JPH102991A - Device for welding nuclear fuel rod - Google Patents

Device for welding nuclear fuel rod

Info

Publication number
JPH102991A
JPH102991A JP8155417A JP15541796A JPH102991A JP H102991 A JPH102991 A JP H102991A JP 8155417 A JP8155417 A JP 8155417A JP 15541796 A JP15541796 A JP 15541796A JP H102991 A JPH102991 A JP H102991A
Authority
JP
Japan
Prior art keywords
fuel rod
pressure
nuclear fuel
welding
hermetic
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.)
Granted
Application number
JP8155417A
Other languages
Japanese (ja)
Other versions
JP3093637B2 (en
Inventor
Ryosuke Nishikawa
川 良 輔 西
Satoru Kurosawa
沢 哲 黒
Hajime Tsuboi
井 一 坪
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.)
Global Nuclear Fuel Japan Co Ltd
Original Assignee
Japan Nuclear Fuel Co Ltd
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 Japan Nuclear Fuel Co Ltd filed Critical Japan Nuclear Fuel Co Ltd
Priority to JP08155417A priority Critical patent/JP3093637B2/en
Publication of JPH102991A publication Critical patent/JPH102991A/en
Application granted granted Critical
Publication of JP3093637B2 publication Critical patent/JP3093637B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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

  • Arc Welding In General (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)

Abstract

PROBLEM TO BE SOLVED: To prevent the change of gas pressure inside a nuclear fuel rod from causing a poor weld of it when a clad tube of it is welded to an end plug. SOLUTION: When a clad tube 10 is welded to an end plug 11, the expansion of the gas filling a nuclear fuel rod due to welding heat may cause a poor weld. In order to prevent such a poor weld, the pressure inside an airtight welding chamber 22 is controlled to respond to that inside the nuclear fuel rod by controlling an electric back-pressure control valve 24 with program data Pd.

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】この発明は原子燃料棒溶接装
置に係り、特に、原子燃料棒の被覆管と端栓とを溶接す
るときに原子燃料棒内の圧力により溶接部が溶接不良を
起こさないようにした原子燃料棒溶接装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear fuel rod welding apparatus and, more particularly, to a welding portion which does not cause poor welding due to pressure in a nuclear fuel rod when welding a cladding tube and an end plug of the nuclear fuel rod. The present invention relates to a nuclear fuel rod welding apparatus as described above.

【0002】[0002]

【従来の技術】一般に、原子燃料棒の被覆管に対して端
栓を溶着して内部を気密にする場合には、図3に示すよ
うにように気密容器である気密溶接チャンバー13内に
燃料棒の一端を挿入した後、気密溶接チャンバー13内
をヘリウムガス雰囲気とし、上記気密溶接チャンバー1
3内に挿入された燃料棒の被覆管10に端栓11を取り
付け、上記燃料棒を回転させながらTIGアーク溶接電
極12によるアークにより被覆管10と端栓11との接
合部を周方向に溶接することが行われている。
2. Description of the Related Art Generally, when an end plug is welded to a cladding tube of a nuclear fuel rod to make the inside airtight, as shown in FIG. 3, a fuel is placed in an airtight welding chamber 13 which is an airtight container. After inserting one end of the rod, the inside of the hermetic welding chamber 13 is set to a helium gas atmosphere,
An end plug 11 is attached to the cladding tube 10 of the fuel rod inserted into the fuel rod 3, and the joint between the cladding tube 10 and the end plug 11 is circumferentially welded by an arc using the TIG arc welding electrode 12 while rotating the fuel rod. That is being done.

【0003】ところが、TIGアーク溶接電極12のア
ークにより被覆管10と端栓11とを溶接するときに
は、原子燃料棒内のヘリウムガスが溶接熱により熱膨脹
させられ、溶接金属部を内側から風船状に膨みブローホ
ール等による溶接不良を起こすことがある。
However, when the cladding tube 10 and the end plug 11 are welded by the arc of the TIG arc welding electrode 12, the helium gas in the nuclear fuel rod is thermally expanded by welding heat, and the weld metal portion is formed into a balloon shape from the inside. Poor welding may occur due to bulging blow holes and the like.

【0004】そこで、気密溶接チャンバー13には電磁
弁14、15を有する背圧制御バルブ16、17、18
が取り付けられ、気密溶接チャンバー13内の圧力を制
御するようにしている。
[0004] Therefore, back pressure control valves 16, 17, 18 having solenoid valves 14, 15 are provided in the hermetic welding chamber 13.
Is mounted to control the pressure in the hermetic welding chamber 13.

【0005】しかしながら溶接熱による原子燃料棒内の
圧力Pr は図4に示すように溶接開始から溶接終了まで
ある一定の関係をもって上昇変化するのに対し気密溶接
チャンバー13内の圧力Pooは背圧制御バルブ16等の
開閉に伴なって制御されるステップアップ状の圧力とな
る。
However, as shown in FIG. 4, the pressure Pr in the nuclear fuel rod due to the welding heat rises and changes in a certain relationship from the start of welding to the end of welding, whereas the pressure Poo in the hermetic welding chamber 13 is controlled by back pressure control. The pressure becomes a step-up pressure controlled in accordance with the opening and closing of the valve 16 and the like.

【0006】そのため原子燃料棒内の圧力Pr と気密溶
接チャンバー13内の圧力Pooとの圧力較差Pc がバラ
ツキき溶接部にアンバランスポテンシャルが働き溶接不
良を起こすことがあった。
As a result, the pressure difference Pc between the pressure Pr in the nuclear fuel rod and the pressure Po in the hermetic welding chamber 13 fluctuates, and an imbalance potential may act on the welded portion to cause poor welding.

【0007】[0007]

【発明が解決しようとする課題】これを解決するために
背圧制御バルブの数を増加し圧力較差のバラツキきを少
なくすることが行われている。
In order to solve this problem, it has been practiced to increase the number of back pressure control valves and reduce variations in the pressure range.

【0008】しかし、背圧制御バルブの数をいかに増加
しても背圧制御バルブの制御がステップアップ状である
ため圧力較差のバラツキきにより溶接部の溶接不良を撲
滅することがとができないと言う問題があった。
However, no matter how much the number of the back pressure control valves is increased, the control of the back pressure control valves is in a step-up manner. There was a problem to say.

【0009】それに加え背圧制御バルブの数が増加する
とその操作、維持管理等が煩雑になると言う問題があっ
た。
In addition, when the number of back pressure control valves increases, there is a problem that the operation, maintenance and the like become complicated.

【0010】そこで本発明は原子燃料棒の被覆管と端栓
とを溶接するときに原子燃料棒内の圧力に対応するよう
に気密溶接チャンバー内の圧力を制御できるようにした
原子燃料棒溶接装置を得ることを目的とするものであ
る。
Accordingly, the present invention provides a nuclear fuel rod welding apparatus capable of controlling the pressure in an airtight welding chamber so as to correspond to the pressure in the nuclear fuel rod when welding the cladding tube and the end plug of the nuclear fuel rod. The purpose is to obtain.

【0011】[0011]

【発明が解決しようとする課題】そこで本発明は気密溶
接チャンバー内において原子燃料棒の被覆管に端栓を溶
着し、原子燃料棒内に規定圧力のヘリウムガス等の不活
性ガスを封入する原子燃料棒溶接装置において、前記気
密溶接チャンバーに、前記原子燃料棒の被覆管と端栓と
を溶接するときに溶接熱によって生じる前記原子燃料棒
内の圧力の変化に対応して前記気密溶接チャンバー内の
圧力を制御する圧力制御手段を設けたことを特徴とす
る。
SUMMARY OF THE INVENTION Accordingly, the present invention is directed to an atomic reactor in which an end plug is welded to a cladding tube of a nuclear fuel rod in an airtight welding chamber and an inert gas such as helium gas at a specified pressure is sealed in the nuclear fuel rod. In the fuel rod welding apparatus, in the hermetic welding chamber, the cladding tube and the end plug of the nuclear fuel rod are welded to each other in the hermetic welding chamber in response to a change in pressure in the nuclear fuel rod caused by welding heat. And a pressure control means for controlling the pressure of the pressure.

【0012】また、本発明の前記圧力制御手段は、前記
原子燃料棒内の圧力の変化をプログラムパターン化した
パターンデータとして読込み、このパターンデータによ
り前記気密溶接チャンバー内の圧力を制御することを特
徴とする。
Further, the pressure control means of the present invention reads a change in pressure in the nuclear fuel rod as pattern data obtained by program patterning, and controls the pressure in the hermetic welding chamber based on the pattern data. And

【0013】さらに、本発明の前記パターンデータによ
る制御信号には前記気密溶接チャンバー内の圧力信号が
フィードバックされることを特徴とする。
Further, a pressure signal in the hermetic welding chamber is fed back to the control signal based on the pattern data of the present invention.

【0014】さらに、本発明の前記圧力制御手段は、前
記原子燃料棒内の圧力に対応して前記気密溶接チャンバ
ー内の圧力を制御する電動背圧制御バルブであることを
特徴とする。
Further, the pressure control means of the present invention is an electric back pressure control valve for controlling the pressure in the hermetic welding chamber in accordance with the pressure in the nuclear fuel rod.

【0015】さらに、本発明の前記圧力制御手段には前
記原子燃料棒の被覆管と端栓とを溶接するときに前記気
密溶接チャンバーの内部で発生する塵埃等を除去するフ
ィルタを設けたことを特徴とする。
Further, the pressure control means of the present invention is provided with a filter for removing dust and the like generated inside the hermetic welding chamber when welding the cladding tube and the end plug of the nuclear fuel rod. Features.

【0016】[0016]

【発明の実施の形態】以下、本発明原子燃料棒溶接装置
の実施の形態を図1について説明する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the nuclear fuel rod welding apparatus according to the present invention will be described below with reference to FIG.

【0017】本発明原子燃料棒溶接装置Aには基礎20
に支持台21を介して気密溶接チャンバー22が据え付
けられている。
The nuclear fuel rod welding apparatus A of the present invention has
An airtight welding chamber 22 is installed via a support 21.

【0018】この気密溶接チャンバー22には原子燃料
棒の被覆管10と端栓11とを溶接するTIGアーク溶
接電極12が備えられ、被覆管10と端栓11とを回転
しながら溶接するようになっている。
The airtight welding chamber 22 is provided with a TIG arc welding electrode 12 for welding the cladding tube 10 of the nuclear fuel rod and the end plug 11 so that the cladding tube 10 and the end plug 11 are welded while rotating. Has become.

【0019】この機密溶接チャンバー22には、また、
フィルター23を備えた電動背圧制御バルブ24および
電動圧力計25が取り付けられ、気密溶接チャンバー2
2内の圧力を電動圧力計25により計測監視しながら電
動背圧制御バルブ24により圧力制御するようになって
いる。
The secret welding chamber 22 also includes:
An electric back pressure control valve 24 equipped with a filter 23 and an electric pressure gauge 25
The pressure in the pressure sensor 2 is controlled by the electric back pressure control valve 24 while monitoring and monitoring the internal pressure by the electric pressure gauge 25.

【0020】また、基礎20にはCPU 、RAM 等を有する
中央演算制御部26が備えられている。この中央演算制
御部26のRAM (図示せず)には気密溶接チャンバー2
2の内部で被覆管10と端栓11とを溶接するときその
溶接熱により原子燃料棒のガスによって変化する原子燃
料棒棒内の圧力Pr に対応する気密溶接チャンバー22
内の圧力Po をプログラムパターン化したパターンデー
タPd として読込んで格納し、電動背圧制御バルブ24
の指令制御電圧とするようにしている。
The base 20 is provided with a central processing control unit 26 having a CPU, a RAM, and the like. The RAM (not shown) of the central processing controller 26 has an airtight welding chamber 2
When the cladding tube 10 and the end plug 11 are welded inside the chamber 2, the hermetic welding chamber 22 corresponding to the pressure Pr in the nuclear fuel rod changed by the gas of the nuclear fuel rod due to the welding heat.
The internal pressure Po is read and stored as pattern data Pd in the form of a program pattern.
Command control voltage.

【0021】この中央演算制御部26と電動圧力計25
とは制御部27に接続され、中央演算制御部26から受
けたパターンデータPd を電動圧力計25が計測し監視
した監視データSd により気密溶接チャンバー22内の
圧力Po を制御し、気密溶接チャンバー22内の圧力P
o と原子燃料棒棒内の圧力Pr との圧力較差Pc が零ま
たはほぼ同じ値になるフィードバックされた制御電圧V
c を得るようにしている。
The central processing controller 26 and the electric pressure gauge 25
Is connected to the control unit 27, and controls the pressure Po in the hermetic welding chamber 22 with the monitoring data Sd measured and monitored by the electric manometer 25 from the pattern data Pd received from the central processing control unit 26. Pressure P
The feedback control voltage V at which the pressure difference Pc between the pressure o and the pressure Pr in the fuel rod becomes zero or almost the same value.
Try to get c.

【0022】この制御部27は電動背圧制御バルブ24
に接続され、フィードバックされた制御電圧Vc を受け
た電動背圧制御バルブ24により気密溶接チャンバー2
2内の圧力Po を原子燃料棒棒内の圧力Pr にほぼ比例
して対応制御するようにしている。
The control unit 27 includes an electric back pressure control valve 24
The airtight welding chamber 2 is connected by an electric back pressure control valve 24 connected to the
The pressure Po in the fuel cell 2 is correspondingly controlled substantially in proportion to the pressure Pr in the fuel rod.

【0023】さらに、フィルター23は被覆管10と端
栓11とを溶接するとき発生する塵埃、煙り等を除去
し、電動背圧制御バルブ24が塵埃等により汚れ性能を
損なわないようにしている。
Further, the filter 23 removes dust and smoke generated when welding the cladding tube 10 and the end plug 11 so that the electric back pressure control valve 24 does not impair the dirt performance due to dust and the like.

【0024】このように構成された原子燃料棒溶接装置
Aの作動を図2を参照しながら説明する。
The operation of the thus constructed nuclear fuel rod welding apparatus A will be described with reference to FIG.

【0025】まず、ペレット、コイルスプリング(いず
れも図示せず)を装填した原子燃料棒の被覆管10およ
び端栓11を気密溶接チャンバー22に回転自在に支持
する。
First, a cladding tube 10 and an end plug 11 of a nuclear fuel rod loaded with a pellet and a coil spring (both not shown) are rotatably supported in a hermetic welding chamber 22.

【0026】つぎに、気密溶接チャンバー22を真空排
気した後加圧したヘリウムガスを気密溶接チャンバー2
2および原子燃料棒に充填する。このようにしてから被
覆管10の先端部に端栓11を取り付ける。
Next, the airtight welding chamber 22 is evacuated and then pressurized helium gas is supplied to the airtight welding chamber 2.
2 and nuclear fuel rods. After that, the end plug 11 is attached to the tip of the cladding tube 10.

【0027】この予備操作が終了したらTIGアーク溶
接電極12を付勢しそのアークにより被覆管10と端栓
11とを回転しながら溶接する。この溶接開始と同時に
電動背圧制御バルブ24、電動圧力計25、中央演算制
御部26、制御部27を運転する。
When this preliminary operation is completed, the TIG arc welding electrode 12 is energized, and the cladding tube 10 and the end plug 11 are welded while rotating by the arc. Simultaneously with the start of the welding, the electric back pressure control valve 24, the electric manometer 25, the central processing control unit 26, and the control unit 27 are operated.

【0028】被覆管10と端栓11との溶接を開始する
と溶接開始時点から溶接終了時点にかけて原子燃料棒内
の圧力Pr が図2に示すように上昇する。
When welding of the cladding tube 10 and the end plug 11 is started, the pressure Pr in the nuclear fuel rod rises from the start of welding to the end of welding as shown in FIG.

【0029】この原子燃料棒内の圧力Pr の上昇変化に
対応するように中央演算制御部26から制御部27にパ
ターンデータPd を送る。このパターンデータPd が制
御部27により制御電圧Vc として電動背圧制御バルブ
24に送られそのバルブを比例制御する。
The pattern data Pd is sent from the central processing control unit 26 to the control unit 27 so as to correspond to the increase in the pressure Pr in the nuclear fuel rod. The pattern data Pd is sent to the electric back pressure control valve 24 as a control voltage Vc by the control section 27, and the valve is proportionally controlled.

【0030】このバルブの比例制御により気密溶接チャ
ンバー22内の圧力Po を原子燃料棒内の圧力Pr に対
応させる。このような制御において気密溶接チャンバー
22内の圧力Po がパターンデータPd による圧力より
高いかあるいは低い場合には電動圧力計25による監視
データSd により制御電圧Vc をフィードバック制御
し、常に、制御電圧Vc を原子燃料棒内の圧力Pr に対
応するようにする。
By the proportional control of this valve, the pressure Po in the hermetic welding chamber 22 is made to correspond to the pressure Pr in the nuclear fuel rod. In such control, when the pressure Po in the hermetic welding chamber 22 is higher or lower than the pressure based on the pattern data Pd, the control voltage Vc is feedback-controlled based on the monitoring data Sd by the electric pressure gauge 25, and the control voltage Vc is constantly controlled. The pressure corresponds to the pressure Pr in the nuclear fuel rod.

【0031】これら制御を通じて気密溶接チャンバー2
2内の圧力Po を原子燃料棒内の圧力Pr の上昇に対応
して変化させるから被覆管10と端栓11との溶接部に
ブローホール等による溶接不良を起こすことがない。そ
のため、原子燃料棒の溶接品質を高め歩留まりを向上さ
せることができる。
The airtight welding chamber 2 is controlled through these controls.
Since the pressure Po in 2 is changed in accordance with the rise in the pressure Pr in the nuclear fuel rod, welding failure due to blow holes or the like does not occur in the welded portion between the cladding tube 10 and the end plug 11. Therefore, the welding quality of the nuclear fuel rods can be improved and the yield can be improved.

【0032】また、この溶接時に気密溶接チャンバー2
2に発生するスス等をフィルタ11により除去し電動背
圧制御バルブ28を汚さないから電動背圧制御バルブ2
8の性能を低下させることがない。
At the time of this welding, the hermetic welding chamber 2
2 is removed by the filter 11 and the electric back pressure control valve 28 is not stained.
8 does not degrade.

【0033】そのため、電動背圧制御バルブ28を長時
間安定して運転することができる。
Therefore, the electric back pressure control valve 28 can be operated stably for a long time.

【0034】[0034]

【発明の効果】本発明は気密溶接チャンバー内において
原子燃料棒の被覆管に端栓を溶着し、原子燃料棒内に規
定圧力のヘリウムガス等の不活性ガスを封入する原子燃
料棒溶接装置において、前記気密溶接チャンバーに、前
記原子燃料棒の被覆管と端栓とを溶接するときに溶接熱
によって生じる前記原子燃料棒内の圧力の変化に対応し
て前記気密溶接チャンバー内の圧力を制御する圧力制御
手段を設けたから気密溶接チャンバー内の圧力を原子燃
料棒内の圧力に比例して上昇させ被覆管と端栓との溶接
部に圧力のバラツキによるブローホール等による溶接不
良の発生を防止することができる。
The present invention relates to a nuclear fuel rod welding apparatus in which an end plug is welded to a cladding tube of a nuclear fuel rod in an airtight welding chamber and an inert gas such as helium gas at a specified pressure is sealed in the nuclear fuel rod. Controlling the pressure in the hermetic welding chamber in response to a change in pressure in the nuclear fuel rod caused by welding heat when welding the cladding tube and the end plug of the nuclear fuel rod to the hermetic welding chamber. Since the pressure control means is provided, the pressure in the hermetic welding chamber is increased in proportion to the pressure in the nuclear fuel rod, thereby preventing the occurrence of welding defects due to blow holes due to pressure variations in the weld between the cladding tube and the end plug. be able to.

【0035】また、本発明の前記圧力制御手段は、前記
原子燃料棒内の圧力の変化をプログラムパターン化した
パターンデータとして読込み、このパターンデータによ
り前記気密溶接チャンバー内の圧力を制御するようにし
たから圧力制御手段をパターンデータにより良好に制御
することができる。
Further, the pressure control means of the present invention reads a change in pressure in the nuclear fuel rod as pattern data in the form of a program pattern, and controls the pressure in the hermetic welding chamber according to the pattern data. Therefore, the pressure control means can be favorably controlled by the pattern data.

【0036】さらに、本発明の前記パターンデータによ
る制御信号には前記気密溶接チャンバー内の圧力信号を
フィードバックしたから気密溶接チャンバー内の圧力が
パターンデータと異なることがあっても気密溶接チャン
バー内の圧力を原子燃料棒内の圧力に比例して制御する
ことができる。
Further, since the pressure signal in the hermetic welding chamber is fed back to the control signal based on the pattern data of the present invention, even if the pressure in the hermetic welding chamber is different from the pattern data, the pressure in the hermetic welding chamber may be different. Can be controlled in proportion to the pressure in the nuclear fuel rod.

【0037】さらに、本発明の前記圧力制御手段は、前
記原子燃料棒内の圧力に対応して前記気密溶接チャンバ
ー内の圧力を制御する電動背圧制御バルブにしたから気
密溶接チャンバー内の圧力を電気的に比例して原子燃料
棒内の圧力に対応制御することができる。
Further, the pressure control means of the present invention is an electric back pressure control valve for controlling the pressure in the hermetic welding chamber in accordance with the pressure in the nuclear fuel rod, so that the pressure in the hermetic welding chamber is reduced. The pressure in the nuclear fuel rod can be controlled correspondingly electrically proportionally.

【0038】さらに、本発明の前記圧力制御手段には前
記原子燃料棒の被覆管と端栓とを溶接するときに前記気
密溶接チャンバーの内部で発生する塵埃等を除去するフ
ィルタを設けたから圧力制御手段を塵埃等により汚すこ
とがない。
Further, the pressure control means of the present invention is provided with a filter for removing dust and the like generated inside the hermetic welding chamber when welding the cladding tube and the end plug of the nuclear fuel rod. The means is not contaminated by dust or the like.

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

【図1】本発明原子燃料棒溶接装置の概要を示す説明
図。
FIG. 1 is an explanatory view showing an outline of a nuclear fuel rod welding apparatus of the present invention.

【図2】本発明の機密溶接チャンバー内の圧力と原子燃
料棒内の圧力とを示す特性曲線図。
FIG. 2 is a characteristic curve diagram showing a pressure in a secure welding chamber and a pressure in a nuclear fuel rod according to the present invention.

【図3】従来の原子燃料棒溶接装置の概要を示す説明
図。
FIG. 3 is an explanatory view showing an outline of a conventional nuclear fuel rod welding apparatus.

【図4】従来の機密溶接チャンバーのチャンバー内の圧
力と原子燃料棒内の圧力とを示す特性曲線図。
FIG. 4 is a characteristic curve diagram showing a pressure inside a conventional secure welding chamber and a pressure inside a nuclear fuel rod.

【符号の説明】[Explanation of symbols]

A、 原子燃料棒溶接装置 10 原子燃料棒の被覆管 11 端栓 12 TIGアーク溶接電極 13、22 気密溶接チャンバー 14、15 電磁弁 16、17、18 背圧制御バルブ 23 フィルター 24 電動背圧制御バルブ 25 電動圧力計 26 中央演算制御部 27 圧力制御部 A, Nuclear fuel rod welding device 10 Clad tube of nuclear fuel rod 11 End plug 12 TIG arc welding electrode 13, 22 Airtight welding chamber 14, 15 Electromagnetic valve 16, 17, 18 Back pressure control valve 23 Filter 24 Electric back pressure control valve 25 Electric pressure gauge 26 Central processing control unit 27 Pressure control unit

Claims (5)

【特許請求の範囲】[Claims] 【請求項1】気密溶接チャンバー内において原子燃料棒
の被覆管に端栓を溶着し、原子燃料棒内に規定圧力のヘ
リウムガス等の不活性ガスを封入する原子燃料棒溶接装
置において、 前記気密溶接チャンバーに、前記原子燃料棒の被覆管と
端栓とを溶接するときに溶接熱によって生じる前記原子
燃料棒内の圧力の変化に対応して前記気密溶接チャンバ
ー内の圧力を制御する圧力制御手段を設けたことを特徴
とする原子燃料棒溶接装置。
1. A nuclear fuel rod welding apparatus for welding an end plug to a cladding tube of a nuclear fuel rod in an airtight welding chamber and enclosing an inert gas such as helium gas at a specified pressure in the nuclear fuel rod. Pressure control means for controlling the pressure in the hermetic welding chamber in response to a change in pressure in the nuclear fuel rod caused by welding heat when welding the cladding tube and the end plug of the nuclear fuel rod to a welding chamber. A nuclear fuel rod welding apparatus characterized by comprising:
【請求項2】前記圧力制御手段は、前記原子燃料棒内の
圧力の変化をプログラムパターン化したパターンデータ
として読込み、このパターンデータにより前記気密溶接
チャンバー内の圧力を制御することを特徴とする請求項
1に記載の原子燃料棒溶接装置。
2. The pressure control means reads a change in pressure in the nuclear fuel rod as pattern data obtained by program patterning, and controls the pressure in the hermetic welding chamber based on the pattern data. Item 8. A nuclear fuel rod welding apparatus according to Item 1.
【請求項3】前記パターンデータによる制御信号には前
記気密溶接チャンバー内の圧力信号がフィードバックさ
れることを特徴とする請求項2に記載の原子燃料棒溶接
装置。
3. The apparatus according to claim 2, wherein a pressure signal in the hermetic welding chamber is fed back to the control signal based on the pattern data.
【請求項4】前記圧力制御手段は、前記原子燃料棒内の
圧力に対応して前記気密溶接チャンバー内の圧力を制御
する電動背圧制御バルブであることを特徴とする請求項
1乃至3のいずれかに記載の原子燃料棒溶接装置。
4. The valve according to claim 1, wherein said pressure control means is an electric back pressure control valve for controlling a pressure in said hermetic welding chamber in accordance with a pressure in said nuclear fuel rod. The nuclear fuel rod welding apparatus according to any one of the above.
【請求項5】前記圧力制御手段には前記原子燃料棒の被
覆管と端栓とを溶接するときに前記気密溶接チャンバー
の内部で発生する塵埃等を除去するフィルタを設けたこ
とを特徴とする請求項1乃至4に記載の原子燃料棒溶接
装置。
5. The pressure control means is provided with a filter for removing dust and the like generated inside the hermetic welding chamber when welding the cladding tube and the end plug of the nuclear fuel rod. The nuclear fuel rod welding apparatus according to claim 1.
JP08155417A 1996-06-17 1996-06-17 Nuclear fuel rod welding equipment Expired - Fee Related JP3093637B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP08155417A JP3093637B2 (en) 1996-06-17 1996-06-17 Nuclear fuel rod welding equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP08155417A JP3093637B2 (en) 1996-06-17 1996-06-17 Nuclear fuel rod welding equipment

Publications (2)

Publication Number Publication Date
JPH102991A true JPH102991A (en) 1998-01-06
JP3093637B2 JP3093637B2 (en) 2000-10-03

Family

ID=15605551

Family Applications (1)

Application Number Title Priority Date Filing Date
JP08155417A Expired - Fee Related JP3093637B2 (en) 1996-06-17 1996-06-17 Nuclear fuel rod welding equipment

Country Status (1)

Country Link
JP (1) JP3093637B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110170724A (en) * 2019-05-31 2019-08-27 上海大学 A kind of fuel assembly welder
US10692610B2 (en) 2015-03-24 2020-06-23 Westinghouse Electric Sweden Ab Method of controlling pressure in a fuel rod

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10692610B2 (en) 2015-03-24 2020-06-23 Westinghouse Electric Sweden Ab Method of controlling pressure in a fuel rod
CN110170724A (en) * 2019-05-31 2019-08-27 上海大学 A kind of fuel assembly welder

Also Published As

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