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JPH0750184B2 - Reactor control rod drive - Google Patents
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JPH0750184B2 - Reactor control rod drive - Google Patents

Reactor control rod drive

Info

Publication number
JPH0750184B2
JPH0750184B2 JP61272380A JP27238086A JPH0750184B2 JP H0750184 B2 JPH0750184 B2 JP H0750184B2 JP 61272380 A JP61272380 A JP 61272380A JP 27238086 A JP27238086 A JP 27238086A JP H0750184 B2 JPH0750184 B2 JP H0750184B2
Authority
JP
Japan
Prior art keywords
upper guide
control rod
guide pipe
guide tube
reactor
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
JP61272380A
Other languages
Japanese (ja)
Other versions
JPS63127193A (en
Inventor
豊 古満
春夫 佐藤
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP61272380A priority Critical patent/JPH0750184B2/en
Publication of JPS63127193A publication Critical patent/JPS63127193A/en
Publication of JPH0750184B2 publication Critical patent/JPH0750184B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は原子炉制御棒駆動装置に関するものである。The present invention relates to a reactor control rod drive system.

〔従来の技術〕[Conventional technology]

第2図および第3図には液体金属ナトリウム冷却形原子
炉用制御棒駆動装置の従来例が示されている。同図に示
されているように原子炉制御棒駆動装置1は、駆動部2
と上部案内管部3とに大別できる。
2 and 3 show a conventional example of a control rod driving device for a liquid metal sodium cooled reactor. As shown in the figure, the reactor control rod drive device 1 includes a drive unit 2
Can be roughly divided into the upper guide tube section 3.

上部案内管部3は、回転プラグ4の上面位置で支持さ
れ、原子炉内カバーガス5(アルゴン,ナトリウムペー
パー等)およびナトリウム6の雰囲気の原子炉容器内に
設置されており、その下端はグリツパー7を介して制御
棒8と接続している。制御棒8は、制御棒案内管9内に
収納されている。
The upper guide tube portion 3 is supported at the upper surface position of the rotary plug 4, is installed in the reactor vessel in the atmosphere of the reactor cover gas 5 (argon, sodium paper, etc.) and sodium 6, and the lower end thereof is a gripper. It is connected to the control rod 8 via 7. The control rod 8 is housed in a control rod guide tube 9.

駆動部2は、回転プラグ4上に位置する制御棒駆動機構
駆動部用案内筒(炉心上部機構)10内に収納されてお
り、その下端は上部案内管部3の最上部と接続してい
る。
The drive unit 2 is housed in a control rod drive mechanism drive unit guide cylinder (core upper mechanism) 10 located on the rotary plug 4, and the lower end thereof is connected to the uppermost portion of the upper guide pipe unit 3. .

駆動部2と上部案内管部3とは原子炉の定検時等におい
て、切り離して別々にメンテナンスすることができるよ
うになつている。また、制御棒8の上下動(引抜および
挿入)時における原子炉内カバーガス5のシールは、上
部案内管部3の上部案内管11の下端に取り付けられてい
るストロークベローズ(溶接ベローズ)12により行う。
ところで上部案内管部3の上部案内管11と案内管13と
は、これら両者を着脱自在に接続する接続手段、軸方向
(長手方向)に配置したボルト14で接続されている。こ
のため原子炉内カバーガス5がボルト14と遊び穴との隙
間から原子炉容器外へ漏れないように、上部案内管11と
案内管13との接続部にはOリング15等のシール部品が必
要であつた。また、このOリング15のシールの健全性を
定期的にチエツクするためのOリングシールチエツクガ
ス系16も必要であつた。
The drive unit 2 and the upper guide tube unit 3 can be separated and maintained separately during a regular inspection of the reactor. In addition, the seal of the reactor cover gas 5 when the control rod 8 moves up and down (withdrawal and insertion) is performed by the stroke bellows (welded bellows) 12 attached to the lower end of the upper guide tube 11 of the upper guide tube section 3. To do.
By the way, the upper guide tube 11 and the guide tube 13 of the upper guide tube part 3 are connected by a connecting means for detachably connecting them and a bolt 14 arranged in the axial direction (longitudinal direction). Therefore, in order to prevent the cover gas 5 inside the reactor from leaking out of the reactor vessel through the gap between the bolt 14 and the play hole, a sealing part such as an O-ring 15 is provided at the connecting portion between the upper guide pipe 11 and the guide pipe 13. It was necessary. Also, an O-ring seal check gas system 16 for periodically checking the soundness of the O-ring 15 is required.

〔発明が解決しようとする問題点〕[Problems to be solved by the invention]

上記従来技術は、下記のような問題があつた。 The above conventional technique has the following problems.

原子炉の運転中等に、上部案内管と案内管との接続部の
Oリングのシール性能が劣化して新品との交換が必要と
なつた時は、駆動部を取り外した後、上部案内管部全体
を原子炉容器内から取り出し、洗浄してナトリウム等を
除去して分解しなければならなかつた。しかしこの交換
作業は、現実的には非常にむずかしい作業であり、実質
的には不可能である。
If the O-ring sealing performance at the connection between the upper guide tube and the guide tube deteriorates and it is necessary to replace it with a new one during operation of the reactor, remove the drive section and then remove the upper guide tube section. The whole thing had to be taken out of the reactor vessel, washed to remove sodium etc. and decomposed. However, this replacement work is extremely difficult in reality, and is practically impossible.

本発明は以上の点に鑑みなされたものであり、メンテナ
ンス性の大幅向上を可能とした原子炉制御棒駆動装置を
提供することを目的とするものである。
The present invention has been made in view of the above points, and an object of the present invention is to provide a reactor control rod drive device capable of significantly improving maintainability.

〔問題点を解決するための手段〕[Means for solving problems]

上記目的は、接続手段を、上部案内管と案内管との軸方
向の接合面に直角方向に打込んだピンで形成することに
より、達成される。
The above object is achieved by forming the connecting means with a pin which is driven perpendicularly to the axial joint surface between the upper guide tube and the guide tube.

〔作用〕[Action]

上部案内管と案内管との軸方向の接合面に直角方向に打
込んだピンで接続手段を形成したので、従来のように上
部案内管と案内管とを接続する軸方向に配置するとボル
トが不要となり、上部案内管を軸方向に貫通する穴が不
要となる。従つて上部案内管と案内管との隙間を上昇す
る原子炉内カバーガスは、上部案内管の外周に設置して
あるOリングでシールされ、原子炉容器外へ漏れること
がないので、従来のように上部案内管と案内管との接続
部のOリング等のシール部品が不要となり、この接続部
のOリングの健全性を定期的にチエツクするためのOリ
ングシールチエツクガス系も不要となる。
Since the connecting means is formed by the pin driven in at a right angle to the axial joint surface between the upper guide pipe and the guide pipe, the bolts will not be formed if the upper guide pipe and the guide pipe are arranged in the axial direction as in the conventional case. It becomes unnecessary, and the hole which penetrates the upper guide tube in the axial direction is unnecessary. Therefore, the reactor cover gas that rises in the gap between the upper guide tubes is sealed by the O-ring installed on the outer circumference of the upper guide tubes and does not leak out of the reactor vessel. As described above, a sealing part such as an O-ring at the connecting portion between the upper guide pipe and the guide pipe becomes unnecessary, and an O-ring seal check gas system for regularly checking the soundness of the O-ring at this connecting portion is also unnecessary. .

〔実施例〕 以下、図示した実施例に基づいて本発明を説明する。第
1図には本発明の一実施例が示されている。なお従来例
と同じ部品には同じ符号を付したので説明を省略する。
本実施例では接続手段を、上部案内管11と案内管13との
軸方向の接合面に直角方向に打込んだピン17で形成し
た。このようにすることにより従来のように上部案内管
と案内管とを接続する軸方向に配置するボルトが不要と
なつて、上部案内管と案内管との接続部のOリング等の
シール部品が不要となり、メンテナンス性の大幅向上を
可能とした原子炉制御棒駆動装置を得ることができる。
[Examples] Hereinafter, the present invention will be described based on illustrated examples. FIG. 1 shows an embodiment of the present invention. The same parts as those of the conventional example are designated by the same reference numerals, and the description thereof will be omitted.
In this embodiment, the connecting means is formed by a pin 17 driven in a direction perpendicular to the axial joint surface between the upper guide tube 11 and the guide tube 13. This eliminates the need for the axially arranged bolts for connecting the upper guide tube and the guide tube as in the conventional case, and the sealing parts such as O-rings at the connecting portion between the upper guide tube and the guide tube are not required. A reactor control rod drive device that is unnecessary and can greatly improve maintainability can be obtained.

すなわち上部案内管11と案内管13とを、接続時の心出し
用印ろう部の位置に、かつ軸直角方向にピン17を打込ん
で接続した。この場合、ピン17用の穴は、上部案内管11
を貫通してない。このようにすることにより、上部案内
管11と案内管13との隙間を上昇する原子炉内カバーガス
は、上部案内管11および案内管13の外周部に原子炉内カ
バーガス、Oリングシールチエツクガス系16のガス,ス
トロークベローズ背圧系のガス等をシールするために設
置してあるOリングによつて原子炉容器外へ漏れるのが
防止される。従つて上述のようにそのメンテナンスが非
常にむずかしい上部案内管11と案内管13との接続部のO
リング等のシール部品が不要となり、原子炉制御棒駆動
装置のメンテナンス性を大幅に向上するとができる。ま
た、このように上部案内管11と案内管13との接続部のO
リング等のシール部品が不要となつたので、この接続部
のOリングのシールの健全性を定期的にチエツクするO
リングシールチエツクガス系も不要となり、原子炉制御
棒駆動装置用のガス系統が簡素化できる。
That is, the upper guide tube 11 and the guide tube 13 were connected to each other at the position of the centering stud portion at the time of connection and by driving the pin 17 in the direction perpendicular to the axis. In this case, the hole for the pin 17 is
Does not penetrate By doing so, the reactor cover gas that rises in the gap between the upper guide pipe 11 and the guide pipe 13 is prevented from flowing into the outer periphery of the upper guide pipe 11 and the guide pipe 13 and the O-ring seal check gas. O-rings installed to seal the gas of the gas system 16, the gas of the stroke bellows back pressure system, etc. are prevented from leaking out of the reactor vessel. Therefore, as described above, the O of the connection between the upper guide pipe 11 and the guide pipe 13 is very difficult to maintain.
Sealing parts such as rings are not required, and the maintainability of the reactor control rod drive device can be greatly improved. In addition, the O of the connecting portion between the upper guide pipe 11 and the guide pipe 13 is
Since no seal parts such as rings are needed, the soundness of the O-ring seal at this connection is checked regularly.
The ring seal check gas system is also unnecessary, and the gas system for the reactor control rod drive can be simplified.

〔発明の効果〕〔The invention's effect〕

上述のように本発明は原子炉制御棒駆動装置のメンテナ
ンス性が大幅に向上するようになつて、メンテナンス性
の大幅向上を可能とした原子炉制御棒駆動装置を得るこ
とができる。
As described above, according to the present invention, the maintainability of the reactor control rod drive device is greatly improved, and the reactor control rod drive device capable of greatly improving the maintainability can be obtained.

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

第1図は本発明の原子炉制御棒駆動装置の一実施例の上
部案内管と案内管との接続部周りの縦断側面図、第2図
は従来の原子炉制御棒駆動装置の縦断側面図、第3図は
同じく従来の上部案内管と案内管との接続部周りの縦断
側面図である。 2……駆動部、3……上部案内管部、11……上部案内
管、13……案内管、17……ピン。
FIG. 1 is a vertical sectional side view around an upper guide pipe and a connecting portion between the guide pipes of an embodiment of a reactor control rod driving device of the present invention, and FIG. 2 is a vertical side view of a conventional reactor control rod driving device. FIG. 3 is a vertical sectional side view around the connection between the conventional upper guide tube and the guide tube. 2 ... Drive part, 3 ... Upper guide tube part, 11 ... Upper guide tube, 13 ... Guide tube, 17 ... Pin.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】駆動部と、この駆動部と着脱自在に接続さ
れ、かつ原子炉容器内に位置する上部案内管部とを備
え、前記上部案内管部は上部案内管と案内管とを有し、
これら上部案内管と案内管とはこれら両者を着脱自在に
接続する接続手段をもつて接続されている原子炉制御棒
駆動装置において、前記接続手段を、前記上部案内管と
案内管との軸方向の接合面に直角方向に打込んだピンで
形成したことを特徴とする原子炉制御棒駆動装置。
1. A drive part, and an upper guide pipe part which is detachably connected to the drive part and which is located inside the reactor vessel. The upper guide pipe part has an upper guide pipe and a guide pipe. Then
In the reactor control rod drive device, wherein the upper guide pipe and the guide pipe are connected with a connecting means for detachably connecting them, in the reactor control rod drive device, the connecting means is arranged in the axial direction of the upper guide pipe and the guide pipe. Reactor control rod drive device, characterized in that it is formed with pins that are driven in the direction perpendicular to the joint surface of.
JP61272380A 1986-11-15 1986-11-15 Reactor control rod drive Expired - Lifetime JPH0750184B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61272380A JPH0750184B2 (en) 1986-11-15 1986-11-15 Reactor control rod drive

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61272380A JPH0750184B2 (en) 1986-11-15 1986-11-15 Reactor control rod drive

Publications (2)

Publication Number Publication Date
JPS63127193A JPS63127193A (en) 1988-05-31
JPH0750184B2 true JPH0750184B2 (en) 1995-05-31

Family

ID=17513077

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61272380A Expired - Lifetime JPH0750184B2 (en) 1986-11-15 1986-11-15 Reactor control rod drive

Country Status (1)

Country Link
JP (1) JPH0750184B2 (en)

Also Published As

Publication number Publication date
JPS63127193A (en) 1988-05-31

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