support platform 39 are installed.

前記第1の走行体33は、前記支持台車39と同様の構
成の台車部33aと、この台車部33aを第1の案内体
32に沿って走行させる駆動部33bとから構成されて
おり、周方向等間隔おきに複数(本実施例では3個)設
けられている。前記支持台車39も第1の走行体33間
に等間隔おきに各々複数個設けられている。そして前記
第1の走行体33の台車部33aおよび支持台車33は
、各々前記連結バー41を介して前記支持リング40に
連結されている。この支持リング40は、前記第1の案
内体32よりも小径で、かつ同心状に配置されている。
The first traveling body 33 includes a truck portion 33a having the same configuration as the support truck 39, and a drive portion 33b that causes the truck portion 33a to travel along the first guide body 32. A plurality (three in this embodiment) are provided at equal intervals in the direction. A plurality of support carts 39 are also provided between the first traveling bodies 33 at regular intervals. The truck portion 33a of the first traveling body 33 and the support truck 33 are each connected to the support ring 40 via the connection bar 41. This support ring 40 has a smaller diameter than the first guide body 32 and is arranged concentrically.

前記支持リング40には、前記第2の案内体34a〜3
4Cの上端部が周方向等間隔おきにブラケット46を介
して連結されている。なお、この第2の案内体34a〜
34cの設置数は3本に限られるものではない。
The support ring 40 includes the second guide bodies 34a to 3.
The upper end portions of 4C are connected via brackets 46 at equal intervals in the circumferential direction. Note that this second guide body 34a~
The number of 34c installed is not limited to three.

前記第2の案内体34a〜34cは、第4図〜第6図に
詳細に示すように、下端部が前記原子炉容器胴部31の
外周而に沿って湾曲しており、下端は前記センタリング
ボルト43に連結されている。また中間部は、約2支持
リング40と同様な複数の中間部支持リング47に、ブ
ラケット46を介して連結されている。すなわもt’r
ir記複数の第1の走行体33と複数の第2の案内体3
4i1 ・〜34cとは一体に連結されており、第2の
案内体34a〜34(は、第1の走行体33の走行によ
り、ヒンタリングj14ルト43を中心として回転する
As shown in detail in FIGS. 4 to 6, the second guide bodies 34a to 34c have lower end portions curved along the outer periphery of the reactor vessel body 31, and lower ends of the second guide members 34a to 34c are curved along the outer periphery of the reactor vessel body 31. It is connected to a bolt 43. The intermediate portion is also connected via brackets 46 to a plurality of intermediate portion support rings 47 similar to approximately two support rings 40 . Sunawamo t'r
IR: A plurality of first running bodies 33 and a plurality of second guide bodies 3
4i1 - 34c are integrally connected, and the second guide bodies 34a to 34 (rotate around the hinting belt 43 as the first running body 33 travels).

前記第2の案内体34aには、第7図〜第9図に詳細に
示J゛ように、前記tA2の走行体35aが取付けられ
てJ3す、このff12の走行体35aは、第2の案内
体34aに形成されたラックに噛合するビニオンを有づ
る駆動部48を<j シてJ5す、ピニオンの回転に、
より第2の案内体34aに冶)て昇降する。l)η2第
2の走行体35aには、探触子走査装置49が固定され
ており、この探触子走査装置49は、上ド端部に前記第
2の案内体34aに遊1■づるガイド枠50が取付けら
れた箱体51と、この箱体51の内部に設置されたねじ
棒52と、このねじ棒52を軸心回りに回転させる回転
駆Ill装置53と、案内棒54と、前記ねじ棒52に
螺合するねじ部55aを有しかつ前記案内棒54に遊嵌
する2組の探触子箱55とから構成されている。前記各
探触子箱55には探触子56が設置されている。前記ね
じ棒52は、軸心方向中央を境桿としてねじの向きが互
いに反対になっており、ねじ棒52を回転させると、前
記2組の探触子w155は互いに逆向きに移動する。な
お57はラックである。
As shown in detail in FIGS. 7 to 9, the running body 35a of the tA2 is attached to the second guide body 34a. The drive unit 48 having a pinion that meshes with a rack formed on the guide body 34a is rotated by J5 to rotate the pinion.
The second guide body 34a moves up and down. l) η2 A probe scanning device 49 is fixed to the second traveling body 35a, and this probe scanning device 49 is attached to the second guiding body 34a at the upper end thereof. A box body 51 to which a guide frame 50 is attached, a threaded rod 52 installed inside this box body 51, a rotary drive device 53 that rotates this threaded rod 52 around its axis, and a guide rod 54. It is comprised of two sets of probe boxes 55, each having a threaded portion 55a that is screwed onto the threaded rod 52 and loosely fitted onto the guide rod 54. A probe 56 is installed in each probe box 55. The threaded rods 52 have threads in opposite directions with the axial center as a boundary rod, and when the threaded rods 52 are rotated, the two sets of probes w155 move in opposite directions. Note that 57 is a rack.

11う2第2の案内体34bには、第10図及び第11
図に詳細に示すように、前記第2の走行体35bが取付
けられており、この第2の走行体35bは、第2の案内
体34bに形成されたラックに噛合するビニオンを有す
る駆動部58を有しており、ピニオンの回転により第2
の案内体34bに沿って昇降する。
11 U2 The second guide body 34b has the
As shown in detail in the figure, the second traveling body 35b is attached, and this second traveling body 35b has a drive portion 58 having a pinion that meshes with a rack formed on the second guide body 34b. The rotation of the pinion causes the second
It moves up and down along the guide body 34b.

前記第2の走行体35bには、探触子走査装置59が取
付けられており、この探触子走査装置59は、前記第2
の案内体34bと直交しかつ前記原子炉容器ffJ部3
1の外周而に沿って湾曲した走査用案内体60と、この
走査用案内体60に形成されたラック61に噛合するビ
ニオンを有する走査用駆動装置62と、この走査用駆動
装置62に取付けられた探触子箱63とから構成されて
おり、前記探触子箱63には探触子64が設置されてい
る。なお65はラックである。
A probe scanning device 59 is attached to the second traveling body 35b, and this probe scanning device 59 is connected to the second traveling body 35b.
perpendicular to the guide body 34b of the reactor vessel ffJ section 3.
a scanning guide 60 curved along the outer periphery of the scanning guide 60; a scanning drive device 62 having a pinion that meshes with a rack 61 formed on the scanning guide 60; and a probe box 63, in which a probe 64 is installed. Note that 65 is a rack.

また、前記第2の走行体35a、35bには、第1図に
示すように、搬像装置45a、 45bが取付Cフられ
ており、これら各撮像装置45a、 45bは、テレビ
ジョンカメラと照明器具とから構成さ′れている。前記
制御盤36に1よ、前記第1の走行体33の駆動部33
bと、I)fj記第2の走行体35a、35bの駆動部
、18.58ト、前記探触子走査装置49.50の回転
駆動装置代53及び走査用駆動装置62と、前記Ha 
ti 装置45a、 45bとを遠隔制御りるil+’
J ill装置が設置されていると共に、前記各探触子
56.64に電気的に接続8れた趙合波探傷装置本体が
設置されCおり、さらには、前記撮像装置4!+a、4
5bにより搬像された画像を表示りる表示装置ど、f−
タタイプライター、°ノ1]ツピーディスク、磁気ディ
スク等を佑えたf−夕収録装置と、コンピュータを備え
たf−り処J!l!装置とが設置されている。なお、前
記第2の案内体34cには、第2の走行体は装着されて
いない。また前記第2の走行体35a、 35bは通常
第2の案内体34a。
Furthermore, as shown in FIG. 1, the second traveling bodies 35a, 35b have image carrier devices 45a, 45b mounted thereon, and these imaging devices 45a, 45b are equipped with a television camera and a lighting device. It consists of equipment. 1 to the control panel 36, the drive section 33 of the first traveling body 33;
b, I)fj, the drive unit of the second traveling bodies 35a, 35b, 18.58g, the rotational drive device allowance 53 and the scanning drive device 62 of the probe scanning device 49.50, and the Ha
remote control of the devices 45a and 45b;
In addition to the Jill device installed therein, the main body of the Zhaohebo flaw detection device electrically connected to each of the probes 56 and 64 is also installed, and furthermore, the imaging device 4! +a, 4
A display device for displaying the image carried by 5b, f-
F-Record J! is equipped with an f-recording device with a typewriter, a typewriter, a disk, a magnetic disk, etc., and a computer! l! equipment is installed. Note that the second traveling body is not attached to the second guide body 34c. Further, the second running bodies 35a, 35b are normally the second guide bodies 34a.

34bから取外されており、検査開始時に原子炉容器ス
カート37のハンドホール38から投入して、第2の案
内体34a、34bに装着する。
34b, and is inserted through the hand hole 38 of the reactor vessel skirt 37 at the start of inspection and attached to the second guide bodies 34a, 34b.

以下、上記構成における作用について説明する。Hereinafter, the effects of the above configuration will be explained.

先ず、周方向に沿う溶接部の検査に際しては、第2の走
行体35aを走行させてねじ棒52の軸心方向中央部を
溶接線に対向させる。そして第1の走行体33を所定速
度で走行させながら、ねじ棒52を所定の速度で所定の
回転数毎に往復回転させる。これにより、溶接線を境と
して送信用及び受信用の探触子56.56が互いに逆方
向に往復移動し、第1図実IQ(A>の如く所定範囲に
わたっての走査がなされる。次に軸心方向に沿う溶接部
の検査に際しては、第1の走行体33を走行させて第2
の走行体35bを溶接線に対向させる。そして第2の走
行体35bを所定の速度で所定の方向へ走行させながら
、走査用駆動装置62を所定の速度で往復移動させる。
First, when inspecting a welded portion along the circumferential direction, the second traveling body 35a is caused to travel so that the central portion of the threaded rod 52 in the axial direction is opposed to the weld line. Then, while the first traveling body 33 is running at a predetermined speed, the threaded rod 52 is reciprocated at a predetermined speed and at a predetermined number of revolutions. As a result, the transmitting and receiving probes 56 and 56 move back and forth in opposite directions with the welding line as a boundary, and scan a predetermined range as shown in Fig. 1 Actual IQ (A>).Next, When inspecting a welded part along the axial direction, the first traveling body 33 is run and the second
The traveling body 35b is placed opposite to the welding line. Then, while the second traveling body 35b is traveling at a predetermined speed in a predetermined direction, the scanning drive device 62 is reciprocated at a predetermined speed.

これにより、探触子64は、溶接線を中心として第1図
実線(B)の如く所定の範囲を走査する。また、上記周
方向に沿う溶接部の検査と同社の方法を用いて、第1の
走行体33の1回転毎に、第2の走行体35aの位置を
探触子56の走査範囲に相当J6距離だCノ順次ヂらせ
ていくことにより、原子炉容器胴部31の外周面全面に
わたって検査を行なうことがでさる。
Thereby, the probe 64 scans a predetermined range as shown by the solid line (B) in FIG. 1 with the weld line as the center. In addition, by inspecting the welded portion along the circumferential direction and using the company's method, the position of the second traveling body 35a is adjusted to correspond to the scanning range of the probe 56 for each rotation of the first traveling body 33. By gradually increasing the distance C, the entire outer peripheral surface of the reactor vessel body 31 can be inspected.

これらの検査においで、探触子56.64からの信号は
制御盤36の超音波深山装置本体に入力され、検査デー
タの処理や記録等がなされると同時に、起fII装買4
5a、 45bからの映像を表示すことにより、検査中
の探触子56,64Wの状況や探傷面の状況を遠隔操作
により観察できる。、また層像装置45a。
In these inspections, the signals from the probes 56 and 64 are input to the main body of the ultrasonic deep mountain equipment in the control panel 36, and at the same time, the inspection data is processed and recorded.
By displaying the images from 5a and 45b, the status of the probes 56 and 64W during inspection and the status of the flaw detection surface can be observed by remote control. , and a layer imager 45a.

45bは、探1幼時以外にも、原子炉′fg器IH部3
1の外周面の目視検査に利用rさる。
In addition to his early childhood, 45b was also involved in the IH section 3 of the nuclear reactor'fg reactor.
It is used for visual inspection of the outer peripheral surface of 1.

このように本実施例によれば、第2の案内体34a〜3
4cが回転するようにしたので、軌36M4迄が簡41
であり、駆動操作の制御す容易である。また溶接部に限
らず、原子炉容器胴部31全域にわたって探傷走査を行
なえるので、母材自体、クラッド内表面、母材−クラッ
ド溶接部などの欠陥も探傷できる。特に、原子炉容器内
面すなわちクラッド内表面は、基準では燃料交換時等に
おいて可能であれば肉眼検査をri務づけられているが
、本実施例の検査袋Uはそれに代わる方法として利用で
きる。また探信検査を遠隔自動で行なえるので、燃料交
換や他の保守・点検作業と並行実施でき、供用期間中検
査の期間を短縮できる。また現場作業は第2の案内体3
4a、34b ヘの第2の走行体35a、35bのセツ
ティングのみであるので、作業者の放射線被曝の低減に
効果がある。
As described above, according to this embodiment, the second guide bodies 34a to 3
Since 4c rotates, it is easy to move up to track 36M4.
Therefore, it is easy to control the drive operation. Moreover, since flaw detection scanning can be performed not only on the welded portion but also over the entire area of the reactor vessel body 31, defects such as the base metal itself, the inner surface of the clad, the base metal-clad welded portion, etc. can also be detected. In particular, the standards require that the inner surface of the reactor vessel, that is, the inner surface of the cladding, be inspected with the naked eye if possible at the time of fuel exchange, etc., but the inspection bag U of this embodiment can be used as an alternative method. In addition, since detection inspections can be performed remotely and automatically, they can be carried out in parallel with fuel replacement and other maintenance and inspection work, reducing the period of inspection during service life. Also, for on-site work, the second guide 3
Since only the setting of the second traveling bodies 35a, 35b to 4a, 34b is required, it is effective in reducing the radiation exposure of the workers.

なお上記実施例においては、周方向に沿う溶接部の検査
にタンデム探傷法を用いたが、−探触子法を用いてもよ
い。すなわち第12図及び第13図に示すように、探触
子走査′ArFl(i6は、上下端に、第2の案内体3
4aに遊嵌するガイド枠67を有する走査用走行体68
と、この走査用走行体68に形成されたラック69に噛
合するピニオンを備えかつ第2の走行体35aに設置さ
れた走査用駆i11装置70と、前記走査用走行体68
の下端部に取付けられた探触子箱71とにより構成され
ており、前記探触子箱71内に探触子72が収納されて
いる。なお、これの代わりに、第10図及び第11図に
示すような駆動構成としてもよい。)なわら、走査用案
内体60を第2の案内体35aと平行にすればよいので
ある。
In the above embodiment, the tandem flaw detection method was used to inspect the welded portion along the circumferential direction, but the -probe method may also be used. That is, as shown in FIG. 12 and FIG.
Scanning traveling body 68 having a guide frame 67 that loosely fits into 4a
, a scanning drive i11 device 70 equipped with a pinion that meshes with a rack 69 formed on the scanning traveling body 68 and installed on the second traveling body 35a, and the scanning traveling body 68
A probe box 71 is attached to the lower end of the probe box 71, and a probe 72 is housed within the probe box 71. Note that instead of this, a driving configuration as shown in FIGS. 10 and 11 may be used. )The scanning guide body 60 may be made parallel to the second guide body 35a.

また上記実施例においては、探触子56,64.72を
所定範囲にわたって走査させたが、探触子の特性あるい
は検査精度によっては、必ずしも走査させる必要はない
Further, in the above embodiment, the probes 56, 64, and 72 were scanned over a predetermined range, but depending on the characteristics of the probes or the inspection accuracy, it is not necessary to scan them.

発明の効果 以上述べたごとく本発明によれば、第2の案内体自体が
回転するようにしたので、@造が簡単で駆動操作の制御
し容易であり、しかも溶接部に限らず原子炉室2g円部
の全域にわたって検査を行なうことができる。また第2
の案内体及び第2の走行体を少なくとも2個設けたので
、周方向に沿う検査と軸心方向に沿う検査とを各々専用
の探触子で行なうことができ、したがって、例えば一方
の検査中に他方の第2の走行体の高さ方向の位置を他方
の検査のスタート位置に合わせることかできるなど、効
率良く検査を行なえる。また探傷を遠隔自動で行なえる
ので、燃料交換や他の保守・点検作業と並行実施でき、
検査期間全体を大幅に短縮でさると同時に、現場作業が
ほとんどないので、作業者の放射線被曝を大幅に低減で
きる。
Effects of the Invention As described above, according to the present invention, since the second guide body itself rotates, the construction is simple and the drive operation is easy to control. Inspection can be performed over the entire 2g circular portion. Also the second
Since at least two guide bodies and second traveling bodies are provided, inspections along the circumferential direction and inspections along the axial direction can be performed with dedicated probes, respectively. Therefore, for example, during one inspection Inspection can be carried out efficiently, such as by being able to align the heightwise position of the other second traveling body with the starting position of the other second traveling body. In addition, since flaw detection can be performed remotely and automatically, it can be carried out in parallel with fuel changes and other maintenance and inspection work.
The overall inspection period is greatly shortened, and at the same time, there is almost no on-site work, which greatly reduces radiation exposure for workers.

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

第1図は本発明の一実施例における原子炉容器胴部の検
査装置の全体構成を示す概略斜視図、第2図は同検査装
置における第1の案内体付近の平面図、第3図は同要部
拡大縦断面図、第4図は同検M装置における第2の案内
体イ1近の斜視図、第5図は同要部拡大横断面図、第6
図は同要部拡大縦断面図、第7図は同検査装置における
一方の第2の走行体付近の斜視図、第8図は同要部拡大
横断面図、第9図tよ探触子箱の縦断面図、第10図は
他方の第2の走行体付近の正面図、第11図は同要部拡
大横断面図、第12図は別の実施例における一方の第2
の走行体付近の斜視図、第13図は同要部拡大横断面図
、第14図は従来装置のItIIIi面図、第15図は
別の従来装置の一部切欠斜視図である。 31・・・原子炉容器胴部、32・・・第1の案内体、
33・・・第1の走行体、34a〜34C・・・第2の
案内体、35a。 35b・・・第2の走行体、36・・・It/J即盤、
56,64.72・・・探触子 べ 傳! 第4図 第7図 第10図 第1I図 I 第12図 5り 第114因 第15図
FIG. 1 is a schematic perspective view showing the overall configuration of a reactor vessel barrel inspection device according to an embodiment of the present invention, FIG. 2 is a plan view of the vicinity of the first guide body in the inspection device, and FIG. 4 is a perspective view of the vicinity of the second guide body I1 in the inspection M device, FIG. 5 is an enlarged cross-sectional view of the same essential part, and FIG.
The figure is an enlarged longitudinal cross-sectional view of the same essential part, Fig. 7 is a perspective view of the vicinity of one of the second traveling bodies in the same inspection device, Fig. 8 is an enlarged cross-sectional view of the same essential part, and Fig. 9 is a probe. A vertical sectional view of the box, FIG. 10 is a front view of the vicinity of the other second traveling body, FIG. 11 is an enlarged cross-sectional view of the same essential part, and FIG. 12 is one of the second traveling bodies in another embodiment.
FIG. 13 is an enlarged cross-sectional view of the same main part, FIG. 14 is an ItIIIi plane view of the conventional device, and FIG. 15 is a partially cutaway perspective view of another conventional device. 31... Reactor vessel body, 32... First guide body,
33...First running body, 34a to 34C...Second guide body, 35a. 35b...Second running body, 36...It/J immediate release,
56, 64.72... Probe beden! Figure 4Figure 7Figure 10Figure 1IFigure IFigure 12Figure 114 FactorsFigure 15

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉容器胴部の外周面近傍に周方向に沿って設置
された環状の第1の案内体と、この第1の案内体に案内
されて走行する第1の走行体と、前記原子炉容器胴部の
外周面近傍に軸心方向に沿って周方向適当間隔おきに配
置されかつ前記第1の走行体に連結された複数の第2の
案内体と、これら第2の案内体のうちの少なくとも2本
の第2の案内体に各別に案内されて走行する少なくとも
2組の第2の走行体と、これら第2の走行体に各々設置
された探触子と、前記第1および第2の走行体を遠隔操
作するための制御装置と、前記各探触子に電気的に接続
された超音波探傷装置本体とを備えたことを特徴とする
原子炉容器胴部の検査装置。
1. An annular first guide body installed along the circumferential direction near the outer circumferential surface of the reactor vessel body, a first traveling body that runs guided by the first guide body, and the atoms a plurality of second guide bodies arranged near the outer circumferential surface of the reactor vessel body along the axial direction at appropriate intervals in the circumferential direction and connected to the first running body; at least two sets of second running bodies that run while being guided separately by at least two of the second guide bodies, probes installed on each of these second running bodies, and the first and second running bodies; An inspection device for a nuclear reactor vessel body, comprising: a control device for remotely controlling a second traveling body; and an ultrasonic flaw detection device main body electrically connected to each of the probes.
JP60195233A 1985-09-03 1985-09-03 Checking device for reactor vessel body part Pending JPS6254161A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60195233A JPS6254161A (en) 1985-09-03 1985-09-03 Checking device for reactor vessel body part

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60195233A JPS6254161A (en) 1985-09-03 1985-09-03 Checking device for reactor vessel body part

Publications (1)

Publication Number Publication Date
JPS6254161A true JPS6254161A (en) 1987-03-09

Family

ID=16337695

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60195233A Pending JPS6254161A (en) 1985-09-03 1985-09-03 Checking device for reactor vessel body part

Country Status (1)

Country Link
JP (1) JPS6254161A (en)

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