JPS6321966Y2 - - Google Patents

Info

Publication number
JPS6321966Y2
JPS6321966Y2 JP1983142242U JP14224283U JPS6321966Y2 JP S6321966 Y2 JPS6321966 Y2 JP S6321966Y2 JP 1983142242 U JP1983142242 U JP 1983142242U JP 14224283 U JP14224283 U JP 14224283U JP S6321966 Y2 JPS6321966 Y2 JP S6321966Y2
Authority
JP
Japan
Prior art keywords
nuclear fuel
fuel rod
laser beam
laser
welding
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
Application number
JP1983142242U
Other languages
Japanese (ja)
Other versions
JPS6052075U (en
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 filed Critical
Priority to JP1983142242U priority Critical patent/JPS6052075U/en
Publication of JPS6052075U publication Critical patent/JPS6052075U/en
Application granted granted Critical
Publication of JPS6321966Y2 publication Critical patent/JPS6321966Y2/ja
Granted 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

  • Length Measuring Devices By Optical Means (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)

Description

【考案の詳細な説明】 〔考案の技術分野〕 本考案は、端栓の溶接を終了した核燃料棒にお
ける溶接ビード径を自動的に測定し得るようにし
た核燃料棒自動溶接装置に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to an automatic nuclear fuel rod welding device that is capable of automatically measuring the weld bead diameter of a nuclear fuel rod whose end plug has been welded.

〔考案の技術的背景およびその問題点〕[Technical background of the invention and its problems]

一般に、発電用原子炉等に使用する核燃料棒
は、第1図に示すように、ジルコニウム合金また
はステンレス鋼管の被覆管1内に、二酸化ウラン
UO2などのペレツト2が所定数装填され、そのペ
レツト2を一方に押しつけるためのばね3が挿入
されてあり、また被覆管1の一端には予め被覆管
1と同材質の端栓4が溶着され、ペレツト填装
後、ペレツト挿入を行なった端部に、端栓4と同
材質の端栓5が溶接される。
Generally, nuclear fuel rods used in power reactors, etc., contain uranium dioxide in a cladding tube 1 made of a zirconium alloy or stainless steel tube, as shown in Figure 1.
A predetermined number of pellets 2 such as UO 2 are loaded, a spring 3 is inserted to press the pellets 2 to one side, and an end plug 4 made of the same material as the cladding tube 1 is welded to one end of the cladding tube 1 in advance. After loading the pellets, an end plug 5 made of the same material as the end plug 4 is welded to the end where the pellets were inserted.

ところで、上記核燃料棒の端栓4および5を溶
接した溶接部ビード直径は、核燃料集合体として
組立てる場合に支障がないようにするために所定
寸法以下に管理する必要がある。
Incidentally, the diameter of the weld bead where the end plugs 4 and 5 of the nuclear fuel rod are welded needs to be controlled to a predetermined size or less in order to avoid any problems when assembled as a nuclear fuel assembly.

ところが、従来上記溶接部ビード直径は、マイ
クロメータやリングゲージを使用して作業者によ
る手作業によって測定されていた。したがって、
その測定を行なうためには、溶接終了後燃料棒を
溶接チヤンバーから引き抜いた後、その移動を一
且停止させた状態で行なわねばならず、連続的に
移送させる自動溶接システムにおける一つの隘路
となっていた。
However, conventionally, the diameter of the weld bead has been manually measured by an operator using a micrometer or a ring gauge. therefore,
In order to perform this measurement, the fuel rod must be pulled out of the welding chamber after welding, and then the movement must be stopped, which is a bottleneck in automatic welding systems that continuously transport the fuel rod. was.

〔考案の目的〕[Purpose of invention]

本考案はこのような点に鑑み、溶接ビード外径
の測定を自動的に行なうようにした核燃料棒自動
溶接装置を得ることを目的とする。
In view of these points, the present invention aims to provide an automatic nuclear fuel rod welding device that automatically measures the outer diameter of a weld bead.

〔考案の概要〕[Summary of the idea]

本考案は、溶接チヤンバーから引抜かれる核燃
料棒の搬出系路の側部に、レーザーによる核燃料
棒の溶接ビード径測定装置を配設し、上記測定装
置によって溶接終了後の核燃料様の搬出行程中に
自動的に溶接ビードの外径を測定し得るようにし
たことを特徴とする。
This invention uses a laser to measure the weld bead diameter of nuclear fuel rods on the side of the transport path for nuclear fuel rods that are pulled out from the welding chamber. It is characterized by being able to automatically measure the outer diameter of the weld bead.

〔考案の実施例〕[Example of idea]

以下、第2図を参照して本考案の一実施例につ
いて説明する。
An embodiment of the present invention will be described below with reference to FIG.

第2図において、符号6は溶接トーチ7を有す
る溶接チヤンバーであって、その溶接チヤンバー
6の一側壁には被覆管1の端部を挿入自在とする
開口8が設けられており、他壁側には、端栓4或
は5を保持しこれを核燃料の被覆管1端に圧入す
る端栓圧入機構9が上記開口8と対向して設けら
れている。
In FIG. 2, reference numeral 6 denotes a welding chamber having a welding torch 7. One side wall of the welding chamber 6 is provided with an opening 8 into which the end of the cladding tube 1 can be freely inserted, and the other wall side is provided with an opening 8 into which the end of the cladding tube 1 can be inserted. An end plug press-fitting mechanism 9 is provided opposite the opening 8 for holding the end plug 4 or 5 and press-fitting it into one end of the nuclear fuel cladding tube.

しかして、被覆管1或はその中に所定数の燃料
ペレツト2およびばね3が挿入された核燃料棒
が、開口8を経て溶接チヤンバー6内に挿入さ
れ、端栓圧入機構9によって上記核燃料棒の被覆
管1の端部に端栓4或は5が圧入され、溶接トー
チ7によつて上記端栓4或は5の溶接が行なわれ
る。
Thus, the cladding tube 1 or a nuclear fuel rod in which a predetermined number of fuel pellets 2 and springs 3 are inserted is inserted into the welding chamber 6 through the opening 8, and the end plug press-fitting mechanism 9 closes the nuclear fuel rod. An end plug 4 or 5 is press-fitted into the end of the cladding tube 1, and the end plug 4 or 5 is welded using a welding torch 7.

ところで、上記端栓4或は5の溶接が完了した
核燃料棒を溶接チヤンバー6から引き抜く搬出系
路の途中には、上記核燃料棒の被覆管1を支持す
る支持輪10,10および駆動モータ11によっ
て回転駆動され核燃料棒の外面に圧接される駆動
輪12が、上記核燃料棒の軸線に対して所定角度
傾斜するように配設されている。
By the way, in the middle of the transport path for pulling out the nuclear fuel rods whose end plugs 4 or 5 have been welded from the welding chamber 6, there are support wheels 10, 10 that support the cladding tube 1 of the nuclear fuel rods and a drive motor 11. A drive wheel 12 that is rotatably driven and pressed against the outer surface of the nuclear fuel rod is arranged so as to be inclined at a predetermined angle with respect to the axis of the nuclear fuel rod.

また、上記支持輪10等より溶接チヤンバー6
寄りには上記搬出系路の一側に、溶接チヤンバー
6から引抜かれた核燃料棒の被覆管1の端栓4或
は5の端部を検出する核燃料棒端部検知センサー
13が配設されている。またその核燃料棒端部検
知センサー13によって端栓4或は5の端部が検
知されたとき、溶接ビード部14と対向する位置
には、上記センサー13からの信号によって作動
せしめられレーザー光を発信するレーザー発信器
15が設けられており、核燃料棒の搬出系路をは
さんで上記レーザー発信器15と対向する位置
に、上記レーザー光を受光してその受光量によっ
て溶接ビードの最大直径を算出するためのレーザ
ー受光器16が配設されている。
In addition, the welding chamber 6 is connected to the support ring 10, etc.
A nuclear fuel rod end detection sensor 13 for detecting the end of the end plug 4 or 5 of the cladding tube 1 of the nuclear fuel rod pulled out from the welding chamber 6 is disposed on one side of the delivery path. There is. Further, when the end of the end plug 4 or 5 is detected by the nuclear fuel rod end detection sensor 13, a position facing the weld bead 14 is activated by the signal from the sensor 13 and emits a laser beam. A laser transmitter 15 is provided at a position facing the laser transmitter 15 across the nuclear fuel rod transport path, and receives the laser beam and calculates the maximum diameter of the weld bead based on the amount of received light. A laser receiver 16 is provided for this purpose.

しかして、端栓4或は5の溶接が終了した核燃
料棒が溶接チヤンバー6から引き抜かれると、そ
の核燃料棒の被覆管1は支持輪10,10によっ
て支持されるとともに、駆動モータ11によって
駆動される駆動輪12により回動されながら軸線
方向に移動される。そこで、核燃料棒の端栓4或
は5の端部が核燃料棒端部検知センサー13の位
置に来ると、そのセンサーによってその端栓4或
は5の端部が所定位置に到達したことが検知さ
れ、その検知信号によって駆動モータ11が制御
され、核燃料棒が溶接ビード部14の計測に必要
な回転数および移動速度となるように減速され
る。
When the nuclear fuel rod whose end plug 4 or 5 has been welded is pulled out from the welding chamber 6, the cladding tube 1 of the nuclear fuel rod is supported by the support wheels 10, 10 and is driven by the drive motor 11. It is moved in the axial direction while being rotated by the drive wheels 12. Therefore, when the end of the end plug 4 or 5 of the nuclear fuel rod comes to the position of the nuclear fuel rod end detection sensor 13, the sensor detects that the end of the end plug 4 or 5 has reached a predetermined position. The drive motor 11 is controlled by the detection signal, and the nuclear fuel rod is decelerated to the rotational speed and movement speed necessary for measuring the weld bead portion 14.

一方、それと同時にセンサー13からの信号に
よってレーザー発信器15が作動せしめられ、レ
ーザー光が発信され、そのレーザー光がレーザー
受光器16によって受光され、その受光量から演
算して溶接ビード部14の最大直径が計測され
る。
Meanwhile, at the same time, the laser transmitter 15 is activated by a signal from the sensor 13, and a laser beam is emitted.The laser beam is received by the laser receiver 16, and the amount of the received light is calculated to calculate the maximum The diameter is measured.

このようにして計測が終了すると、駆動モータ
11が増速され、核燃料棒の移動速度が元にもど
されて所定位置に搬送される。
When the measurement is completed in this manner, the speed of the drive motor 11 is increased, the moving speed of the nuclear fuel rod is returned to the original speed, and the nuclear fuel rod is transported to a predetermined position.

〔考案の効果〕[Effect of idea]

以上説明したように、本考案においては溶接チ
ヤンバーから引抜かれる核燃料棒の搬出系路の側
部に、レーザーによる核燃料棒の溶接ビード径測
定装置を配設したので、溶接チヤンバーから引き
出された核燃料棒の溶接ビード部の外径を、作業
者の手作業によることなく測定することができ、
しかもその測定を核燃料棒の移動中に行なうこと
ができて、その都度核燃料棒の移動を停止させる
必要がなく連続的に測定できて、溶接装置自体の
作動効率を向上させることができる。
As explained above, in the present invention, a laser-based weld bead diameter measuring device for nuclear fuel rods is installed on the side of the transport path for nuclear fuel rods pulled out from the welding chamber, so that the nuclear fuel rods pulled out from the welding chamber are The outer diameter of the weld bead can be measured without manual work by the operator.
Moreover, the measurement can be performed while the nuclear fuel rod is moving, and the measurement can be performed continuously without the need to stop the movement of the nuclear fuel rod each time, thereby improving the operating efficiency of the welding device itself.

しかも、核燃料棒に自転を加えながら溶接ビー
ド部の径を測定するので、周方向の如何なる点で
もその外径が保証され、計測精度を極めて高いも
のとすることができる。
Moreover, since the diameter of the weld bead portion is measured while rotating the nuclear fuel rod, the outer diameter is guaranteed at any point in the circumferential direction, making it possible to achieve extremely high measurement accuracy.

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

第1図は核燃料棒の縦断側面図、第2図は本考
案の核燃料棒自動溶接装置の概略構成図である。 1……被覆管、5……端栓、6……溶接チヤン
バー、10……支持輪、11……駆動モータ、1
2……駆動輪、13……核燃料棒端部検知センサ
ー、15……レーザー発信器、16……レーザー
受光器。
FIG. 1 is a longitudinal side view of a nuclear fuel rod, and FIG. 2 is a schematic diagram of an automatic nuclear fuel rod welding apparatus of the present invention. DESCRIPTION OF SYMBOLS 1... Cladding tube, 5... End plug, 6... Welding chamber, 10... Support wheel, 11... Drive motor, 1
2... Drive wheel, 13... Nuclear fuel rod end detection sensor, 15... Laser transmitter, 16... Laser receiver.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 溶接チヤンバーから引抜かれる核燃料棒の搬出
経路の側部に、核燃料棒端部検知センサーからの
信号によって作動せしめられレーザー光を発信す
るレーザー発信器と、核燃料棒の搬出経路をはさ
んで上記レーザー発信器と対向して配設され、上
記レーザー光を受光してその受光量によって溶接
ビードの最大直径を算出するためのレーザー受光
器と、上記溶接ビード径の測定中に上記核燃料棒
を軸線回りに回転させる回転駆動装置とを設けた
ことを特徴とする、核燃料棒自動溶接装置。
A laser transmitter that is activated by a signal from a nuclear fuel rod end detection sensor and emits a laser beam is placed on the side of the nuclear fuel rod removal path to be pulled out from the welding chamber, and a laser transmitter that emits a laser beam is placed across the nuclear fuel rod removal path. A laser receiver is disposed facing the laser beam, and is configured to receive the laser beam and calculate the maximum diameter of the weld bead based on the amount of received light. An automatic nuclear fuel rod welding device characterized by being provided with a rotation drive device for rotating.
JP1983142242U 1983-09-16 1983-09-16 Nuclear fuel rod automatic welding equipment Granted JPS6052075U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1983142242U JPS6052075U (en) 1983-09-16 1983-09-16 Nuclear fuel rod automatic welding equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1983142242U JPS6052075U (en) 1983-09-16 1983-09-16 Nuclear fuel rod automatic welding equipment

Publications (2)

Publication Number Publication Date
JPS6052075U JPS6052075U (en) 1985-04-12
JPS6321966Y2 true JPS6321966Y2 (en) 1988-06-16

Family

ID=30317892

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1983142242U Granted JPS6052075U (en) 1983-09-16 1983-09-16 Nuclear fuel rod automatic welding equipment

Country Status (1)

Country Link
JP (1) JPS6052075U (en)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55159103A (en) * 1979-05-31 1980-12-11 Fujitsu Ltd Outside diameter measuring device

Also Published As

Publication number Publication date
JPS6052075U (en) 1985-04-12

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