JPH01227915A - Inspecting device for nuclear fuel rod end plug weld zone - Google Patents
Inspecting device for nuclear fuel rod end plug weld zoneInfo
- Publication number
- JPH01227915A JPH01227915A JP63054048A JP5404888A JPH01227915A JP H01227915 A JPH01227915 A JP H01227915A JP 63054048 A JP63054048 A JP 63054048A JP 5404888 A JP5404888 A JP 5404888A JP H01227915 A JPH01227915 A JP H01227915A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel rod
- end plug
- axis
- weld zone
- 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
Links
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 52
- 238000007689 inspection Methods 0.000 claims abstract description 26
- 238000006073 displacement reaction Methods 0.000 abstract description 6
- 238000001514 detection method Methods 0.000 abstract description 5
- 230000008961 swelling Effects 0.000 abstract description 5
- 238000005253 cladding Methods 0.000 description 10
- 238000003466 welding Methods 0.000 description 6
- 230000002093 peripheral effect Effects 0.000 description 3
- 238000005452 bending Methods 0.000 description 2
- 229910001315 Tool steel Inorganic materials 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- Length Measuring Devices With Unspecified Measuring Means (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
「産業上の利用分野」
この発明は、核燃料棒端栓溶接部の外径およびエンベロ
ープ（端栓圧入の曲がり等）を測定検査する核燃料棒端
栓溶接部の検査装置に関するものである。Detailed Description of the Invention "Industrial Application Field" This invention is an inspection device for a nuclear fuel rod end plug weld, which measures and inspects the outer diameter and envelope (curvature of the end plug press-fit, etc.) of a nuclear fuel rod end plug weld. It is related to.
「従来の技術」
加圧水型軽水炉等の原子炉に装荷される核燃料集合体を
構成する核燃料棒は、例えば第３図に示すように、円筒
状の被覆管Ｉ内に、複数個の燃料ベレット２と、この燃
料ベレット２の移動、損傷を防止するためのスプリング
３とを挿入し、被覆管ｌの両端部に端栓４．４を圧入し
、これら端栓４．４と被覆管！との合わせ目を周溶接す
ることにより製造されている。"Prior Art" Nuclear fuel rods constituting a nuclear fuel assembly loaded into a nuclear reactor such as a pressurized water reactor are, for example, as shown in FIG. and a spring 3 to prevent the fuel pellet 2 from moving or being damaged, and press-fit the end plugs 4.4 into both ends of the cladding tube l. It is manufactured by circumferentially welding the joints.
上記のようにして製造された核燃料棒ｉこおいては、種
々の仕様が厳しく規定されているが、被覆管ｌと端栓４
．４との溶接部の盛り上がり量および端栓４，４が被覆
管１に曲がって挿入されていないかどうかについても厳
しく規定されている。Although various specifications are strictly prescribed for the nuclear fuel rod i manufactured as described above, the cladding tube l and the end plug 4 are
．． There are also strict regulations regarding the amount of swell of the welded portion with 4 and whether or not the end plugs 4, 4 are inserted into the cladding tube 1 in a crooked manner.
従来、上記溶接部の盛り上がり量の検査や、端栓４，４
が被覆管１に曲がって挿入されていないかどうかの検査
（エンベロープ検査）については、リングゲージにより
、作業者が手作業で行っそいた。Conventionally, inspection of the amount of swelling of the welded part, and inspection of the end plugs 4, 4
The inspection (envelope inspection) to see if the envelope was inserted into the cladding tube 1 in a bent manner was carried out manually by an operator using a ring gauge.
［発明が解決しようとする課題−１
ところが、上記リングゲーノを用いる検査では、手作業
に頼らざるを（すず、自動化が困難であると同時に、定
ｍ的評価ができないという欠点があったため、このよう
な欠点を解決すべく検査の自動化が望まれていた。[Problem to be solved by the invention - 1 However, the above-mentioned inspection using the Ringgeno has to rely on manual labor (because it is difficult to automate and at the same time cannot perform constant evaluation, Automation of inspection has been desired to solve these shortcomings.
「発明の目的」
この発明は上記事情に鑑みてなされたものであり、被覆
管と端栓との溶接部の盛り上がり量の検査やエンベロー
プ検査を正確かつ自動的に行うことができる核燃料棒端
栓溶接部の検査装置を提供することを目的としている。``Purpose of the Invention'' This invention was made in view of the above circumstances, and provides a nuclear fuel rod end plug that can accurately and automatically inspect the amount of swelling of the weld between the cladding tube and the end plug and the envelope inspection. The purpose is to provide an inspection device for welded parts.
［課題を解決するための手段」
この発明の核燃料棒端栓溶接部の検査装置は、軸回りに
回転自在に設けられた略円筒状をなす回転体と、この回
転体の内部に同回転体と軸線を同一にかつ軸線方向に移
動自在に設けられた円柱状をなす基準プラグと、上記回
転体のその周方向に等間隔で離間した少なくとも３箇所
に上記回転体の軸線と直交する方向に移動自在に支持さ
れて、上記基準プラグと軸線を同一にして保持された核
燃料棒の端栓溶接部に当接４゛る当接部とを具備してな
るものである。[Means for Solving the Problems] The nuclear fuel rod end plug welding part inspection device of the present invention includes a rotating body in a substantially cylindrical shape that is rotatable around an axis, and a rotary body inside the rotating body. a cylindrical reference plug that is movable in the axial direction and has the same axis as the rotating body; The plug is movably supported and is provided with an abutting part that abuts a welded end plug of a nuclear fuel rod that is held in the same axis as the reference plug.
「作用 １
この発明の核燃料棒端栓溶接部の検査装置にあっては、
回転体に核燃料棒の軸線と直交する方向に移動自在に設
けられた当接部を、回転体を回転さ仕ることにより、核
燃料棒の端栓溶接部に摺接さ仕、この時に生じる当接部
の核燃料棒の軸線と直交する方向への移動量（変位量）
により、端栓溶接部の検査を自動的に行う。"Function 1" In the nuclear fuel rod end plug welding part inspection device of the present invention,
By rotating the rotating body, a contact part provided on the rotating body so as to be movable in a direction perpendicular to the axis of the nuclear fuel rod is brought into sliding contact with the welded end plug of the nuclear fuel rod, and the contact generated at this time is removed. Amount of movement (displacement) in the direction perpendicular to the axis of the nuclear fuel rod at the contact part
automatically inspects end plug welds.
「実施例Ｊ
以下この発明の核燃料棒端栓溶接部の検査装置の一実施
例を第１図および第２図を参照して説明する。Embodiment J An embodiment of the nuclear fuel rod end plug weld inspection device of the present invention will be described below with reference to FIGS. 1 and 2.
これらの図において符号１０は回転体を示ケ。In these figures, the reference numeral 10 indicates a rotating body.
この回転体１０は略円筒状のものであり、その外周部は
ラジアルベアリング１１に支持されている。This rotating body 10 has a substantially cylindrical shape, and its outer peripheral portion is supported by a radial bearing 11.
そして、この回転体１０はその左端部に取り付けられた
プーリ１２を図示しないベルト、駆動源により回転させ
ることにより、軸回りに回転自在に設けられている。The rotating body 10 is rotatably provided around an axis by rotating a pulley 12 attached to the left end thereof by a belt and a drive source (not shown).
上記回転体１０の内部には核燃料棒Ａより若干大径の略
円柱状をなす基準プラグ１３がその軸線を回転体１０の
軸線と同一にして設けられている。Inside the rotating body 10, a reference plug 13 having a substantially cylindrical shape and having a diameter slightly larger than that of the nuclear fuel rod A is provided with its axis aligned with the axis of the rotating body 10.
この基準プラグ１３はその先端部が回転体１ｏの内部先
端側に設けられたストロークベアリング１４により軸線
方向に移動自在にかつ回転体１０に対して相対的に回転
自在に支持されており、後端部が回転体１０の内部後端
側に設けられたコンバインドベアリング１５のラジアル
ベアリング部１５ａに軸線方向に摺動自在に挿入支持さ
れている。The reference plug 13 has its tip supported by a stroke bearing 14 provided on the inner tip side of the rotating body 1o so as to be movable in the axial direction and rotatable relative to the rotating body 10, and its rear end The radial bearing portion 15a of the combined bearing 15 provided on the inner rear end side of the rotating body 10 is inserted and supported so as to be slidable in the axial direction.
また、この基準プラグ１３の中途部にはフランジ部＋３
ａが形成されており、このフランジ部１３ａと上記コン
バインドベアリング１５のスラストベアリング部１５ｂ
との間には、基準プラグ１３を第１図中右方に付勢する
コイルスプリング１７が設けられている。In addition, a flange portion +3 is provided in the middle of this reference plug 13.
a is formed, and this flange portion 13a and the thrust bearing portion 15b of the combined bearing 15
A coil spring 17 that urges the reference plug 13 to the right in FIG. 1 is provided between the two.
また、上記回転体の先端部（第１図中右端部）には大径
部２０が軸線を同一にして形成されている。Further, a large-diameter portion 20 is formed at the tip portion (right end portion in FIG. 1) of the rotating body with the same axis.
この大径部２０の周壁部にはストロークベアリング２１
が周方向に等間隔で４個組み込まれており、δストロー
クベアリング２１を回転体１ｏの軸線方向おいて挾む位
置にはそれぞれストロークベアリング２２．２２が組み
込まれている。A stroke bearing 21 is provided on the peripheral wall of this large diameter portion 20.
Four stroke bearings 22 and 22 are installed at positions sandwiching the δ stroke bearing 21 in the axial direction of the rotating body 1o.
さらに、上記大径部２０の内側には核燃料棒Ａの端栓溶
接部に当接する当接部２３が周方向に等間隔で離間して
４個配置されている。この当接部２３は断面コ字状の支
持部２４と、この支持部２４の突部２４ａ、２４ａ間に
渡されて支持された支持軸２４ｂに回転自在に支持され
て、核燃料棒Ａの端栓溶接部に転勤摺接するローラ２５
と、支持部２４の外側面に立設されて上記ストロークベ
アリング２＋、２２．２２に上記回転体１ｏの軸線と直
交する方向に移動自在に支持されたガイドロッド２６，
２７．２７と、且つ上記大径部２ｏの内周面と支持部２
４の間に設けられて、支持部２４を核燃料棒Ａ側に向け
て付勢するコイルスプリング２８とから構成されている
。さらに、上記ガイドロッド２６にはこの移動量（変位
量）を検知するための検知部（図示せず）が連結されて
いる。Further, inside the large diameter portion 20, four contact portions 23 that contact the end plug welded portions of the nuclear fuel rods A are arranged at equal intervals in the circumferential direction. This abutment part 23 is rotatably supported by a support part 24 having a U-shaped cross section and a support shaft 24b supported between protrusions 24a, 24a of this support part 24, and is supported at the end of the nuclear fuel rod A. Roller 25 that slides into contact with the plug welding part
and a guide rod 26 erected on the outer surface of the support portion 24 and supported by the stroke bearings 2+, 22.22 so as to be movable in a direction orthogonal to the axis of the rotating body 1o.
27.27, and the inner peripheral surface of the large diameter portion 2o and the support portion 2
4, and a coil spring 28 that biases the support portion 24 toward the nuclear fuel rod A side. Further, a detection section (not shown) is connected to the guide rod 26 to detect the amount of movement (displacement).
また、上記回転体ＩＯの第１図中右方には、基準Ｖブロ
ック３０が設けられており、この基準Ｖブロック３０の
上方には、これにより上記基準プラグ１３と軸線を同一
にして支持された核燃料棒Ａを基準Ｖブロック３０に押
圧固定するための固定■ブロック３１が上下方向に移動
自在に設けられている。Further, a reference V block 30 is provided on the right side of the rotating body IO in FIG. A fixed block 31 for pressing and fixing the nuclear fuel rod A to the reference V block 30 is provided so as to be movable in the vertical direction.
なお、上記基準プラグ１３およびローラ２５の材質とし
ては、高硬度でかつ耐摩耗性の優れた超硬合金、工具鋼
、ステンレス焼き入れ鋼等が用いられている。The reference plug 13 and the roller 25 are made of cemented carbide, tool steel, hardened stainless steel, etc., which have high hardness and excellent wear resistance.
次に、上記構成の核燃料棒端栓溶接部の検査装置を用い
て、端栓溶接部の検査を行う方法を説明する。Next, a method for inspecting end plug welds of nuclear fuel rods using the apparatus for inspecting nuclear fuel rod end plug welds having the above configuration will be described.
まず、回転体ＩＯ内に設けられた基準プラグ１３をコイ
ルスプリング１７の付勢力により大径部２０の内側に突
出させて当接部２３・・・のローラ２５・・・の間に挿
入すると共に、ローラ２５・・・をコイルスプリング２
８・・・の付勢力により基準プラグ１３に当接して、ガ
イドロッド２６に連結された検知部（図示せず）のキヤ
リプレーシタンを行う。First, the reference plug 13 provided in the rotary body IO is made to protrude inside the large diameter part 20 by the biasing force of the coil spring 17, and is inserted between the rollers 25 of the contact parts 23... , roller 25... to coil spring 2
8... comes into contact with the reference plug 13 to cause a calibration of a sensing portion (not shown) connected to the guide rod 26.
次に、検査する核燃料棒Ａを基準Ｖブロック３０に載置
することにより、核燃料棒Ａの軸線と基準プラグＩ３の
軸線を一致さけた後、核燃料棒Ａを第１図中左方に移動
させて、ローラ２５・・・間に位置していた基準プラグ
１３をコイルスプリング１７の付勢力に逆らって回転体
１０内に押し込むと共に、核燃料棒Ａの先端部すなわち
端栓溶接部をローラ２５・・・間に位置させ、固定Ｖブ
ロック３１により核燃料棒Ａを基準Ｖブロック３０に押
圧固定する。この時、当接部２３・・・のローラ２５・
・・がコイルスプリング２８・・・の付勢力により核燃
料棒Ａの端栓溶接部に当接する。Next, the nuclear fuel rod A to be inspected is placed on the reference V block 30 so that the axis of the nuclear fuel rod A and the axis of the reference plug I3 are aligned, and then the nuclear fuel rod A is moved to the left in FIG. Then, the reference plug 13, which was located between the rollers 25, is pushed into the rotating body 10 against the biasing force of the coil spring 17, and the tip of the nuclear fuel rod A, that is, the end plug welded part, is pushed into the roller 25,...・Nuclear fuel rod A is pressed and fixed to the reference V block 30 by the fixed V block 31 located in between. At this time, the roller 25 of the contact portion 23...
... comes into contact with the end plug welded portion of the nuclear fuel rod A due to the biasing force of the coil spring 28.
その後、回転体ｌＯを軸線回りに９０°回転させる。す
ると、回転体ｌＯの回転に伴って当接部２３が核燃料棒
Ａの軸線回りに回転し、これによりローラ２５・・・が
核燃料棒Ａの端栓溶接部上を周方向に転勤する。この時
、ローラ２５・・・は端栓溶接部の若干の凹凸により核
燃料棒Ａの軸線と直交する方向に移動せしめられ、この
移動量（変位量）が支持部２４、ガイドロッド２６を介
して検知部に伝達される。そして、この検知部に伝達さ
れた変位量により核燃料棒Ａの端栓溶接部の盛り上がり
量および端栓が被覆管に曲がって挿入されていないかど
うかの検査（エンベロープ検査）を定量的に行う。なお
、このように回転体ｌＯを回転させる際においては、基
準プラグ１３と核燃料棒Ａはコイルスプリング１７の付
勢力により当接しているのので、基準プラグ１３が回転
体１０の回転に伴って回転することがなく、さらにコイ
ルスプリング１７が回転体１０の回転に伴ってねじれる
ことがない。Thereafter, the rotating body IO is rotated 90 degrees around the axis. Then, the contact portion 23 rotates around the axis of the nuclear fuel rod A as the rotating body 1O rotates, and thereby the rollers 25 move over the end plug welded portion of the nuclear fuel rod A in the circumferential direction. At this time, the rollers 25... are moved in a direction perpendicular to the axis of the nuclear fuel rod A due to the slight irregularities of the end plug welding part, and this movement amount (displacement amount) is transferred via the support part 24 and the guide rod 26. The signal is transmitted to the detection unit. Then, based on the amount of displacement transmitted to the detection unit, an inspection (envelope inspection) is quantitatively performed to determine the amount of swelling of the end plug welded portion of the nuclear fuel rod A and whether the end plug is inserted into the cladding tube with a bend. Note that when rotating the rotating body lO in this way, the reference plug 13 and the nuclear fuel rod A are in contact with each other due to the biasing force of the coil spring 17, so the reference plug 13 rotates with the rotation of the rotating body 10. Furthermore, the coil spring 17 will not be twisted as the rotating body 10 rotates.
しかして、上記核燃料棒端栓溶接部の検査装置によれば
、回転自在に設けられた回転体ＩＯの大径部２０に核燃
料棒Ａの軸線と直交する方向に移動自在に設けられた当
接部２３のローラ２５を、回転体ｌＯを回転させること
により、核燃料棒Ａの端栓溶接部に転勤摺接させ、この
時に生じる当接部２３の核燃料棒Ａの軸線と直交する方
向への移動量（変位ＩＩ）により、端栓溶接部の検査を
自動的に行うようにしたので、従来のリングゲージを用
いた手作業による検査に比べ、格段に正確に行うことが
できると共に、作業者の検査ミス等を生じることもなく
、さらには端栓溶接部の検査を定量的に行うこともでき
、これにより端栓溶接部の盛り上がり飛や端栓の被覆管
に対する曲がり量のバラツキ等を知ることもでき、加え
て、被覆管と端栓との同軸度に検査に適用することもで
きる。According to the nuclear fuel rod end plug weld inspection apparatus described above, an abutment movably provided on the large diameter portion 20 of the rotary body IO, which is provided so as to be rotatable, in a direction perpendicular to the axis of the nuclear fuel rod A. The roller 25 of the part 23 is brought into sliding sliding contact with the end plug welded part of the nuclear fuel rod A by rotating the rotating body IO, and the movement of the contact part 23 in the direction perpendicular to the axis of the nuclear fuel rod A that occurs at this time. Since the inspection of the end plug weld is automatically performed based on the amount (displacement II), it is much more accurate than manual inspection using a conventional ring gauge, and it also saves the operator's time. There is no inspection error, and it is also possible to quantitatively inspect the welded part of the end plug, which makes it possible to check for bulges in the welded part of the end plug and variations in the amount of bending of the end plug with respect to the cladding pipe. In addition, it can also be applied to inspect the coaxiality of the cladding tube and the end plug.
なお、上記実施例では回転体ＩＯの大径部２０に当接部
２３を周方向に等間隔で離間して４個設けたが、この発
明では少なくとも３個以上設ければよく、４個に限定さ
れるものではない。In the above embodiment, four contact parts 23 are provided at equal intervals in the circumferential direction on the large diameter part 20 of the rotating body IO, but in the present invention, at least three or more contact parts 23 may be provided. It is not limited.
「発明の効果」
以上説明したように、この発明の核燃料棒端栓溶接部の
検査装置によれば、軸回りに回転自在の回転体に核燃料
棒の軸線と直交する方向に移動自在に設けられた当接部
を、回転体を回転させることにより、核燃料棒の端栓溶
接部に摺接させ、この時に生じる当接部の核燃料棒の軸
線と直交する方向への移動量（変［ぴ量）により、端枠
溶接部の検査を自動的に行うようにしたので、従来のり
ングゲーノを用いた手作業による検査に比べ、格段に正
確に行うことができろと共に、作業各の検査ミス等を生
じることもなく、さらには端栓溶接部の検査を定型的に
行うこともてき、これにより端栓溶接部の盛り上がり量
や端栓の被覆管に対する曲がり量のバラツキ等を知るこ
とらでき、加えて、被覆管と端栓との同軸度に検査にも
適用゛４′ることかできる。"Effects of the Invention" As explained above, according to the nuclear fuel rod end plug welding inspection device of the present invention, the inspection device is provided with a rotating body that is rotatable about its axis and is movable in a direction orthogonal to the axis of the nuclear fuel rod. By rotating the rotating body, the abutting part is brought into sliding contact with the end plug welded part of the nuclear fuel rod, and the amount of movement of the abutting part in the direction perpendicular to the axis of the nuclear fuel rod that occurs at this time is measured. ), the end frame welds are automatically inspected, making it much more accurate than the conventional manual inspection using a Ringgeno, and reducing inspection errors during each operation. In addition, inspections of end plug welds can be carried out on a regular basis, which makes it possible to determine the amount of swelling of the end plug weld and variations in the amount of bending of the end plug with respect to the cladding. Therefore, it can also be applied to inspecting the coaxiality of the cladding tube and the end plug.
第１図および第２図はこの発明の核燃料棒端栓溶接部の
検査装置の一実施例を示すしのであり、第１図は装置の
概略構成断面図、第２図は第１図おける■−■線視図、
第３図は核燃料棒の断面図である。
！０・・・・・・回転体、１３・・・・・・基準プラグ
、２３・・・・・・当接部、Ａ・・・・・核燃料棒。1 and 2 show an embodiment of the nuclear fuel rod end plug weld inspection device of the present invention. FIG. 1 is a schematic cross-sectional view of the device, and FIG. − ■ Linear view,
FIG. 3 is a cross-sectional view of a nuclear fuel rod. ! 0... Rotating body, 13... Reference plug, 23... Contact portion, A... Nuclear fuel rod.
Claims (1)
、この回転体の内部に同回転体と軸線を同一にかつ軸線
方向に移動自在に設けられた円柱状をなす基準プラグと
、上記回転体のその周方向に等間隔で離間した少なくと
も３箇所に上記回転体の軸線と直交する方向に移動自在
に支持されて、上記基準プラグと軸線を同一にして保持
された核燃料棒の端栓溶接部に当接する当接部とを具備
してなることを特徴とする核燃料棒端栓溶接部の検査装
置。a substantially cylindrical rotating body that is rotatable around an axis; a cylindrical reference plug that is disposed inside the rotating body and has the same axis as the rotating body and is movable in the axial direction; An end of a nuclear fuel rod supported movably in a direction orthogonal to the axis of the rotor at at least three equally spaced locations in the circumferential direction of the rotor, and held with the same axis as the reference plug. 1. An inspection device for a nuclear fuel rod end plug weld, comprising: a contact portion that comes into contact with a plug weld.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63054048A JPH0660816B2 (en) | 1988-03-08 | 1988-03-08 | Nuclear fuel rod end plug weld inspection device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63054048A JPH0660816B2 (en) | 1988-03-08 | 1988-03-08 | Nuclear fuel rod end plug weld inspection device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01227915A true JPH01227915A (en) | 1989-09-12 |
| JPH0660816B2 JPH0660816B2 (en) | 1994-08-10 |
Family
ID=12959722
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63054048A Expired - Lifetime JPH0660816B2 (en) | 1988-03-08 | 1988-03-08 | Nuclear fuel rod end plug weld inspection device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0660816B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8885789B2 (en) | 2008-09-15 | 2014-11-11 | Areva Nc | Device for measuring and correcting a parallelism error in a nuclear fuel rod |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5999307A (en) * | 1982-11-30 | 1984-06-08 | Mitsubishi Electric Corp | Apparatus for detecting configuration of end of steel pipe |
-
1988
- 1988-03-08 JP JP63054048A patent/JPH0660816B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5999307A (en) * | 1982-11-30 | 1984-06-08 | Mitsubishi Electric Corp | Apparatus for detecting configuration of end of steel pipe |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8885789B2 (en) | 2008-09-15 | 2014-11-11 | Areva Nc | Device for measuring and correcting a parallelism error in a nuclear fuel rod |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0660816B2 (en) | 1994-08-10 |
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