JPS6056296A - Manipulator for control rod - Google Patents

Manipulator for control rod

Info

Publication number
JPS6056296A
JPS6056296A JP58164849A JP16484983A JPS6056296A JP S6056296 A JPS6056296 A JP S6056296A JP 58164849 A JP58164849 A JP 58164849A JP 16484983 A JP16484983 A JP 16484983A JP S6056296 A JPS6056296 A JP S6056296A
Authority
JP
Japan
Prior art keywords
control rod
fuel
outer casing
support fitting
rod
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.)
Pending
Application number
JP58164849A
Other languages
Japanese (ja)
Inventor
良吉 五十嵐
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP58164849A priority Critical patent/JPS6056296A/en
Publication of JPS6056296A publication Critical patent/JPS6056296A/en
Pending 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

  • Load-Engaging Elements For Cranes (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は沸騰水型原子炉(以後BWRと称す)において
定期検査時等に制御棒案内管う制御棒取扱い装置に関+
乙。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a control rod handling device for controlling rod guide tubes during periodic inspections in a boiling water reactor (hereinafter referred to as BWR).
Otsu.

〔発明の技術的背景〕[Technical background of the invention]

第1図および第2図を参照して従来例を説明する。図中
符号1(d &<子炉圧力容器を示しこの原子炉圧力容
器1内には炉心2が収容されている。この炉心2は4体
で1組をなす複数の燃料集合体3および複数の制御棒4
とから構成されておシ、前記原子炉圧力容器1内に設置
されたシュラウド5、上部格子板6および炉心支持板7
からなる内部支持構造物8にょシ支持されている。すな
わち上記炉心支持板7には制御棒案内管9が設けられ、
この制初)棒案内管9内にオリフィスJOBを有する燃
料支持金μ、 107)K着脱自在に装着されており、
燃料集合体3にこの燃料支持金具10の開口部10kに
装着されている。一方!!ii制御棒4の下端部4Aは
原子炉圧力容器1の底部IAを貫通して挿入された制御
棒駆動機構(以後CRDと称す)llの係止装置1IA
K着脱自在に連結されている。
A conventional example will be explained with reference to FIGS. 1 and 2. In the figure, reference numeral 1 (d &< indicates a child reactor pressure vessel. A reactor core 2 is accommodated in this reactor pressure vessel 1. This reactor core 2 consists of a plurality of fuel assemblies 3 and a plurality of four fuel assemblies 3. control rod 4
A shroud 5, an upper grid plate 6, and a core support plate 7 installed in the reactor pressure vessel 1.
It is supported by an internal support structure 8 consisting of. That is, the core support plate 7 is provided with a control rod guide tube 9,
The fuel support μ, 107) K having an orifice JOB in the rod guide pipe 9 is removably installed,
The fuel assembly 3 is attached to the opening 10k of the fuel support fitting 10. on the other hand! ! ii. The lower end 4A of the control rod 4 is a locking device 1IA of the control rod drive mechanism (hereinafter referred to as CRD) inserted through the bottom IA of the reactor pressure vessel 1.
K are detachably connected.

このような構成において例えば定期検査時制御棒4の交
換は以下のようにして行なわれる。
In such a configuration, for example, the control rod 4 is replaced during periodic inspection as follows.

壕ず第2図囚に示すように燃料集合体3を取扱う前に制
御棒4を全挿入しておき未臨界性を維持する。次に第2
図(B)に示すように対角位置の1対の燃料集合体3を
取外し、その空間に制御棒案内装置12を挿入する。こ
の制御棒案内装置12は1対の模擬チャンネル12kを
連結部材12Bで一体化した構成をなしておシ、制御棒
4の縦方向案内機能を有している。そして第2図(C)
に示すように残シの1対の燃料集合体3を取9外す。こ
れは制御棒4を全引抜きしても未臨界性を維持すること
ができるようにする為である。次に第2図■)に示すよ
うに制御棒4を全引抜きして原子炉圧力容器lの底部7
Aの外fluから制御s4と制御棒駆動機構11との連
結を解除する。そして第2図(ト)に示すように制御棒
案内装置12を取外す。その後燃料支持金具10を引抜
きさらに制御棒4を上方に取外す。
As shown in Figure 2, the control rods 4 are fully inserted before handling the fuel assembly 3 to maintain subcriticality. Then the second
As shown in Figure (B), a pair of diagonally positioned fuel assemblies 3 are removed, and the control rod guide device 12 is inserted into the space. This control rod guide device 12 has a structure in which a pair of simulated channels 12k are integrated with a connecting member 12B, and has a function of guiding the control rod 4 in the longitudinal direction. And Figure 2 (C)
As shown in Figure 9, remove the remaining pair of fuel assemblies 3. This is so that subcriticality can be maintained even if the control rod 4 is completely withdrawn. Next, as shown in Figure 2 (■), the control rods 4 are completely withdrawn and the bottom 7 of the reactor pressure vessel 1 is removed.
The connection between the control s4 and the control rod drive mechanism 11 is released from the outside flu of A. Then, as shown in FIG. 2(G), the control rod guide device 12 is removed. Thereafter, the fuel support fitting 10 is pulled out and the control rod 4 is removed upward.

制御棒4を取外す前に燃料支持金具10を取外すのは、
燃料支持金具10を取付けた菫までは制御棒4を制御棒
駆動機構11の係止装置11kから離脱させることがで
きない構成になっているからである。
To remove the fuel support fitting 10 before removing the control rod 4,
This is because the control rod 4 cannot be disengaged from the locking device 11k of the control rod drive mechanism 11 until the point where the fuel support fitting 10 is attached.

〔背景技術の問題点〕[Problems with background technology]

このように制御棒4の交換を行なう為には、制御棒案内
装置12の取伺、取外作業、燃料支持金具10の取外、
取付作業等をj@次行なわなけれげならず、その為作業
に長時I′pHf要し、プラントの稼動率向上を図る上
で好ましいとはいえず、また作業員の彼曝量増大も懸念
されていた。
In order to replace the control rods 4 in this way, the control rod guide device 12 must be inspected and removed, the fuel support fitting 10 must be removed, and the control rod guide device 12 must be removed.
Installation work, etc. must be carried out next time, and therefore the work requires a long time of I'pHf, which is not desirable in terms of improving the plant's operating rate, and there is also concern that the amount of exposure to workers will increase. It had been.

〔発明の目的〕[Purpose of the invention]

本発明の目的とするところは、制御棒交換作業に要する
作業時間を短縮させ、プラントとしての稼動率向上を図
ると共に作業員の被G羞低減を図ることが可能な制01
棒取扱い装置を提供することにある。
The object of the present invention is to provide a control system capable of shortening the work time required for control rod replacement work, improving the operating rate of the plant, and reducing G-force exposure to workers.
Our goal is to provide rod handling equipment.

〔発明の概要〕[Summary of the invention]

すなわち本発明による制御棒取扱い装置は、燃料集合体
を引抜いた後の空1b」に挿入される外筐と、この外−
内に設けられ燃料支持金具をつかむ燃料支持金具つかみ
装置と、上記外筐内に設けられ制御棒をつかむ制御棒つ
かみ装置とを具備した構成である。
That is, the control rod handling device according to the present invention includes an outer casing that is inserted into the cavity 1b after the fuel assembly has been pulled out, and a
This configuration includes a fuel support fitting gripping device provided inside the outer casing for gripping the fuel support fitting, and a control rod gripping device installed inside the outer casing to grip the control rod.

したがって制御棒交換作業時一部燃料来合体を引抜いた
後外筐を挿入し外筐内に設けられた燃料支持金具つかみ
装置および制御棒つかみ装置により燃料支持金具および
制御棒をつかむ。
Therefore, during control rod replacement work, after a part of the fuel assembly is pulled out, the outer casing is inserted, and the fuel support fittings and control rods are grabbed by the fuel support fitting gripping device and the control rod gripping device provided inside the outer casing.

これによって外筐を引上げる際同時に燃料支持金具およ
び制御棒を引上げ取外すことができるので、制御棒交換
に要する作業時間を大巾に短縮することができ、それに
よってプラントの稼動率向上を図ると共に作業員の被曝
低減を図9、安全性を大巾に向上させることができる。
This allows the fuel support fittings and control rods to be pulled up and removed at the same time as the outer casing is pulled up, which greatly reduces the work time required to replace the control rods, thereby improving the plant's operating efficiency. It is possible to reduce the radiation exposure of workers (Figure 9) and greatly improve safety.

〔発明の実施例〕[Embodiments of the invention]

以下第3図ないし第5図を参照して本発明の一実施例を
説明する。なお従来例の説明に使用した第1図および第
2図七同一部分には同一符号を付して説明する。第3図
は本実施例による制御棒取扱い装置の斜視図であシ第4
図は縦断面図である。上記制御棒取扱い装置は外筐とし
ての制御棒案内装置21、燃料支持金具っがみ機構Eお
よび制御棒つかみ機構ヨとから構成されている。上記制
御棒案内装置とは燃料集合体3と同形等大をなす1対の
模擬チャンネル24.25をブラケット26にょシ対角
位置に一体化した構成をなしておシ、制御棒縦方向案内
機能を有している。上記模擬チャンネル24、zsの上
端面には円形孔24に、25kが形成されているととも
に下端部には下部タイプレート24B、25Bがそれぞ
れ取付けられている0また模擬チャンネル24.25の
上部には吊り金具27が取付けられている。
An embodiment of the present invention will be described below with reference to FIGS. 3 to 5. Note that the same parts in FIG. 1 and FIG. 2 used to explain the conventional example will be described with the same reference numerals. Figure 3 is a perspective view of the control rod handling device according to this embodiment.
The figure is a longitudinal sectional view. The control rod handling device is comprised of a control rod guide device 21 serving as an outer casing, a fuel support fitting holding mechanism E, and a control rod holding mechanism Y. The control rod guide device has a configuration in which a pair of simulated channels 24 and 25 having the same shape and size as the fuel assembly 3 are integrated at diagonal positions on the bracket 26, and has a control rod longitudinal guide function. have. A circular hole 24 is formed in the upper end surface of the simulated channel 24, zs, and a lower tie plate 24B, 25B is attached to the lower end thereof. A hanging fitting 27 is attached.

上記模擬チャンネル24.25内下部には第4図に示す
ように燃料支持金具10を取扱う燃料支持金具つかみ機
#!t22が内蔵さ!している。
In the lower part of the simulated channel 24, 25, there is a fuel support fitting gripping machine # for handling the fuel support fitting 10, as shown in FIG. Built-in t22! are doing.

この燃料支持金具つかみ機構22はレバー2B、爪片2
9およびエアーシリンダ3oとから構成されている。す
なわちレバー28はエアーシリンダ300ロツド3ノに
連結されたビン32に回転自在に支持されている。この
レバー28の下部は模擬チャンネル24.25の下部タ
イプレート24B、25Bから下方に突出し、その下端
には爪片29が取付けられておシ、この爪片29が燃料
支持金具1oのオリフィスJOBに内側から係合する構
成である。そして上記レバー28はその中間位置を支持
ビン32Aに回動自在に支持されている。またエアーシ
リンダ30には図示しない燃粒交換フロアから配設され
たホース31kが連結されている。すなわちレバー28
は通常時は2点鎖線で示すような状態にあシ、爪片29
け内側に閉じている。そしてホース31kを介してエア
ーシリンダ3oに圧力空気を供給しロッド31を突出さ
せることにより、図中実線で示すようにレバー28は支
持ビン32kを中心に回動して開き、爪片29がオリフ
ィスl0BIlC係合する構成である。
This fuel support fitting gripping mechanism 22 includes a lever 2B, a claw piece 2
9 and an air cylinder 3o. That is, the lever 28 is rotatably supported by a pin 32 connected to an air cylinder 300 and a rod 3. The lower part of this lever 28 protrudes downward from the lower tie plates 24B, 25B of the simulated channel 24.25, and a claw piece 29 is attached to its lower end, and this claw piece 29 is connected to the orifice JOB of the fuel support fitting 1o. It is configured to engage from the inside. The lever 28 is rotatably supported at its intermediate position by a support bin 32A. Further, a hose 31k disposed from a fuel exchange floor (not shown) is connected to the air cylinder 30. That is, the lever 28
Normally, the reeds and claw pieces 29 are in the state shown by the two-dot chain line.
It is closed inward. Then, by supplying pressurized air to the air cylinder 3o via the hose 31k and causing the rod 31 to protrude, the lever 28 rotates around the support bin 32k and opens as shown by the solid line in the figure, and the claw piece 29 opens the orifice. This is a configuration that engages 10BI1C.

そして模擬チャンネル24.25内中間部には制御棒つ
かみ機構23が内蔵されている。この制御棒つかみ機構
11は、上記模擬チャンイ、ル24内に設置されたエア
シリンダ33と、このエアシリンダ33から出入シする
ロッド34、このロッド34が貫通する模擬チャンネル
24゜25に形成されたロッド支持穴35.36、この
ロッド支持穴35,36を補強し中央部にロッド貫通孔
を有する補強板37.38とから構成されている。上記
エアシリンダ33には、前記燃料交換フロアから導かれ
たホース39を介して圧力空気が供給されそれによって
ロッドが作動し模擬チャンネル24.25内で全引抜さ
れた制御棒4のハンドル4Aの取扱穴4Bを貫通し1模
擬チヤンネル25のロッド支持穴36に挿入される構成
である。
A control rod gripping mechanism 23 is built in the intermediate portion of the simulated channels 24 and 25. This control rod gripping mechanism 11 includes an air cylinder 33 installed in the simulated channel 24, a rod 34 that enters and exits from the air cylinder 33, and a simulated channel 24-25 that the rod 34 passes through. It is composed of rod support holes 35 and 36, and reinforcing plates 37 and 38 that reinforce the rod support holes 35 and 36 and have a rod through hole in the center. The air cylinder 33 is supplied with pressurized air via a hose 39 led from the refueling floor, thereby actuating the rod and handling the handle 4A of the control rod 4 fully withdrawn within the simulated channel 24.25. It is configured to pass through the hole 4B and be inserted into the rod support hole 36 of the first simulated channel 25.

以上の構成をもとに制御棒交換作業について説明する。The control rod replacement work will be explained based on the above configuration.

まず未臨界性を維持する為に燃料集合体3を取扱う前に
制御棒4を全挿入しておく。
First, in order to maintain subcriticality, the control rods 4 are fully inserted before handling the fuel assembly 3.

次に対角位置にある1対の燃料集合体3を取外す。そし
て取外した後の窒間内に前述した制御棒取扱い装置を装
入する。々おその際には燃料支持金具つかみ機構ムユの
レバー28を第4図中一点鎖線で示すように内側に閉じ
ておき、かつエアシリンダ33の口、ド34を引抜いて
おく。次に残りの1対の燃料集合体3を取外す。
Next, a pair of fuel assemblies 3 located at diagonal positions are removed. After removal, the control rod handling device described above is inserted into the nitrogen chamber. In each case, the lever 28 of the fuel support gripping mechanism MUY is closed inward as shown by the dashed line in FIG. 4, and the opening and door 34 of the air cylinder 33 are pulled out. Next, the remaining pair of fuel assemblies 3 are removed.

これは制御棒4を全引抜きしても未臨界性を維持するこ
とができるようにする為である。そして制御棒4を全引
抜し、原子炉圧力茶器1の底部IAの外側から制御棒4
と制御棒駆動機構1ノとの連結を解除する。次に燃料支
持金具つかみ機構とのレバー28を拡げて爪片29を燃
料支持金具1θのオリフィスIOBに内側から保合させ
る。壕だ制御棒つかみ機構23のロッド34を伸し制御
棒4のハンドル4Aに係止させる。この状態で制御棒案
内装置2ノを引上げることによシ、燃料支持金具10お
よび制御棒4を同時に取外すことができる。
This is so that subcriticality can be maintained even if the control rod 4 is completely withdrawn. Then, completely pull out the control rod 4, and insert the control rod 4 from the outside of the bottom IA of the reactor pressure teapot 1.
and the control rod drive mechanism 1. Next, the lever 28 connected to the fuel support fitting gripping mechanism is expanded to engage the claw piece 29 with the orifice IOB of the fuel support fitting 1θ from the inside. The rod 34 of the control rod gripping mechanism 23 is extended and locked to the handle 4A of the control rod 4. By pulling up the control rod guide device 2 in this state, the fuel support fitting 10 and the control rod 4 can be removed at the same time.

すなわち制御棒案内装置2ノに燃料支持金具つかみ機構
22および制御棒つかみ機構23を内蔵した構成の制御
棒取扱い装置を使用することにより、制御棒案内装置2
1を引上げる際同時に燃料支持金具ノθおよび制御棒4
を引上なシそれによってプラントの稼III率向上はも
とよシ作業員の被曝低減を図ることができる。
That is, by using a control rod handling device having a built-in fuel support fitting gripping mechanism 22 and control rod gripping mechanism 23 in the control rod guiding device 2, the control rod guiding device 2
When pulling up the fuel support fitting θ and the control rod 4 at the same time
As a result, it is possible to not only improve the plant's operating rate but also reduce the radiation exposure of workers.

次に第5図を参照して別の実施例を説明する。Next, another embodiment will be described with reference to FIG.

す力わち前記実施例では外筺として制御棒4の縦方向の
案内機能を有する制御棒案内装置21を使用したのに対
し、この実施例は前記模疲チャンネル24.25を短少
とした角管41゜42をプレート43で連結したフレー
ム40f:外筐として使用している。上記プレート43
の中央には支持部材44が数句けられておシ、との支持
部材44に燃料交換器の抽助ポイスト(図示せず)から
のワイヤローノ45を直接連結して取扱う。上記フレー
ム4o内には前記実施例同様燃料支持金具つかみ装置2
2および制御棒つかみ装置23が設けられている。なお
図中46.47はホース3ノおよび39が貫通する棒4
を交換する場合には前記従来例のH;℃明で示したiI
I:J御梓系内装置12を取外したイ掟、上記制御棒取
扱い装置を挿入する。以後は前記実施例と同様であり、
フレーム40を引上げることによシ燃料支持金具10お
よび制御棒4を同時に引上けることができ前記実施例と
同イ求の効果金臭することができる。
In other words, in the above embodiment, the control rod guide device 21 having the function of guiding the control rods 4 in the vertical direction was used as the outer casing, whereas in this embodiment, the simulated fatigue channels 24 and 25 were shortened. A frame 40f in which the tubes 41 and 42 are connected by a plate 43 is used as an outer casing. Said plate 43
A support member 44 is provided in the center of the fuel exchanger, and a wire rotor 45 from an extraction point (not shown) of the fuel exchanger is directly connected to the support member 44 for handling. Inside the frame 4o is a fuel support fitting gripping device 2 similar to the previous embodiment.
2 and a control rod gripping device 23 are provided. In addition, 46.47 in the figure is the rod 4 through which the hoses 3 and 39 pass.
When replacing H;
I: After removing the J Azusa system internal device 12, insert the control rod handling device described above. The rest is the same as the above example,
By pulling up the frame 40, the fuel support fitting 10 and the control rod 4 can be pulled up at the same time, and the same effect as in the previous embodiment can be obtained.

〔発明の効果〕〔Effect of the invention〕

中 すなわち本発明による制御棒取扱装置は、燃料集合体を
引抜いた後の空間に挿入される外筐と、この外筺内に設
けられ郷料支持金具をつかむ燃料支持金具つかみ装置と
、上記外筐内に設けられ制御棒をつかむ制御棒つかみ装
置とを具備した構成である。
In other words, the control rod handling device according to the present invention includes an outer casing that is inserted into the space after the fuel assembly has been pulled out, a fuel support metal gripping device that is provided inside the outer casing and that grips the metal support metal fittings, and the above-mentioned outer casing. This configuration includes a control rod gripping device that is provided inside the casing and grips the control rod.

したがってfti!f ′@棒交換作業時一部燃料集合
体を引抜いた後外筐を挿入し外筐内に設けられた燃料支
持金具つかみ装置および制御棒つかみ装置によ)燃料支
持金具および制御棒をつかむ。
Therefore fti! f'@During rod replacement work, after partially pulling out the fuel assembly, insert the outer casing and grab the fuel support fittings and control rods using the fuel support fitting gripping device and control rod gripping device provided inside the outer casing.

これによって外筐を引上げる除同時に燃料支持金具およ
び制御棒を引上げ取外すことができるので、制御棒交換
に要する作業時間を大巾に短縮することができそれによ
ってノシントの稼動率向上を図ると共に作業員の被曝低
減を図シ、安全性を大巾に向上させることができる。
This allows the fuel support fittings and control rods to be lifted up and removed at the same time as the outer casing is pulled up, which greatly reduces the work time required to replace the control rods, thereby improving the operation rate of the nocinto and improving the work efficiency. It is possible to significantly improve safety by reducing radiation exposure for personnel.

は制御棒交換作条を示す図、第3図」9よび第4−色ノ
−・・・制御棒取扱装置(外筺L2,7・・・燃料支持
金具つかみ装置、23 制御棒つかみ装置。
Figure 3 shows the control rod replacement process, Figure 3 ``9'' and 4th color number... Control rod handling device (outer casing L2, 7... Fuel support fitting gripping device, 23 Control rod gripping device.

出顧人代理人 弁理士 鈴 江 武 該第1凶 第2vA (A) (B) コ2AClient agent Patent attorney Suzue Takeshi No. 1 2nd vA (A) (B) Ko2A

Claims (1)

【特許請求の範囲】[Claims] 燃料集合体を引抜いた後の空間に挿入される外筐と、こ
の外筐内に設けられ燃料支持金具をつかむ燃料支持金具
つかみ装置と、上記外筐内に設けられ制御棒をつかむ制
御棒つかみ装置とを具備したことを特徴とする制御棒取
扱い装置。
An outer casing inserted into the space after the fuel assembly is pulled out, a fuel support fitting gripping device provided in the outer casing to grip the fuel support fitting, and a control rod grip provided in the outer casing to grip the control rod. A control rod handling device characterized by comprising:
JP58164849A 1983-09-07 1983-09-07 Manipulator for control rod Pending JPS6056296A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58164849A JPS6056296A (en) 1983-09-07 1983-09-07 Manipulator for control rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58164849A JPS6056296A (en) 1983-09-07 1983-09-07 Manipulator for control rod

Publications (1)

Publication Number Publication Date
JPS6056296A true JPS6056296A (en) 1985-04-01

Family

ID=15801084

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58164849A Pending JPS6056296A (en) 1983-09-07 1983-09-07 Manipulator for control rod

Country Status (1)

Country Link
JP (1) JPS6056296A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0626699A1 (en) * 1993-05-21 1994-11-30 General Electric Company BWR control rod handling tooling and method
FR2724257A1 (en) * 1994-09-06 1996-03-08 Framatome Sa Handling equipment for removing absorber rod cluster from nuclear fuel assembly

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0626699A1 (en) * 1993-05-21 1994-11-30 General Electric Company BWR control rod handling tooling and method
US5473645A (en) * 1993-05-21 1995-12-05 General Electric Company Fuel support and control rod storage rack
FR2724257A1 (en) * 1994-09-06 1996-03-08 Framatome Sa Handling equipment for removing absorber rod cluster from nuclear fuel assembly

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