JPS6158791B2 - - Google Patents
Info
- Publication number
- JPS6158791B2 JPS6158791B2 JP55131548A JP13154880A JPS6158791B2 JP S6158791 B2 JPS6158791 B2 JP S6158791B2 JP 55131548 A JP55131548 A JP 55131548A JP 13154880 A JP13154880 A JP 13154880A JP S6158791 B2 JPS6158791 B2 JP S6158791B2
- Authority
- JP
- Japan
- Prior art keywords
- welding
- repair
- laser
- reactor vessel
- cutting
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
- 230000005540 biological transmission Effects 0.000 claims description 9
- 238000003466 welding Methods 0.000 description 25
- 238000005520 cutting process Methods 0.000 description 17
- 238000000034 method Methods 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- 239000000463 material Substances 0.000 description 3
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
- 230000005856 abnormality Effects 0.000 description 2
- 229910000963 austenitic stainless steel Inorganic materials 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 229910000975 Carbon steel Inorganic materials 0.000 description 1
- 239000010962 carbon steel Substances 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000001066 destructive effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 238000003754 machining Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
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
- Laser Beam Processing (AREA)
- Heat Treatment Of Articles (AREA)
Description
【発明の詳細な説明】
本発明は供用期間中検査等で、万一原子炉容器
内面その他に材料異常が発見された場合に補修溶
接・切断する手段を提供するための装置である。
ナトリウムを冷却材とする高速増殖炉用原子炉に
おいては、原子炉容器や炉内構造物は通例オース
テナイト系ステンレス鋼で製造される。オーステ
ナイト系ステンレス鋼は炭素鋼などとくらべて、
熱が伝わりにくい上に熱膨張率が大きいため溶接
などの入熱による熱変形が大きいので製品製作途
上の溶接にあつても種々の工夫をこらしている。
その様な状態であるため、原子炉運転開始後例え
ば供用期中検査等によつて万一原子炉容器内面そ
の他に材料異常が発見された場合補修溶接しよう
とする場合には、下記の如き制約が加わつて一層
困難さが増す。DETAILED DESCRIPTION OF THE INVENTION The present invention is a device for providing a means for repair welding and cutting in the event that material abnormalities are discovered on the inner surface of the reactor vessel or elsewhere during in-service inspections or the like.
In fast breeder reactors that use sodium as a coolant, the reactor vessel and reactor internals are typically made of austenitic stainless steel. Compared to carbon steel, austenitic stainless steel
In addition to being difficult to conduct heat, it has a high coefficient of thermal expansion, so it is subject to large thermal deformation due to heat input during welding, so various measures are taken during welding during product manufacturing.
Because of this situation, if a material abnormality is discovered on the inside of the reactor vessel or elsewhere after the start of reactor operation, for example, during an in-service inspection, the following restrictions apply when attempting to perform repair welding. This adds to the difficulty.
製品が完成し使用開始後であるため、補修溶
接後機械加工等によつて形状公差、寸法公差等
を改善することが困難であるため、変形の少な
い補修溶接法も採用する必要がある。 Since the product has already been completed and is ready for use, it is difficult to improve shape tolerances, dimensional tolerances, etc. by machining after repair welding, so it is necessary to adopt a repair welding method that causes less deformation.
高速増殖炉の特殊性から、通常アンダザプラ
グ燃料交換方式を採用しているため、原子炉容
器蓋を容易に取りはずすことができないので、
補修作業も原子炉容器蓋をとりはずさないまま
行なうことが望まれる。 Due to the special nature of fast breeder reactors, an under-the-plug refueling system is usually adopted, and the reactor vessel lid cannot be easily removed.
It is desirable that repair work be carried out without removing the reactor vessel lid.
原子炉容器内は放射線源強度が高いため、作
業者の立入・接近が著しく制約される。従つて
遠隔操作による補修作業が必要となる。 Due to the high intensity of the radiation source inside the reactor vessel, access for workers is severely restricted. Therefore, repair work must be performed by remote control.
溶接後全体の熱処理ができないため、高い寸
法精度を要求される部所に対しては高エネルギ
密度の溶接法等の適用が望まれる。 Since the entire weld cannot be heat treated after welding, it is desirable to apply high energy density welding methods to parts that require high dimensional accuracy.
原子炉容器内は放射線源強度が高いため、炉
内で用いる補修器材に対して必要な放射線しや
へいを行なう必要がある。 Because the intensity of the radiation source inside the reactor vessel is high, it is necessary to provide necessary radiation protection for repair equipment used inside the reactor.
以上の如き諸問題点を解消した、運転開始後に
原子炉容器内面その他を補修溶接・切断できる装
置の発明が望まれていた。 It has been desired to invent an apparatus capable of repair welding and cutting the inner surface of the reactor vessel and other parts after the start of operation, which solves the above-mentioned problems.
本発明の目的は、上記諸問題点を除去した原子
炉容器内面等を補修溶接・切断可能とする原子炉
補修装置を提供することにある。 SUMMARY OF THE INVENTION An object of the present invention is to provide a nuclear reactor repair device that eliminates the above-mentioned problems and enables repair welding and cutting of the inner surface of a reactor vessel.
以下、一実施例の図面を参照して本発明を説明
する。第１図は本発明の原子炉補修設備を原子炉
に設置した状態を示す。第２図は第１図のＡ・Ａ
矢視図における平面図を示す。 The present invention will be described below with reference to the drawings of one embodiment. FIG. 1 shows the nuclear reactor repair equipment of the present invention installed in a nuclear reactor. Figure 2 is A/A of Figure 1.
A plan view in the direction of arrows is shown.
第１図に示すごとく、原子炉容器１は側壁部に
ノズル２を有し、上部面には大回転プラグ３が設
置される。この大回転プラグ３には偏心して小回
転プラグ４が配置され、炉心上部機構６がこの小
回転プラグ４に一体的に取付けられている。また
原子炉容器１の内部には炉心支持構造物５が設け
られる。 As shown in FIG. 1, a reactor vessel 1 has a nozzle 2 on its side wall, and a large rotating plug 3 is installed on its upper surface. A small rotation plug 4 is arranged eccentrically on the large rotation plug 3, and a core upper mechanism 6 is integrally attached to the small rotation plug 4. Further, a core support structure 5 is provided inside the reactor vessel 1 .
前記大回転プラグ３上面には、レーザ溶接・切
断装置９配置される。大回転プラグ３の貫通孔に
は延長管１０が連通し、前記レーザ溶接・切断装
置９に一体的に取りつけられる。延長管１０の下
部端には、レーザ光伝送・集光装置１１が配置さ
れ、さらにレーザ光出口部には開閉可能なシヤツ
ター１１ａを設ける。 A laser welding/cutting device 9 is arranged on the upper surface of the large rotation plug 3. An extension tube 10 communicates with the through hole of the large rotation plug 3 and is integrally attached to the laser welding/cutting device 9. A laser beam transmission and condensing device 11 is arranged at the lower end of the extension tube 10, and a shutter 11a that can be opened and closed is provided at the laser beam outlet.
また、レーザ溶接・切断装置９は、レーザ光伝
送装置１２ａ，１２ｂ，１２ｃを介して、レーザ
発信装置１３に連結され、さらに制御装置１４へ
とつながつている。 Further, the laser welding/cutting device 9 is connected to a laser transmitting device 13 and further to a control device 14 via laser beam transmission devices 12a, 12b, and 12c.
図中８は、大回転プラグ３と係合する回転駆動
装置であり、７は小回転プラグ４に取付けられる
燃料交換装置である。 In the figure, 8 is a rotational drive device that engages with the large-rotation plug 3, and 7 is a fuel exchange device that is attached to the small-rotation plug 4.
次に以上説明の原子炉補修装置を使用して原子
炉容器内の補修作業を行なう手順について説明す
る。まず第１図に示すように大回転プラグ３上の
貫通孔にレーザ溶接・切断装置９を挿入設置す
る。次にレーザ光伝送装置１２ａ，１２ｂ，１２
ｃにより別置のレーザ発信装置１３と光学的に連
結する。次に回転駆動装置８を駆動して大回転プ
ラグ３を回転させ、レーザ溶接・切断装置９を希
望する位置まで移動させる。（原子炉容器内の補
修程度の大きさにもよるが、燃料を炉外に取出
し、冷却機のナトリウムをドレーンして本補修作
業を行なえば、原子炉容器ノズル２はもちろん、
原子炉容器１内のほぼ全方位にレーザ光を到達さ
せることが可能となる。）
所定の位置に停止したら、レーザ溶接・切断装
置に内蔵した駆動部からの遠隔駆動によつて延長
管１０で上下動および回転動を、レーザ伝送・集
光装置１１でレーザ出口方位の微調整を行なえ
る。次に所定位置にエネルギのレーザ光を照射さ
せる。制御装置１４からの制御により各々最適の
溶接・切断条件を実現できる。これにより補修を
必要とする箇所の補修溶接又は切断を容易にしか
も確実で安定した品質で実施できる。実際に溶
接、又は切断を行なうためにレーザ光を照射する
場合にのみシヤツタ１１ａを開くため、レーザ伝
送・集光装置１１が炉内にあつて強い放射線の照
射をうけてレンズ、鏡等の機器が損傷するのを防
止できる。 Next, a procedure for performing repair work inside the reactor vessel using the reactor repair apparatus described above will be explained. First, as shown in FIG. 1, the laser welding/cutting device 9 is inserted into the through hole on the large rotating plug 3. Next, the laser beam transmission devices 12a, 12b, 12
It is optically connected to the separately installed laser transmitting device 13 by c. Next, the rotary drive device 8 is driven to rotate the large rotation plug 3, and the laser welding/cutting device 9 is moved to a desired position. (It depends on the extent of the repair inside the reactor vessel, but if the main repair work is carried out by taking the fuel out of the reactor and draining the sodium from the cooler, the reactor vessel nozzle 2 can be damaged.
It becomes possible for laser light to reach almost all directions inside the reactor vessel 1. ) Once it has stopped at a predetermined position, the extension tube 10 is used to control vertical and rotational movements by remote drive from a drive unit built into the laser welding/cutting device, and the laser transmission/focusing device 11 is used to finely adjust the laser exit direction. can be done. Next, a predetermined position is irradiated with an energetic laser beam. Optimal welding and cutting conditions can be achieved through control from the control device 14. As a result, repair welding or cutting of areas requiring repair can be performed easily and with reliable and stable quality. Since the shutter 11a is opened only when irradiating laser light for actual welding or cutting, the laser transmission/concentration device 11 is inside the furnace and is exposed to strong radiation, causing equipment such as lenses and mirrors to be exposed. can be prevented from being damaged.
以上説明のように、本発明のレーザ溶接・切断
装置は、次のごとき効果を期待できる。 As explained above, the laser welding/cutting apparatus of the present invention can be expected to have the following effects.
高速増殖炉の特徴であるアンダザプラグ概念
のまま、原子炉容器内の補修溶接や切断を遠隔
で容易にかつ安定した品質で確実に行なうこと
ができる。レーザ光を使用しているため軸方向
の長さが著しく長くなつても比較的容易に対応
できる。 While retaining the under-the-plug concept that characterizes fast breeder reactors, repair welding and cutting inside the reactor vessel can be easily and reliably performed remotely with stable quality. Since laser light is used, even if the length in the axial direction becomes significantly long, it can be handled relatively easily.
きわめて密集している原子炉容器蓋上面にあ
つて、占有面積を最少限におさえながら、原子
炉容器内のほゞ全方位に対しレーザ光を到達し
うるため、補修可能はんいが著しく拡大され
る。 Although the upper surface of the reactor vessel lid is extremely densely packed, the laser beam can reach almost all directions inside the reactor vessel while minimizing the occupied area, significantly expanding the number of areas that can be repaired. be done.
高エネルギ密度溶接法を採用しているため、
熱変形もきわめて少なく、かつ材質の変化もご
く局所的に限定できるため良好な補修溶接・切
断ができる。また仕上り状態が非常に良好なた
め溶接・切断後の表面養生（グラインダ仕上げ
等）を行なわずにそのまま各種非破壊検査を行
なうことができるため、工期や工数を短縮でき
る。 Adopting high energy density welding method,
There is very little thermal deformation, and changes in material quality can be limited to very localized areas, allowing for good repair welding and cutting. In addition, since the finished product is in very good condition, various non-destructive tests can be performed on it without surface curing (grinding, etc.) after welding and cutting, which can shorten the construction period and man-hours.
第１図は本発明の原子炉補修装置を設置した原
子炉の概略断面図、第２図は第１図のＡ・Ａ矢視
における断面図である。
３……大回転プラグ、９……レーザ溶接・切断
装置、１０……延長管、１１……レーザ伝送・集
光装置、１２ａ，１２ｂ，１２ｃ……レーザ伝送
装置、１３……レーザ発信装置。
FIG. 1 is a schematic cross-sectional view of a nuclear reactor in which a nuclear reactor repair apparatus of the present invention is installed, and FIG. 2 is a cross-sectional view taken along arrow A-A in FIG. 3... Large rotation plug, 9... Laser welding/cutting device, 10... Extension tube, 11... Laser transmission/concentration device, 12a, 12b, 12c... Laser transmission device, 13... Laser transmitting device.
Claims (1)
端であつて原子炉容器内部に設けられるレーザ光
伝送・集光装置と、前記延長管の他端で回転プラ
グ上に配置される補修装置本体と、この補修装置
本体にレーザ光伝送装置を介して連設されるレー
ザ発信装置とからなる原子炉補修装置。1. A laser beam transmission/concentration device installed inside the reactor vessel at one end of the extension tube installed in the through hole of the rotating plug, and a repair device main body placed on the rotating plug at the other end of the extension tube. and a laser transmitting device connected to the main body of the repair device via a laser beam transmission device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55131548A JPS5756793A (en) | 1980-09-24 | 1980-09-24 | Nuclear reactor repairing device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55131548A JPS5756793A (en) | 1980-09-24 | 1980-09-24 | Nuclear reactor repairing device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5756793A JPS5756793A (en) | 1982-04-05 |
| JPS6158791B2 true JPS6158791B2 (en) | 1986-12-13 |
Family
ID=15060644
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55131548A Granted JPS5756793A (en) | 1980-09-24 | 1980-09-24 | Nuclear reactor repairing device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5756793A (en) |
-
1980
- 1980-09-24 JP JP55131548A patent/JPS5756793A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5756793A (en) | 1982-04-05 |
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