JPS62102147A - Isi testing device for piping penetration part of nuclear reactor container - Google Patents
Isi testing device for piping penetration part of nuclear reactor containerInfo
- Publication number
- JPS62102147A JPS62102147A JP60241514A JP24151485A JPS62102147A JP S62102147 A JPS62102147 A JP S62102147A JP 60241514 A JP60241514 A JP 60241514A JP 24151485 A JP24151485 A JP 24151485A JP S62102147 A JPS62102147 A JP S62102147A
- Authority
- JP
- Japan
- Prior art keywords
- film
- isi
- welding part
- photographing
- testing device
- 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
Links
Classifications
-
- 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
- Analysing Materials By The Use Of Radiation (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の詳細な説明〕
本発明は、原子炉格納容器の配管ペネトレーションに係
り、特に当該部のプロセス配管のl5i(供用期間中検
査)試験に好適なISI試験装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Detailed Description of the Invention] The present invention relates to piping penetration in a nuclear reactor containment vessel, and particularly relates to an ISI test device suitable for I5i (in-service inspection) testing of process piping in the relevant part. .
従来の原子炉格納容器配管ペネトレーション部の構造に
ついて第5図、第6図にて説明する。The structure of a conventional reactor containment vessel piping penetration section will be explained with reference to FIGS. 5 and 6.
配管ペネトレーション3は第5図及び第6図に示す如く
、プロセス配管4が原子炉遮蔽壁1及び原子炉格納容器
2を貫通する部分に設けられる。As shown in FIGS. 5 and 6, the pipe penetration 3 is provided at a portion where the process pipe 4 penetrates the reactor shielding wall 1 and the reactor containment vessel 2.
これには防護用のガート管5が設けられる場合もある。This may be provided with a guard pipe 5 for protection.
この配管ペネトレーション3内のプロセス管4は第6図
に示す配管ペネトレーション3の前後で溶接により系統
の配管と接続され、配管ペネトレーション3の内部で溶
接し接続する構造とはしない、この理由はプロセス配管
の溶接部はJEAC(日本電気協会)の規程によりLS
I (供用期間中検査)を行ない、その健全性を確認す
る必要があり、ISIを行なうにはプロセス管4外部の
ガード管5との間が狭隘であるため、狭所での作業を避
る為である。The process pipe 4 in this pipe penetration 3 is connected to the system pipe by welding before and after the pipe penetration 3 shown in Fig. 6, and the structure is not designed to weld and connect inside the pipe penetration 3.The reason for this is that the process pipe The welded part is LS according to JEAC (Japan Electrical Association) regulations.
It is necessary to conduct ISI (in-service inspection) to confirm its soundness, and to perform ISI, there is a narrow space between the process pipe 4 and the guard pipe 5 outside, so avoid working in narrow spaces. It is for this purpose.
近年、既設原子カプラントにおいて、5CC(応力腐食
割れ)対策として該当するプロセス管4を耐scc材に
交替する作業が生じているが、新設プラントと異なり建
家、原子炉遮蔽壁1及び周辺機器、配管等との干渉等に
より配管ペネトレーション3を一体で搬入することは干
渉物の一時撤去品が膨大になること、遮蔽壁に仮開口が
必要となることなどにより、現地据付工程上及びコスト
面で問題があった。In recent years, as a measure against 5CC (stress corrosion cracking) in existing nuclear power plants, there has been work to replace the corresponding process pipes 4 with SCC-resistant materials. Due to interference with piping, etc., transporting Piping Penetration 3 in one piece requires a huge amount of temporary removal of interfering objects, and temporary openings are required in the shielding wall, making it difficult to install on-site and in terms of cost. There was a problem.
−本発明の目的は、前述の問題点を排除し、原子炉格納
容器の配管ペネトレーション内部の狭隘な個所に於ける
プロセス管の溶接部の健全性を確認することを容易にす
るISI放射線透過試験装置を提供することにある。- The object of the present invention is to eliminate the above-mentioned problems and to facilitate confirmation of the integrity of welds of process pipes in narrow locations inside piping penetrations of reactor containment vessels using ISI radiographic testing. The goal is to provide equipment.
本発明は原子炉格納容器の配管ペネトレーション部に於
けるプロセス管のISI工法の一つである放射線透過試
験においてフィルムの着脱を空気による遠隔操作とする
ことにより溶接部のISIを容易にしたことを特徴とす
るものである。The present invention facilitates ISI of welded parts by remotely controlling the attachment and detachment of films using air in radiographic testing, which is one of the ISI methods for process pipes in piping penetration areas of reactor containment vessels. This is a characteristic feature.
以下、本発明の実施例を第1図〜第4図により説明する
。第1図はISI対象のプロセス管4が原子炉格納容器
2の配管貫通部内で溶接線6により溶接され、かつ、原
子炉格納容器内側よりIS工試験装置7を挿入した状態
を示す。ISI試験装置7は複数個に分割されており、
原子炉格納容器2内部にて組立、ペネトレーション3内
に挿入ができる構造となっている。溶接線6上に挿着さ
れたISI試験装置7は第2図に示す様に外部にフィル
ム巻取り装置!8を設置し、連続撮影が可能な構造とす
る。撮影時の状態を説明するとISI試験装[17に設
けられている加圧、及び吸引口9へ送風ポンプ10によ
りフレキシンプルチューブ11を介してゴムシール12
内へ空気を送り込むことによりゴムシール12がふくら
みフィルム13を溶接部6へ密着させる。その後フィル
ム13と相対する位置に設けられた線源へ、線源操作装
@14より線源口15へ経て線源を放射し撮影を行なう
。フィルム13はISI試験装置7に設けられている。Embodiments of the present invention will be described below with reference to FIGS. 1 to 4. FIG. 1 shows a state in which a process pipe 4 to be subjected to ISI is welded by a welding line 6 within a pipe penetration portion of a reactor containment vessel 2, and an IS engineering test device 7 is inserted from inside the reactor containment vessel. The ISI test device 7 is divided into multiple pieces,
It has a structure that allows it to be assembled inside the reactor containment vessel 2 and inserted into the penetration 3. The ISI test device 7 inserted onto the welding line 6 has an external film winding device as shown in Fig. 2! 8 installed in a structure that allows continuous shooting. To explain the state at the time of photographing, the pressure provided in the ISI test device [17] and the rubber seal 12 are applied to the suction port 9 via the flexible tube 11 by the air pump 10.
By blowing air into the rubber seal 12, the swollen film 13 is brought into close contact with the welded portion 6. Thereafter, the radiation source is emitted from the radiation source operating device @ 14 to the radiation source port 15 placed at a position facing the film 13, and an image is taken. The film 13 is installed in the ISI test device 7.
ガイド16により横移動を拘束され、フィルム巻取り装
置にて1巻取り、巻戻しを行なう。Lateral movement is restrained by a guide 16, and one winding and rewinding are performed by a film winding device.
本フィルム巻取り装置8はISI試験装置!l!7本体
を回転させることにより自動的に巻取るか、その都度遠
隔操作により巻取るか、いずれの方法でもよい。This film winding device 8 is an ISI test device! l! 7. Either method may be used, such as automatically winding up by rotating the main body, or winding up by remote control each time.
又1図中に示す斜線部は線源からフィルム13へ悪影響
を受けない様、線源に対する遮蔽に優れた鉛製とするこ
とが望ましい。Further, the shaded area shown in FIG. 1 is preferably made of lead, which has excellent shielding properties against the radiation source, so that the film 13 is not adversely affected by the radiation source.
第3図に於いてISI試験装置7の挿入、引出し、移動
、回転等、撮影時以外の状態について説明すると、加圧
、吸引口9より、フレキシブルチューブ11を介し真空
ポンプ17にてゴムシール12内の空気を吸引し、フィ
ルム13を溶接部6ないしプロセス管4との間に間隙を
設けフィルム13の損傷を防ぎ移動1回転等の作業を行
なう。In FIG. 3, to explain the state of the ISI test device 7 other than when photographing, such as insertion, withdrawal, movement, rotation, etc., the pressure is applied to the inside of the rubber seal 12 through the vacuum pump 17 through the flexible tube 11 from the suction port 9. The air is sucked, and a gap is created between the film 13 and the welding part 6 or the process tube 4 to prevent damage to the film 13, and operations such as one rotation of movement are performed.
このISI試験装置7によれば線源口15とフィルム1
3の位置が相対する位置にある。撮影後はフィルム3巻
取り前に吸引にてフィルム13と溶接部6間に空間を設
けた後に巻取り、本装置を撮影未済の個所まで円周方向
に回転させ再度空圧により、フィルム13を密着させ撮
影する。以上の事を繰返して全周撮影が可能、即ち、I
SIの試験が出来る。According to this ISI test device 7, the radiation source port 15 and the film 1
The positions numbered 3 and 3 are opposite to each other. After photographing, before winding up the film 3, use suction to create a space between the film 13 and the welded part 6, then wind it up, rotate this device in the circumferential direction to the part that has not yet been photographed, and use air pressure again to unwind the film 13. Take a close-up photo. By repeating the above steps, it is possible to take pictures all around, i.e., I
You can take the SI test.
第4図本発明の応用例として第3図に於れる■S工試験
装e7の位置設定を容易にする一例として、ガード管5
内径側にス1〜ツバ18を設ける二とによりISI試験
装置7の軸方向の移動を拘束するため操作が容易となる
。Fig. 4 As an example of application of the present invention, as an example of facilitating the position setting of ■S engineering test equipment e7 in Fig. 3, the guard pipe 5
By providing the collars 1 to 18 on the inner diameter side, the movement of the ISI test device 7 in the axial direction is restrained, so that the operation becomes easy.
本発明によれば、原子力発電プラント、原子格納容器配
管貫通部のプロセス管の改造等に於いて次の効果を奏す
る。According to the present invention, the following effects can be achieved in the modification of process pipes in nuclear power plants and nuclear containment vessel piping penetrations.
(1)配管ペネトレーション内部にプロセス管の溶接線
を設けても、ISI試験が容易に行なえるため、搬入及
び据付時の周辺機器、建屋壁、配管等との干渉回避が可
能となり据付工程の短縮が可能となる。(1) ISI tests can be easily performed even if process pipe weld lines are installed inside the pipe penetration, making it possible to avoid interference with peripheral equipment, building walls, pipes, etc. during delivery and installation, shortening the installation process. becomes possible.
(2)上記により作業者の被爆低減が計れる。(2) The above will reduce radiation exposure for workers.
第1図は、本発明の一実施例を示す部分断面図、第2図
、第3図は本発明の構造を示す詳細図、第4図は本発明
の応用例を示す部分断面図、第5図は、従来の原子炉格
納容器の縦断面図、第6図は第5図に於ける配管ペネト
レーションを示すA部詳細図である。
1・・・原子炉遮蔽壁、2・・・原子炉格納容器、4・
・・プロセス管、10・・・送風ポンプ、14・・・線
源操作装置、15・・・線源口、16・・・ガイド、1
7・・・真空ポンプ。FIG. 1 is a partial cross-sectional view showing an embodiment of the present invention, FIGS. 2 and 3 are detailed views showing the structure of the present invention, and FIG. 4 is a partial cross-sectional view showing an application example of the present invention. FIG. 5 is a vertical sectional view of a conventional reactor containment vessel, and FIG. 6 is a detailed view of section A showing the pipe penetration in FIG. 5. 1... Reactor shielding wall, 2... Reactor containment vessel, 4...
...Process pipe, 10...Blower pump, 14...Radiation source operating device, 15...Radiation source port, 16...Guide, 1
7...Vacuum pump.
Claims (1)
るプロセス配管の当該溶接部の供用期間中検査の方法で
ある放射線透過試験において、フィルムと線源を相対す
る位置に設け一体で移動できる構造を有し、撮影時には
フィルムを空気圧で該溶接個所に密着させ、上記以外の
撮影前後の移動、フィルムの巻き取り及びセット時にお
いては、フィルムを空気の吸引により雇本体側に密着さ
せ、当該溶接部とフィルムの間に空間を設ける事を特徴
とする原子炉格納容器の配管ペネトレーション部のIS
I試験装置。1. In radiographic testing, which is a method of in-service inspection of the welded parts of process piping installed in the piping penetration of the reactor containment vessel, the film and radiation source are placed in opposing positions and have a structure that allows them to move together. During photography, the film is brought into close contact with the welded part using air pressure, and when moving before and after taking pictures other than the above, and when winding and setting the film, the film is brought into close contact with the main body by air suction, and the welded part and the film are IS of piping penetration part of reactor containment vessel characterized by providing space between
I test equipment.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60241514A JPS62102147A (en) | 1985-10-30 | 1985-10-30 | Isi testing device for piping penetration part of nuclear reactor container |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60241514A JPS62102147A (en) | 1985-10-30 | 1985-10-30 | Isi testing device for piping penetration part of nuclear reactor container |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS62102147A true JPS62102147A (en) | 1987-05-12 |
Family
ID=17075472
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP60241514A Pending JPS62102147A (en) | 1985-10-30 | 1985-10-30 | Isi testing device for piping penetration part of nuclear reactor container |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS62102147A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2008076136A (en) * | 2006-09-20 | 2008-04-03 | Murazumi Kogyo Kk | Plate for microscope specimen |
CN109545405A (en) * | 2018-10-29 | 2019-03-29 | 中国核工业二三建设有限公司 | A kind of tile film-taking in means for nuclear power CV container butt weld ray detection |
-
1985
- 1985-10-30 JP JP60241514A patent/JPS62102147A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2008076136A (en) * | 2006-09-20 | 2008-04-03 | Murazumi Kogyo Kk | Plate for microscope specimen |
CN109545405A (en) * | 2018-10-29 | 2019-03-29 | 中国核工业二三建设有限公司 | A kind of tile film-taking in means for nuclear power CV container butt weld ray detection |
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