JP3113174B2 - Nuclear fuel cladding welding method and welding device - Google Patents

Nuclear fuel cladding welding method and welding device

Info

Publication number
JP3113174B2
JP3113174B2 JP07156391A JP15639195A JP3113174B2 JP 3113174 B2 JP3113174 B2 JP 3113174B2 JP 07156391 A JP07156391 A JP 07156391A JP 15639195 A JP15639195 A JP 15639195A JP 3113174 B2 JP3113174 B2 JP 3113174B2
Authority
JP
Japan
Prior art keywords
welding
nuclear fuel
fuel cladding
cladding tube
chamber
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 - Lifetime
Application number
JP07156391A
Other languages
Japanese (ja)
Other versions
JPH095486A (en
Inventor
嶋 輝 昭 三
米 智 明 久
納 利 之 加
沢 哲 黒
川 良 輔 西
Original Assignee
日本ニユクリア・フユエル株式会社
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
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Priority to JP07156391A priority Critical patent/JP3113174B2/en
Publication of JPH095486A publication Critical patent/JPH095486A/en
Application granted granted Critical
Publication of JP3113174B2 publication Critical patent/JP3113174B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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

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  • Butt Welding And Welding Of Specific Article (AREA)

Description

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

【0001】[0001]

【産業上の利用分野】本発明は、核燃料被覆管の端栓溶
接方法及び装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method and an apparatus for welding end plugs of a nuclear fuel cladding tube.

【0002】[0002]

【従来の技術】一般に、核燃料被覆管の開口端部に端栓
を挿入溶着する場合には、不活性ガス雰囲気とされた溶
接チャンバー内で行なわれる。
2. Description of the Related Art Generally, when an end plug is inserted and welded at the open end of a nuclear fuel cladding tube, the welding is performed in a welding chamber in an inert gas atmosphere.

【0003】すなわち、図4は従来の核燃料被覆管の溶
接装置を示す図であって、溶接チャンバー1の一側壁部
には核燃料被覆管2の一開口端側を気密的に挿入し得る
開口が設けられており、この開口と対向する部分には、
上記溶接チャンバー内に挿入された被覆管の開口端に正
対させて端栓3を保持する端栓保持具4が配設され、そ
の外部には上記端栓保持具4に保持された端栓3を被覆
管端に圧接する端栓圧入機構5が設けられ、さらに頂壁
部には溶接トーチ6が垂設されている。
FIG. 4 is a view showing a conventional welding apparatus for a nuclear fuel cladding tube. An opening through which one opening end side of the nuclear fuel cladding tube 2 can be hermetically inserted is provided on one side wall of the welding chamber 1. It is provided, and in the part facing this opening,
An end plug holder 4 for holding the end plug 3 is provided facing the open end of the cladding tube inserted into the welding chamber, and an end plug held by the end plug holder 4 is provided outside the end plug holder. An end plug press-fitting mechanism 5 for pressing the end 3 into contact with the cladding tube end is provided, and a welding torch 6 is vertically provided on the top wall.

【0004】そこで、上記核燃料被覆管2に端栓を装着
溶接する場合には、その核燃料被覆管2の端栓装着を行
なう側の一開口端側を溶接チャンバー1内に挿入し、他
方の開口端側を気密性の保持具7によって保持した後、
上記溶接チャンバー1内及び核燃料被覆管2内を所定の
真空度まで真空排気する。その後、上記溶接チャンバー
1内に不活性ガスを導入し溶接チャンバー内をほぼ大気
圧状態にする。
In order to mount and weld an end plug on the nuclear fuel cladding tube 2, one end of the nuclear fuel cladding tube 2 on which the end plug is to be mounted is inserted into the welding chamber 1 and the other opening is provided. After holding the end side with the airtight holding tool 7,
The inside of the welding chamber 1 and the inside of the nuclear fuel cladding tube 2 are evacuated to a predetermined degree of vacuum. Thereafter, an inert gas is introduced into the welding chamber 1 to bring the interior of the welding chamber into a substantially atmospheric pressure state.

【0005】この状態から、端栓圧入機構5によって、
先端に端栓3を保持している端栓保持具4が前進せしめ
られ、上記端栓3が核燃料被覆管2の開口端に圧入され
る。
From this state, the end plug press-fitting mechanism 5
The end plug holder 4 holding the end plug 3 at the tip is advanced, and the end plug 3 is pressed into the open end of the nuclear fuel cladding tube 2.

【0006】次に、回転機構8によって核燃料被覆管2
を軸線回りに回転させながら、核燃料被覆管2と端栓3
の突き合わせ面を周溶接する。
Next, the nuclear fuel cladding tube 2 is rotated by the rotating mechanism 8.
Is rotated around the axis while the nuclear fuel cladding tube 2 and the end plug 3 are rotated.
Girth weld the butted surface of.

【0007】[0007]

【発明が解決しようとする課題】ところが、上述の如き
装置による溶接においては、その溶接時における熱影響
のため被覆管2内のガスが膨張し若干の内圧上昇を引き
起すことになる。すなわち、図5に示すように、溶接時
間に応じて被覆管内圧が点線で示す限界圧力を超え、図
6(a)に示すように、溶融金属10が内部から押上げ
られ、溶接仕上り外径Dが大きくなったり、或は図6
(b)に示すように溶融金属10の一部に膨れ部11が
生じ、核燃料被覆管2の許容肉厚tが小さくなることが
あり、溶接品質が安定せず収率を低下させる等の問題が
ある。
However, in welding by the above-described apparatus, the gas in the cladding tube 2 expands due to the heat effect at the time of welding, causing a slight increase in the internal pressure. In other words, as shown in FIG. 5, the cladding internal pressure exceeds the limit pressure indicated by the dotted line according to the welding time, and as shown in FIG. D becomes large, or
As shown in (b), a swelling portion 11 is formed in a part of the molten metal 10, and the allowable thickness t of the nuclear fuel cladding tube 2 may be reduced, and the welding quality is not stable and the yield is reduced. There is.

【0008】そこで、溶接時に溶接チャンバー1内の圧
力を上昇させ上記問題を解決することも提案されている
が、この加圧状態では図7(a)に示すように、溶融金
属10に加圧量が作用し、溶融金属が被覆管2の内部に
溶け落ち、端栓3との間に気泡を取り込み気孔13を発
生させたり、溶融金属に凹部14が発生し溶接部の外観
が損なわれる等の問題がある。
Therefore, it has been proposed to solve the above problem by increasing the pressure in the welding chamber 1 during welding. However, in this pressurized state, as shown in FIG. The molten metal melts down into the inside of the cladding tube 2 to take in air bubbles between the end plug 3 and generate pores 13, and a concave portion 14 is generated in the molten metal to impair the appearance of the welded portion. There is a problem.

【0009】本発明はこのような点に鑑み、核燃料被覆
管溶接時における熱影響による被覆管の内圧上昇を溶接
欠陥発生の限界圧力以内に制御し得るようにした核燃料
被覆管溶接方法及び装置を得ることを目的とする。
In view of the foregoing, the present invention provides a nuclear fuel cladding welding method and apparatus capable of controlling the internal pressure rise of the cladding due to the heat effect during welding of the nuclear fuel cladding within the limit pressure at which welding defects occur. The purpose is to gain.

【0010】[0010]

【課題を解決するための手段】第1の発明は核燃料被覆
管の端栓溶接側端部を溶接チャンバー内に挿入し、他端
側を保持具によって保持して、上記溶接チャンバー内で
上記核燃料被覆管の一開口端に端栓を溶接する核燃料被
覆管溶接方法において、上記溶接チャンバーから外部に
突出している核燃料被覆管の開口端に、その核燃料被覆
管内に連通するシリンダー室を有する圧力低減装置を気
密的に装着し、そのシリンダー室内に摺動自在に配設さ
れたピストンを被覆管と反対方向に移動させることによ
り、溶接時に上記被覆管内の圧力上昇を低減させること
を特徴とする。
According to a first aspect of the present invention, an end plug welding side end of a nuclear fuel cladding tube is inserted into a welding chamber, and the other end side is held by a holder. A nuclear fuel cladding welding method for welding an end plug to one opening end of a cladding tube, the pressure reducing device having a cylinder chamber communicating with the inside of the nuclear fuel cladding tube at an opening end of the nuclear fuel cladding tube protruding outside from the welding chamber. Is mounted in an airtight manner, and a piston slidably disposed in the cylinder chamber is moved in a direction opposite to the cladding tube, whereby a pressure rise in the cladding tube during welding is reduced.

【0011】また、第2の発明は、溶接チャンバーから
外部に突出している核燃料被覆管の開口端に、上記核燃
料被覆管内のみに連通するシリンダー室を有する圧力低
減装置を気密的に装着し、そのシリンダー室内に配設さ
れたピストンを被覆管と反対方向に移動させることによ
り溶接時に上記シリンダー室内の容量を変更するように
したことを特徴とする。
According to a second aspect of the present invention, a pressure reducing device having a cylinder chamber communicating only inside the nuclear fuel cladding tube is hermetically attached to an open end of the nuclear fuel cladding tube projecting outside from the welding chamber. The capacity in the cylinder chamber is changed at the time of welding by moving a piston disposed in the cylinder chamber in a direction opposite to the cladding tube.

【0012】[0012]

【作用】核燃料被覆管の開口端にその被覆管内に連通す
る所定容量の空室を有する圧力低減装置を気密的に装着
することにより、端栓の溶接時における被覆管内の内圧
の上昇が上記圧力低減装置の容積に応じて低減され、被
覆管の内圧上昇を溶接欠陥が発生する限界圧力以内に制
御することができる。
By pressure-tightly mounting a pressure reducing device having a vacant chamber of a predetermined volume communicating with the inside of the cladding tube at the open end of the nuclear fuel cladding tube, the internal pressure in the cladding tube at the time of welding of the plug is increased by the pressure. It is reduced according to the volume of the reduction device, and the internal pressure rise of the cladding tube can be controlled within the limit pressure at which welding defects occur.

【0013】[0013]

【実施例】以下、図1乃至図3を参照して本発明の実施
例について説明する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS.

【0014】図1において、符号1は溶接チャンバーで
あって、その溶接チャンバー1の一側には、上記溶接チ
ャンバー1内に溶接端側が挿入された核燃料被覆管2を
その軸線回りに回転させる回転機構部8が配設されてお
り、また上記溶接チャンバー1の他側壁部には、溶接チ
ャンバー内に挿入された被覆管と同一軸線上に端栓保持
具4が設けられ、その端栓保持具4が端栓圧入機構5に
よって前後動可能としてある。
In FIG. 1, reference numeral 1 denotes a welding chamber. On one side of the welding chamber 1, a rotation for rotating a nuclear fuel cladding tube 2 having a welding end inserted into the welding chamber 1 around its axis. A mechanism portion 8 is provided, and an end plug holder 4 is provided on the other side wall portion of the welding chamber 1 on the same axis as the cladding tube inserted into the welding chamber. 4 can be moved back and forth by an end plug press-fitting mechanism 5.

【0015】一方、溶接チャンバー1の一側には核燃料
被覆管2の外端部を気密的に保持する被覆管保持具7が
配設されており、その被覆管保持具7には圧力低減装置
20が連結されている。
On the other hand, a cladding holder 7 for holding the outer end of the nuclear fuel cladding 2 in an airtight manner is provided on one side of the welding chamber 1, and the cladding holder 7 has a pressure reducing device. 20 are connected.

【0016】上記圧力低減装置20は、被覆管2内に連
通するシリンダ室21を有し、そのシリンダ室21内に
ピストン22が摺動自在に配設され、そのピストン22
に連結され被覆管2と反対方向に突出するピストンロッ
ド23の端部に連結部材を介して雌ねじ部材24が設け
られ、その雌ねじ部材24が、モータ25によって回転
駆動されるねじ軸26に螺合されている。
The pressure reducing device 20 has a cylinder chamber 21 communicating with the inside of the cladding tube 2, and a piston 22 is slidably disposed in the cylinder chamber 21.
A female screw member 24 is provided via a connecting member at an end of a piston rod 23 projecting in a direction opposite to the cladding tube 2, and the female screw member 24 is screwed to a screw shaft 26 rotationally driven by a motor 25. Have been.

【0017】しかして、核燃料被覆管2の端部に端栓3
を溶着する場合には、その核燃料被覆管2の一つの開口
端部を溶接チャンバー1内に挿入し、他方の開口端部を
被覆管保持具7で保持する。そして、溶接チャンバー1
及び被覆管2内を所定の真空度まで真空排気した後、溶
接チャンバー1内に不活性ガスを充填しほぼ大気圧状態
とする。
The end plug 3 is attached to the end of the nuclear fuel cladding tube 2.
Is welded, one open end of the nuclear fuel cladding tube 2 is inserted into the welding chamber 1, and the other open end is held by the cladding tube holder 7. And the welding chamber 1
After the inside of the cladding tube 2 is evacuated to a predetermined degree of vacuum, the welding chamber 1 is filled with an inert gas to make it substantially at atmospheric pressure.

【0018】その後、上記状態で端栓3を核燃料被覆管
2に圧入し、その核燃料被覆管2を回転させながら端栓
3と核燃料被覆管2の突き合わせ面を周溶接する。
Thereafter, the end plug 3 is pressed into the nuclear fuel cladding tube 2 in the above-mentioned state, and the butt surface of the end plug 3 and the nuclear fuel cladding tube 2 is circumferentially welded while rotating the nuclear fuel cladding tube 2.

【0019】この場合、溶接による熱影響で核燃料被覆
管2の内圧が上昇するが、この内圧上昇に応じるように
モータ25が駆動され、ねじ軸26、雌ねじ24及びピ
ストンロッド23を介してピストン22が外方(図にお
いて左方)に移動される。
In this case, the internal pressure of the nuclear fuel cladding tube 2 rises due to the heat effect of the welding. The motor 25 is driven in response to the rise in the internal pressure, and the piston 22 is driven through the screw shaft 26, the female screw 24 and the piston rod 23. Is moved outward (to the left in the figure).

【0020】したがって、核燃料被覆管2内に連通する
空所の容積が増加する方向に制御され、核燃料被覆管2
内の圧力が溶接欠陥が発生する限界圧力以内におさえら
れ、溶接仕上り径の増大、肉厚不足の発生或は気孔の発
生等が防止される。
Therefore, the volume of the cavity communicating with the nuclear fuel cladding tube 2 is controlled to increase, and the nuclear fuel cladding tube 2 is controlled.
The internal pressure is kept within the limit pressure at which a welding defect occurs, thereby preventing an increase in the finished diameter of the weld, a lack of wall thickness or the generation of pores.

【0021】図2は、上記圧力低減装置を使用した場合
の核燃料被覆管2の溶接時の内圧上昇の状況を示す図で
あり、実線で示すように溶接時の内圧は溶接時間に対応
して上昇するけれども、破線Aで示す溶接仕上り径の増
大及び肉厚不足等の溶接欠陥発生が生じる限界圧力と、
破線Bで示す溶接外観及び気孔等の溶接欠陥発生に生じ
る限界圧力との間となっている。
FIG. 2 is a view showing a situation where the internal pressure rises during welding of the nuclear fuel cladding tube 2 when the above-mentioned pressure reducing device is used. As shown by a solid line, the internal pressure at the time of welding corresponds to the welding time. A critical pressure at which welding defects such as an increase in the weld finish diameter and a lack of wall thickness as indicated by a dashed line A occur,
It is between the welding appearance shown by the dashed line B and the critical pressure that occurs when welding defects such as pores occur.

【0022】ところで、実際の溶接においては、入熱条
件が一定しており、また核燃料被覆管の内圧上昇も繰り
返し性があることから、図3に示すように、ピストン2
2をねじ軸27により手動により移動させ容量可変とし
てもよい。
In actual welding, since the heat input condition is constant and the internal pressure of the nuclear fuel cladding rises repetitively, as shown in FIG.
2 may be manually moved by the screw shaft 27 to make the capacity variable.

【0023】[0023]

【発明の効果】以上説明したように、本発明は溶接チャ
ンバーから外部に突出している核燃料被覆管の開口端
に、その核燃料被覆管内に連通するシリンダー室を有す
る圧力低減装置を気密的に装着し、そのシリンダー室内
に摺動自在に配設されたピストンを被覆管と反対方向に
移動させることにより、溶接時に上記被覆管内の圧力上
昇を低減させるようにしたので、そのシリンダー室によ
って溶接時における被覆管の内圧の上昇を低減させるこ
とができ、内圧の影響により溶融金属が内部から押し上
げられ溶接仕上り外径が大きくなったり、或は膨れ部が
生じることを防止することができ、溶接欠陥の発生を防
止し、溶接品質を安定させることができる。
As described above, according to the present invention, a pressure reducing device having a cylinder chamber communicating with the inside of a nuclear fuel cladding tube is hermetically mounted at the open end of the nuclear fuel cladding tube projecting outside from the welding chamber. By moving the piston slidably disposed in the cylinder chamber in the opposite direction to the cladding tube, the pressure rise in the cladding tube during welding is reduced. It is possible to reduce the rise in internal pressure of the pipe, prevent the molten metal from being pushed up from the inside by the influence of the internal pressure, and prevent the weld finish outer diameter from becoming large, or prevent the occurrence of bulging parts, and the occurrence of welding defects Can be prevented and welding quality can be stabilized.

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

【図1】本発明の核燃料被覆管の溶接装置の概略構成を
示す図。
FIG. 1 is a view showing a schematic configuration of a welding apparatus for a nuclear fuel cladding tube of the present invention.

【図2】溶接時の被覆管内圧と溶接欠陥発生の限界圧力
の関係を示す図。
FIG. 2 is a view showing the relationship between the cladding internal pressure during welding and the critical pressure at which welding defects occur.

【図3】本発明の圧力低減装置の他の実施例を示す図。FIG. 3 is a diagram showing another embodiment of the pressure reducing device of the present invention.

【図4】従来の溶接装置の概略説明図。FIG. 4 is a schematic explanatory view of a conventional welding device.

【図5】従来の装置における溶接時の被覆管内圧と溶接
欠陥発生の限界圧力の関係を示す図。
FIG. 5 is a diagram showing the relationship between the cladding internal pressure during welding and the critical pressure at which welding defects occur in a conventional apparatus.

【図6】従来方法における溶接欠陥の具体例を示す図。FIG. 6 is a diagram showing a specific example of a welding defect in a conventional method.

【図7】従来方法における他の溶接欠陥の具体例を示す
図。
FIG. 7 is a diagram showing a specific example of another welding defect in the conventional method.

【符号の説明】[Explanation of symbols]

1 溶接チャンバー 2 核燃料被覆管 3 端栓 7 被覆管保持具 20 圧力低減装置 21 シリンダ室 22 ピストン 25 モータ 26 ねじ軸 DESCRIPTION OF SYMBOLS 1 Welding chamber 2 Nuclear fuel cladding tube 3 End plug 7 Cladding tube holder 20 Pressure reducing device 21 Cylinder chamber 22 Piston 25 Motor 26 Screw shaft

───────────────────────────────────────────────────── フロントページの続き (72)発明者 黒 沢 哲 神奈川県横須賀市内川二丁目3番1号 日本ニユクリア・フユエル株式会社内 (72)発明者 西 川 良 輔 神奈川県横須賀市内川二丁目3番1号 日本ニユクリア・フユエル株式会社内 (56)参考文献 特開 昭62−227580(JP,A) (58)調査した分野(Int.Cl.7,DB名) G21C 3/16 G21C 21/02 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Inventor Satoshi Kurosawa 2-3-1, Kawakawa, Yokosuka City, Kanagawa Prefecture Inside Nihonkuri Fuyuer Co., Ltd. (72) Ryosuke Nishikawa 2-3-3 Kawa, Yokosuka City, Kanagawa Prefecture No. 1 Inside Nihonkuri Fuyuer Co., Ltd. (56) References JP-A-62-227580 (JP, A) (58) Fields investigated (Int. Cl. 7 , DB name) G21C 3/16 G21C 21/02

Claims (2)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】核燃料被覆管の端栓溶接側端部を溶接チャ
ンバー内に挿入し、他端側を保持具によって保持して、
上記溶接チャンバー内で上記核燃料被覆管の一開口端に
端栓を溶接する核燃料被覆管溶接方法において、上記溶
接チャンバーから外部に突出している核燃料被覆管の開
口端に、その核燃料被覆管内に連通するシリンダー室を
有する圧力低減装置を気密的に装着し、そのシリンダー
室内に摺動自在に配設されたピストンを被覆管と反対方
向に移動させることにより、溶接時に上記被覆管内の圧
力上昇を低減させることを特徴とする、核燃料被覆管溶
接方法。
1. An end plug welding end of a nuclear fuel cladding tube is inserted into a welding chamber, and the other end is held by a holder.
In the nuclear fuel cladding welding method for welding an end plug to one opening end of the nuclear fuel cladding in the welding chamber, the nuclear fuel cladding communicates with the opening end of the nuclear fuel cladding projecting outside from the welding chamber into the nuclear fuel cladding. A pressure reduction device having a cylinder chamber is hermetically mounted, and a piston slidably disposed in the cylinder chamber is moved in a direction opposite to the cladding tube, thereby reducing a pressure rise in the cladding tube during welding. A method for welding a nuclear fuel cladding tube, the method comprising:
【請求項2】核燃料被覆管の端栓溶接側端部を溶接チャ
ンバー内に挿入し、他端側を保持具によって保持して、
上記溶接チャンバー内で上記核燃料被覆管の一開口端に
端栓を溶接する核燃料被覆管溶接装置において、上記溶
接チャンバーから外部に突出している核燃料被覆管の開
口端に、上記核燃料被覆管内のみに連通するシリンダー
室を有する圧力低減装置を気密的に装着し、そのシリン
ダー室内に配設されたピストンを被覆管と反対方向に移
動させることにより溶接時に上記シリンダー室内の容量
を変更するようにしたことを特徴とする、核燃料被覆管
溶接装置。
2. An end plug welding side end of a nuclear fuel cladding tube is inserted into a welding chamber, and the other end side is held by a holder.
In a nuclear fuel cladding welding apparatus for welding an end plug to one opening end of the nuclear fuel cladding tube in the welding chamber, an opening end of the nuclear fuel cladding tube protruding outside from the welding chamber communicates only with the nuclear fuel cladding tube. A pressure reducing device having a cylinder chamber to be airtightly mounted, and by moving a piston disposed in the cylinder chamber in a direction opposite to the cladding tube, the capacity of the cylinder chamber is changed at the time of welding. A nuclear fuel cladding tube welding device.
JP07156391A 1995-06-22 1995-06-22 Nuclear fuel cladding welding method and welding device Expired - Lifetime JP3113174B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP07156391A JP3113174B2 (en) 1995-06-22 1995-06-22 Nuclear fuel cladding welding method and welding device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP07156391A JP3113174B2 (en) 1995-06-22 1995-06-22 Nuclear fuel cladding welding method and welding device

Publications (2)

Publication Number Publication Date
JPH095486A JPH095486A (en) 1997-01-10
JP3113174B2 true JP3113174B2 (en) 2000-11-27

Family

ID=15626723

Family Applications (1)

Application Number Title Priority Date Filing Date
JP07156391A Expired - Lifetime JP3113174B2 (en) 1995-06-22 1995-06-22 Nuclear fuel cladding welding method and welding device

Country Status (1)

Country Link
JP (1) JP3113174B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR102273293B1 (en) * 2020-05-11 2021-07-06 한전원자력연료 주식회사 A Welding Machine for the Dashpot Tube and Guide Thimble End Plug of the Fuel Assembly

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR102273293B1 (en) * 2020-05-11 2021-07-06 한전원자력연료 주식회사 A Welding Machine for the Dashpot Tube and Guide Thimble End Plug of the Fuel Assembly

Also Published As

Publication number Publication date
JPH095486A (en) 1997-01-10

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