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JPS6411160B2 - - Google Patents
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JPS6411160B2 - - Google Patents

Info

Publication number
JPS6411160B2
JPS6411160B2 JP57084181A JP8418182A JPS6411160B2 JP S6411160 B2 JPS6411160 B2 JP S6411160B2 JP 57084181 A JP57084181 A JP 57084181A JP 8418182 A JP8418182 A JP 8418182A JP S6411160 B2 JPS6411160 B2 JP S6411160B2
Authority
JP
Japan
Prior art keywords
pressure vessel
connection port
plug
reactor
operating 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.)
Expired
Application number
JP57084181A
Other languages
Japanese (ja)
Other versions
JPS58200195A (en
Inventor
Yasukata Tamai
Yoshio Yada
Katsushi Takano
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 JP57084181A priority Critical patent/JPS58200195A/en
Publication of JPS58200195A publication Critical patent/JPS58200195A/en
Publication of JPS6411160B2 publication Critical patent/JPS6411160B2/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Pressure Vessels And Lids Thereof (AREA)

Description

【発明の詳細な説明】 本発明は、原子炉圧力容器の炉水漏洩遮断装
置、さらに詳細には、沸騰水型原子炉圧力容器の
ドレン配管取替工事に際して使用される炉水漏洩
遮断装置に関するものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor water leakage cutoff device for a nuclear reactor pressure vessel, and more particularly, to a reactor water leakage cutoff device used during drain piping replacement work for a boiling water reactor pressure vessel. It is something.

本発明の説明に先立ち、沸騰水型原子炉圧力容
器の内部構造を第1図にもとづいて説明する。第
1図において、符号1は原子炉圧力容器全体を総
括的に示しており、圧力容器1を大別すると、容
器胴部2、下鏡3、さらには上蓋(図示せず)か
ら構成されている。圧力容器1内には、蒸気乾燥
器4、気水分離器5、シユラウド上蓋6、上部格
子板7、燃料棒8、燃料棒サポート(図示せず)、
炉心サポート9、さらには制御棒案内管10など
の炉内構造物が組み込まれている。また、下鏡3
には、制御棒駆動機構ハウジング11および原子
炉圧力容器ドレン配管12が溶接々続されてい
る。
Prior to explaining the present invention, the internal structure of a boiling water reactor pressure vessel will be explained based on FIG. In FIG. 1, reference numeral 1 generally indicates the entire reactor pressure vessel, and the pressure vessel 1 is roughly divided into a vessel body 2, a lower mirror 3, and an upper cover (not shown). There is. Inside the pressure vessel 1, there are a steam dryer 4, a steam separator 5, a shroud upper cover 6, an upper grid plate 7, a fuel rod 8, a fuel rod support (not shown),
Internal reactor structures such as a core support 9 and further control rod guide tubes 10 are incorporated. Also, lower mirror 3
A control rod drive mechanism housing 11 and a reactor pressure vessel drain pipe 12 are welded to each other.

以上の構成において、圧力容器1の底部に接続
されているドレン配管12を取り替えるには、容
器1を炉水で満水した状態、すなわち容器底部の
ドレン配管接続口部を水封した状態にしなけれ
ば、高放射線環境となり、作業者が近づけない。
In the above configuration, in order to replace the drain pipe 12 connected to the bottom of the pressure vessel 1, the vessel 1 must be filled with reactor water, that is, the drain pipe connection port at the bottom of the vessel must be sealed with water. , creating a highly radioactive environment that workers cannot approach.

したがつて、炉水有りの状態でドレン配管12
を取り替えるには、容器底部のドレン配管接続口
部に水封プラグを装着することになるが、このプ
ラグの装着操作は、炉心上方からおこなわれる。
プラグ装着に際しては、圧力容器1の胴内から各
種据付機器を取り除く必要があるが、胴内から取
り外しできるものは、蒸気乾燥器4、気水分離器
5、シユラウド上蓋6、燃料棒8、図示を省略し
た燃料棒サポートおよび制御棒案内管10であ
り、その他の炉内構造物は、胴体1と一体に溶接
されているため、取り外しできない。第2図は第
1図に示す圧力容器1の胴内から各種据付機器を
取り除き、容器胴体と胴内溶接部材との配置関係
を示す図、第3図は第2図のA−A矢視図であつ
て、上部格子板7、炉心サポート9および制御棒
駆動機構ハウジング11が圧力容器1の胴内に残
り、これらが水封プラグの挿入、引抜時の障害と
なる。これをさらに詳述すると、第2図に符号1
3で示すドレン配管接続口部は、多数林立した制
御棒駆動機構ハウジング11の間に位置してお
り、しかも既設の原子炉圧力容器においては、こ
れまた第2図に示すように、ドレン配管接続口部
13が圧力容器1の中心部から偏倚して設けられ
ているため、ドレン配管12の取替作業に先立つ
て圧力容器1のフランジ部1aにプラツトフオー
ムを設置し、炉水満水の状態でドレン配管接続口
部13に水封プラグを装着しようとしても、この
作業には煩雑さがともなう。
Therefore, in a state where reactor water is present, the drain pipe 12
To replace the reactor, a water seal plug must be installed at the drain pipe connection port at the bottom of the vessel, but this plug is installed from above the core.
When installing the plug, it is necessary to remove various installed equipment from the inside of the pressure vessel 1. The items that can be removed from the inside of the pressure vessel 1 are the steam dryer 4, steam separator 5, shroud top cover 6, fuel rods 8, and the The fuel rod support and control rod guide tube 10 are omitted, and the other reactor internal structures are integrally welded to the fuselage 1 and cannot be removed. Fig. 2 is a diagram showing the arrangement relationship between the vessel body and the internal welding members after removing various installed equipment from the inside of the pressure vessel 1 shown in Fig. 1, and Fig. 3 is a view taken along arrow A-A in Fig. 2. In the figure, the upper grid plate 7, core support 9, and control rod drive mechanism housing 11 remain in the shell of the pressure vessel 1, and these become obstacles when inserting and withdrawing the water seal plug. To explain this in more detail, reference numeral 1 is shown in Figure 2.
The drain pipe connection port indicated by 3 is located between many control rod drive mechanism housings 11, and in the existing reactor pressure vessel, as shown in FIG. Since the mouth part 13 is provided offset from the center of the pressure vessel 1, a platform is installed on the flange part 1a of the pressure vessel 1 prior to the replacement work of the drain pipe 12, and the reactor is filled with water. Even if an attempt is made to attach a water seal plug to the drain pipe connection port 13, this operation is complicated.

一方、ドレン配管接続口部13の内壁には、経
年によつてクラツド等の異物が付着し、この異物
によつて水封効果が損なわれることが予想される
ため、口部13の水封に先立つては、上記異物の
除去を考慮しておく必要がある。
On the other hand, foreign matter such as crud adheres to the inner wall of the drain pipe connection port 13 over time, and this foreign matter is expected to impair the water sealing effect. Beforehand, it is necessary to consider the removal of the foreign matter.

これに対し、原子炉圧力容器の中心部から偏倚
して設けられているドレン配管接続口部に水封プ
ラグが容易に到達すべく、先端に水封プラグを取
り付けた操作ロツドの途中に屈曲部を設けて、こ
の操作ロツドを原子炉圧力容器の上方から炉内に
出し入れ自在とした炉水漏洩遮断装置が、特開昭
55−39020号として先に提案されている。
On the other hand, in order for the water seal plug to easily reach the drain piping connection port, which is offset from the center of the reactor pressure vessel, there is a bend in the middle of the operating rod with the water seal plug attached to the tip. A reactor water leakage cutoff device was developed in Japanese Patent Application Laid-Open No. 2003-103002, in which the operating rod can be taken in and out of the reactor from above the reactor pressure vessel.
Previously proposed as No. 55-39020.

本発明は、この種炉水漏洩遮断装置、すなわち
先端に水封プラグが取り付けられた操作ロツドの
途中に屈曲部を設けた原子炉圧力容器の炉水漏洩
遮断装置をさらに改良したものであつて、その目
的とするところは、沸騰水型原子炉圧力容器のド
レン配管取替作業に先立ち、炉水満水の状態でド
レン配管接続口部の研磨、すなわち既述のごと
く、ドレン配管接続口部の内壁には、経年によつ
てクラツド等の異物が付着し、この異物によつて
水封効果が損なわれることが予想されるため、ド
レン配管接続口部の水封に先立つ当該口部の研
磨、さらにはこれに続く水封プラグの装着をおこ
なう場合に、装置の一部を共用化して製品コスト
の低減化をはかり得、しかも水封プラグによるド
レン配管接続口部の水封信頼性向上化と長寿命を
も同時にはかることのできる原子炉圧力容器の炉
水漏洩遮断装置を提供することにある。
The present invention is a further improvement of this type of reactor water leakage cutoff device, that is, a reactor water leakage cutoff device for a reactor pressure vessel in which a bent part is provided in the middle of an operating rod with a water seal plug attached to the tip. The purpose of this is to polish the drain piping connection port while the reactor water is full, prior to the drain piping replacement work of the boiling water reactor pressure vessel. Foreign matter such as crud adheres to the inner wall over time, and it is expected that this foreign matter will impair the water sealing effect. Furthermore, when installing a water seal plug subsequent to this, it is possible to share a part of the equipment and reduce product costs.In addition, the water seal plug can improve the reliability of the water seal at the drain piping connection port. It is an object of the present invention to provide a reactor water leakage cutoff device for a nuclear reactor pressure vessel that can also ensure a long service life.

上記目的は、原子路圧力容器の上方から炉内に
出し入れされる操作ロツドの先端に、上記圧力容
器底部のドレン配管接続口部を水封するプラグユ
ニツトを装着し、かつ原子炉圧力容器のドレン配
管接続口部を水封するプラグユニツトを、上下二
段のシール構造とし、上方に位置するシールプラ
グを、その自重と炉水の水圧ヘツドによりドレン
配管接続口部の内壁に密着する楔型に形成すると
ともに、上記操作ロツドの途中(原子炉圧力容器
内に位置する炉心サポートより、下方に挿入され
る操作ロツド部分)に、原子炉圧力容器の中心部
から偏倚して設けられているドレン配管接続口部
にプラグユニツトが到達する屈曲部を形成した原
子炉圧力容器の炉水漏洩遮断装置において、上記
操作ロツドの先端に接続されるジヨイント部と、
ジヨイント部の下部に設けられたエアモータと、
エアモータの下部に取り付けられた研磨ブラシと
を有し、かつ圧力容器底部のドレン配管接続口部
を研磨する研磨ユニツトを、上記プラグユニツト
と交換自在に操作ロツドに取り付け、かつ操作ロ
ツド内に通路を設け、この通路を、研磨ユニツト
のエアモータへの圧縮空気供給通路、およびシー
ルプラグを上下二段に構成したシールプラグユニ
ツトのうち、下方に位置するシールプラグへの圧
縮空気供給通路として共用するとともに、上記二
段に構成されたシールプラグのうち、下方に位置
するシールプラグを、当該プラグの中空部を加工
することにより膨張させて、上記ドレン配管接続
口部の内壁に密着させる構造とすることによつて
達成される。
The above purpose is to attach a plug unit to the tip of the operating rod that is moved in and out of the reactor from above the reactor pressure vessel to seal the drain pipe connection port at the bottom of the reactor pressure vessel, and The plug unit that water-seals the pipe connection port has a two-stage seal structure, upper and lower, and the upper seal plug is wedge-shaped so that it tightly contacts the inner wall of the drain pipe connection port due to its own weight and the hydraulic head of the reactor water. At the same time, a drain pipe is provided in the middle of the operating rod (the part of the operating rod that is inserted below the core support located in the reactor pressure vessel) and is offset from the center of the reactor pressure vessel. A reactor water leakage cutoff device for a reactor pressure vessel having a bent portion through which a plug unit reaches a connection port, comprising: a joint portion connected to the tip of the operating rod;
An air motor installed at the bottom of the joint,
A polishing unit having a polishing brush attached to the bottom of the air motor and polishing the drain pipe connection port at the bottom of the pressure vessel is attached to the operating rod so as to be replaceable with the plug unit, and a passage is provided in the operating rod. This passage is shared as a compressed air supply passage to the air motor of the polishing unit and a compressed air supply passage to the lower seal plug of the seal plug unit configured with upper and lower seal plugs, Among the two-tiered seal plugs, the lower seal plug is expanded by processing the hollow part of the plug, so that it comes into close contact with the inner wall of the drain pipe connection port. It is achieved by doing so.

以下、本発明を、第4図ないし第7図の一実施
例にもとづいて説明すると、本発明装置は、第4
図および第5図に示すロツド14、すなわち原子
炉圧力容器1の上方から炉内に出し入れされる操
作ロツド14と、上記操作ロツド14の先端に取
り付けられ、圧力容器1のドレン配管接続口部1
3を研磨する研磨ユニツト15(第6図)と、上
記研磨ユニツト15と交換して操作ロツド14の
先端に取り付けられ、圧力容器1のドレン配管接
続口部13を水封するプラグユニツト16(第7
図)との組み合わせからなり、圧力容器1の中心
部(換言すると、上部格子板7および炉心サポー
ト9の穴部中心d)から偏倚して設けられている
ドレン配管接続口部13に研磨ユニツト15(お
よびプラグユニツト16)が到達し得るよう、上
記操作ロツド14の途中(炉心サポート9よりも
下方に挿入される操作ロツド部分)に屈曲部14
aが形成されている。
Hereinafter, the present invention will be explained based on an embodiment shown in FIGS. 4 to 7.
The operating rod 14 shown in FIG. 1 and FIG.
A plug unit 16 (FIG. 6) which is attached to the tip of the operating rod 14 in place of the polishing unit 15 and seals the drain pipe connection port 13 of the pressure vessel 1 with water. 7
A polishing unit 15 is attached to the drain pipe connection port 13 which is provided offset from the center of the pressure vessel 1 (in other words, the hole center d of the upper grid plate 7 and the core support 9). (and the plug unit 16), there is a bent part 14 in the middle of the operating rod 14 (the part of the operating rod inserted below the core support 9).
a is formed.

原子炉圧力容器1のドレン配管接続口部13を
研磨する研磨ユニツト15は、第6図に示すよう
に、操作ロツド14とのジヨイント部17、エア
モータ18および研磨ブラシ19で構成され、研
磨ブラシ19を回転させるエアモータ18には、
操作ロツド14内を貫通する通路を通つて、空気
源からの圧縮空気が供給される。
As shown in FIG. 6, the polishing unit 15 for polishing the drain pipe connection port 13 of the reactor pressure vessel 1 is composed of a joint 17 with the operating rod 14, an air motor 18, and a polishing brush 19. The air motor 18 that rotates the
Compressed air is supplied from an air source through a passageway passing through the operating rod 14.

原子炉圧力容器1のドレン配管接続口部13を
水封するプラグユニツト16は、第7図に示すよ
うに、上下二段のゴム製シールプラグ20および
21を有しており、下方に位置するシールプラグ
20は、その中空部を加圧することにより膨張し
て、ドレン配管接続口部13の内壁に密着する。
なお、シールプラグ20の中空部には、操作ロツ
ド14内を貫通する通路を通つて、空気源からの
圧縮空気が供給されるものであり、研磨ユニツト
15とプラグユニツト16に対する圧縮空気供給
通路を両ユニツト15,16で共用することによ
り、空気供給系の簡略化がはかれ、製品コストの
低減化に寄与する。シールプラグ20の上方に位
置するシールプラグ21は、楔型に形成されてお
り、その自重と炉水の水圧ヘツドにより、ドレン
配管接続口部13の内壁に密着する。
The plug unit 16 that seals the drain pipe connection port 13 of the reactor pressure vessel 1 has rubber seal plugs 20 and 21 in two stages, upper and lower, as shown in FIG. The seal plug 20 expands by pressurizing its hollow portion and comes into close contact with the inner wall of the drain pipe connection port 13 .
The hollow portion of the seal plug 20 is supplied with compressed air from an air source through a passage passing through the operating rod 14, and a compressed air supply passage for the polishing unit 15 and the plug unit 16 is provided. By sharing the air supply system with both units 15 and 16, the air supply system can be simplified, contributing to a reduction in product cost. The seal plug 21 located above the seal plug 20 is formed into a wedge shape, and is brought into close contact with the inner wall of the drain pipe connection port 13 due to its own weight and the hydraulic head of the reactor water.

以上の構成において、原子炉圧力容器1の底部
に接続されているドレン配管を、炉水満水の状態
で取替えるに先立つては、まず、操作ロツド14
の先端に研磨ユニツト15を取り付け、この研磨
ユニツト15により、圧力容器1のドレン配管接
続口部13を研磨し、経年によつて口部13の内
壁に付着しているクラツド等の異物を取り除くこ
とにより、プラグユニツト16と口部13との密
着性を高める。しかして、その場合の操作ロツド
14の取扱は、次のとおりである。まず、第6図
に示すように、圧力容器1の上方より操作ロツド
14を下降させ、ロツド14の屈曲部14aが炉
心サポート9の穴部を通過したならば、ロツド1
4をドレン配管接続口部13の方向に平行移動さ
せる。このようにして、研磨ユニツト15がドレ
ン配管接続口部13の位置に達したならば、ロツ
ド14を下降させ、空気源を開いて圧縮空気をエ
アーモータ18に供給し、研磨ブラシ19を回転
させることにより、ドレン配管接続口部13の内
壁に付着しているクラツド等の異物を取り除く。
In the above configuration, before replacing the drain pipe connected to the bottom of the reactor pressure vessel 1 while the reactor water is full, first, the operating rod 14
A polishing unit 15 is attached to the tip of the pipe, and the polishing unit 15 polishes the drain pipe connection port 13 of the pressure vessel 1 to remove foreign matter such as crud that has adhered to the inner wall of the port 13 over time. This improves the adhesion between the plug unit 16 and the mouth portion 13. The handling of the operating rod 14 in that case is as follows. First, as shown in FIG. 6, the operating rod 14 is lowered from above the pressure vessel 1, and when the bent portion 14a of the rod 14 passes through the hole in the core support 9, the rod 1
4 in parallel in the direction of the drain pipe connection port 13. In this way, when the polishing unit 15 reaches the position of the drain pipe connection port 13, the rod 14 is lowered, the air source is opened, compressed air is supplied to the air motor 18, and the polishing brush 19 is rotated. By doing so, foreign matter such as crud adhering to the inner wall of the drain pipe connection port 13 is removed.

以上のようにして、ドレン配管接続口部13の
内壁研磨が終了したならば、空気源を閉じてエア
ーモータ18への圧縮空気の供給を停止し、研磨
ブラシ19の回転を止めて操作ロツド14を引き
上げ、口部13から研磨ユニツト15を抜き出
し、操作ロツド14を炉内挿入と反対の手順で圧
力容器1内から取り出す。続いて、操作ロツド1
4の先端に取付けられている研磨ユニツト15を
取り外し、このロツド先端に新たにプラグユニツ
ト16を取り付け、既述した研磨ユニツト15の
炉内挿入と同じ要領で、プラグユニツト16をド
レン配管接続口部13内に装着する。プラグユニ
ツト16を口部13内に装着後、空気源を開き、
圧縮空気でシールプラグ20の中空部を加圧する
と、このシールプラグ20は膨張して、ドレン配
管接続口部13の内壁に密着する。以上のように
して、ドレン配管接続口部13を水封した状態で
ドレン配管の取替工事が終了したならば、空気源
を閉じてシールプラグ20への空気加圧を止め、
操作ロツド14を引き上げ、ドレン配管接続口部
13からプラグユニツト16を抜き出し、操作ロ
ツド14を圧力容器1内から取り出すことによ
り、作業は終了する。
When the inner wall polishing of the drain pipe connection port 13 is completed as described above, the air source is closed to stop supplying compressed air to the air motor 18, the rotation of the polishing brush 19 is stopped, and the operation rod 14 is The polishing unit 15 is pulled up from the mouth 13, and the operating rod 14 is taken out from the pressure vessel 1 in the reverse order of insertion into the furnace. Next, operation rod 1
Remove the polishing unit 15 attached to the tip of the rod 4, attach a new plug unit 16 to the tip of this rod, and insert the plug unit 16 into the drain pipe connection port in the same manner as the insertion of the polishing unit 15 into the furnace described above. Install it within 13. After installing the plug unit 16 into the mouth 13, open the air source and
When the hollow part of the seal plug 20 is pressurized with compressed air, the seal plug 20 expands and comes into close contact with the inner wall of the drain pipe connection port 13. When the drain piping replacement work is completed with the drain piping connection port 13 sealed with water as described above, the air source is closed to stop pressurizing the seal plug 20.
The operation is completed by pulling up the operating rod 14, extracting the plug unit 16 from the drain pipe connection port 13, and removing the operating rod 14 from the pressure vessel 1.

なお、操作ロツド14の先端部付近、あるいは
研磨ユニツト15およびプラグユニツト16にユ
ニバーサルジヨイントを取り付けておけば、上記
各ユニツト15,16の先端部は、ドレン配管接
続口部13の穴内にスムーズにガイドされる。
If a universal joint is attached near the tip of the operating rod 14 or to the polishing unit 15 and plug unit 16, the tips of the units 15 and 16 will fit smoothly into the hole of the drain pipe connection port 13. be guided.

ところで、既述した特開昭55−39020号公報に
は、原子炉圧力容器のドレン配管接続口部を水封
する上下二段のプラグユニツトのうち、下方に位
置するシールプラグ、すなわちゴム等の弾性体で
構成されたシールプラグの外径を、ドレン配管接
続口部の内径よりも大径とし、ドレン配管接続口
部の内径よりも大径とし、ドレン配管接続口部の
閉塞時、このシールプラグを、上記ドレン配管接
続口部に強制的に押し込む記載があるが、これに
よれば、弾性体からなるシールプラグは、使用の
都度、原子炉圧力容器のドレン配管接続口部に無
理やり押し込まれるため、当該ドレン配管接続口
部の内壁とシールプラグとの間の摺動摩擦は非常
に大きく、プラグ外周の水封効果が比較的早めの
うちに損なわれることが考えられ、斯かる場合、
重要機器である原子炉圧力容器の水封機能に万全
を期すためには、上記プラグの交換頻度が高くな
ることをあらかじめ予測しておかなければならな
い。これに対し、本発明においては、既述のごと
く、原子炉圧力容器のドレン配管接続口部13を
水封する上下一対のシールプラグ21,20のう
ち、下方に位置するシールプラグ20を、その中
空部を加圧することにより膨張させて、ドレン配
管接続口部13の内壁に密着させる構造としたこ
とにより、シールプラグ20に無理な外力を加え
ることなく、当該シールプラグ20をドレン配管
接続口部内壁に密着させることができ、その耐用
性を、上記従来のこの種装置に比べて大幅に向上
させることができる。
By the way, in the above-mentioned Japanese Patent Application Laid-open No. 55-39020, there is a seal plug located at the lower part of the upper and lower two-stage plug unit that water-seals the drain pipe connection port of the reactor pressure vessel, that is, a seal plug made of rubber or the like. The outer diameter of the seal plug made of an elastic material is larger than the inner diameter of the drain pipe connection port, and the seal plug is made larger than the inner diameter of the drain pipe connection port, so that when the drain pipe connection port is blocked, this seal There is a description of forcibly pushing the plug into the drain pipe connection port, but according to this, the seal plug made of an elastic material is forced into the drain pipe connection port of the reactor pressure vessel each time it is used. Therefore, the sliding friction between the inner wall of the drain pipe connection port and the seal plug is extremely large, and it is thought that the water sealing effect around the plug's outer periphery will be lost relatively quickly.
In order to ensure the water-sealing function of the reactor pressure vessel, which is an important piece of equipment, it is necessary to predict in advance that the frequency of replacing the plug will increase. In contrast, in the present invention, as described above, of the pair of upper and lower seal plugs 21 and 20 that water-seal the drain pipe connection port 13 of the reactor pressure vessel, the lower seal plug 20 is By applying pressure to the hollow part to expand it and make it tightly contact the inner wall of the drain pipe connection port 13, the seal plug 20 can be attached to the drain pipe connection port without applying excessive external force to the seal plug 20. It can be brought into close contact with the inner wall, and its durability can be greatly improved compared to the conventional devices of this kind.

本発明は以上のごときであり、本発明によれ
ば、原子炉圧力容器の中心部から偏倚して設けら
れているドレン配管接続口部に水封プラグが容易
に到達すべく、先端に水封プラグを取り付けた操
作ロツドの途中に屈曲部を設けて、この操作ロツ
ドを原子炉圧力容器の上方から炉内に出し入れ自
在とした炉水漏洩遮断装置において、原子炉圧力
容器のドレン配管取替作業に先立ち、炉水満水の
状態でドレン配管接続口部の研磨、さらにはこれ
に続く水封プラグの装着をおこなう場合に、装置
の一部を共用化して製品コストの低減化をはかり
得、しかも水封プラグによるドレン配管接続口部
の水封信頼性向上化と長寿命をも同時にはかるこ
とのできる、改良された原子炉圧力容器の炉水漏
洩遮断装置を提供することができる。
The present invention is as described above, and according to the present invention, a water seal is attached to the tip of the water seal plug so that the water seal plug can easily reach the drain pipe connection port provided offset from the center of the reactor pressure vessel. Replacement work on the reactor pressure vessel drain piping in a reactor water leakage shutoff system in which a bent part is provided in the middle of the operating rod to which a plug is attached so that the operating rod can be taken in and out of the reactor from above the reactor pressure vessel. When polishing the drain piping connection port and subsequently installing the water seal plug in a state where the reactor water is full prior to the process, it is possible to share part of the equipment and reduce product costs. It is possible to provide an improved reactor water leakage shutoff device for a reactor pressure vessel that can simultaneously improve the reliability of the water seal at the drain piping connection port using the water seal plug and extend its life.

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

第1図は沸騰水型原子炉圧力容器の内部構造説
明図、第2図は第1図に示す圧力容器の胴内から
各種据付機器を取り除き、容器胴体と胴内溶接部
材との配置関係を示す図、第3図は第2図のA−
A矢視図、第4図ないし第7図は本発明の一実施
例を示し、第4図および第5図はいずれも本発明
装置の全体的な取扱説明図、第6図は原子炉圧力
容器のドレン配管接続口部を研磨する研磨ユニツ
トの構成説明図、第7図は原子炉圧力容器のドレ
ン配管接続口部を水封するプラグユニツトの構成
説明図である。 1……原子炉圧力容器、1a……フランジ、7
……上部格子板、9……炉心サポート、11……
制御棒駆動機構ハウジング、12……ドレン配
管、13……ドレン配管接続口部、14……操作
ロツド、14a……屈曲部、15……研磨ユニツ
ト、16……プラグユニツト、17……ジヨイン
ト部、18……エアーモータ、19……研磨ブラ
シ、20および21……シールプラグ。
Figure 1 is an explanatory diagram of the internal structure of a boiling water reactor pressure vessel, and Figure 2 shows the arrangement of the vessel body and internal welding parts after removing various installed equipment from the pressure vessel body shown in Figure 1. The figure shown in Figure 3 is A- in Figure 2.
A view from arrow A and FIGS. 4 to 7 show an embodiment of the present invention, FIGS. 4 and 5 are illustrations for explaining the overall operation of the device of the present invention, and FIG. 6 shows the reactor pressure. FIG. 7 is an explanatory diagram of the configuration of a polishing unit for polishing a drain pipe connection port of a vessel, and FIG. 1... Reactor pressure vessel, 1a... Flange, 7
... Upper grid plate, 9 ... Core support, 11 ...
Control rod drive mechanism housing, 12... Drain pipe, 13... Drain pipe connection port, 14... Operation rod, 14a... Bent part, 15... Polishing unit, 16... Plug unit, 17... Joint part , 18...Air motor, 19...Abrasive brush, 20 and 21...Seal plug.

Claims (1)

【特許請求の範囲】 1 原子炉圧力容器の上方から炉内に出し入れさ
れる操作ロツドの先端に、上記圧力容器底部のド
レン配管接続口部を水封するプラグユニツトを装
着し、かつ原子炉圧力容器のドレン配管接続口部
を水封するプラグユニツトを、上下二段のシール
構造とし、上方に位置するシールプラグを、その
自重と炉水の水圧ヘツドによりドレン配管接続口
部の内壁に密着する楔型に形成するとともに、上
記操作ロツドの途中(原子炉圧力容器内に位置す
る炉心サポートよりも下方に挿入される操作ロツ
ド部分)に、原子炉圧力容器の中心部から偏倚し
て設けられているドレン配管接続口部にプラグユ
ニツトが到達する屈曲部を形成した原子炉圧力容
器の炉水漏洩遮断装置において、 上記操作ロツドの先端に接続されるジヨイント
部と、ジヨイント部の下部に設けられたエアーモ
ータと、エアーモータの下部に取り付けられた研
磨ブラシとを有し、かつ圧力容器底部のドレン配
管接続口部を研磨する研磨ユニツトを、上記プラ
グユニツトと交換自在に操作ロツドに取り付け、
かつ操作ロツド内に通路を設け、この通路を、研
磨ユニツトのエアーモータへの圧縮空気供給通
路、およびシールプラグを上下二段に構成したシ
ールプラグユニツトのうち、下方に位置するシー
ルプラグへの圧縮空気供給通路として共用すると
ともに、上記二段に構成されたシールプラグのう
ち、下方に位置するシールプラグを、当該プラグ
の中空部を加圧することにより膨張させて、上記
ドレン配管接続口部の内壁に密着する構造とした
ことを特徴とする原子炉圧力容器の炉水漏洩遮断
装置。
[Scope of Claims] 1. A plug unit for water-sealing the drain piping connection port at the bottom of the pressure vessel is attached to the tip of an operating rod that is moved in and out of the reactor from above the reactor pressure vessel, and The plug unit that seals the drain piping connection port of the vessel has a two-tiered seal structure, with the upper seal plug tightly attached to the inner wall of the drain piping connection port due to its own weight and the hydraulic head of the reactor water. It is formed in a wedge shape, and is provided in the middle of the operating rod (the part of the operating rod that is inserted below the core support located in the reactor pressure vessel) so as to be offset from the center of the reactor pressure vessel. In a reactor water leakage cutoff device for a reactor pressure vessel, which has a bent part where the plug unit reaches the drain pipe connection port, a joint part connected to the tip of the operating rod and a joint part provided at the bottom of the joint part are used. A polishing unit having an air motor and a polishing brush attached to the bottom of the air motor and polishing the drain pipe connection port at the bottom of the pressure vessel is attached to the operating rod so as to be replaceable with the plug unit,
In addition, a passage is provided in the operating rod, and this passage is used as a passage for supplying compressed air to the air motor of the polishing unit, and for supplying compressed air to the lower seal plug of the seal plug unit, which has two upper and lower seal plugs. In addition to being shared as an air supply passage, the lower seal plug of the two-tiered seal plug is expanded by pressurizing the hollow part of the plug, and the inner wall of the drain pipe connection port is expanded. 1. A reactor water leak cutoff device for a reactor pressure vessel, characterized by having a structure that is in close contact with the reactor pressure vessel.
JP57084181A 1982-05-18 1982-05-18 Reactor water leakage shielding device for reactor pressure vessel Granted JPS58200195A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57084181A JPS58200195A (en) 1982-05-18 1982-05-18 Reactor water leakage shielding device for reactor pressure vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57084181A JPS58200195A (en) 1982-05-18 1982-05-18 Reactor water leakage shielding device for reactor pressure vessel

Publications (2)

Publication Number Publication Date
JPS58200195A JPS58200195A (en) 1983-11-21
JPS6411160B2 true JPS6411160B2 (en) 1989-02-23

Family

ID=13823305

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57084181A Granted JPS58200195A (en) 1982-05-18 1982-05-18 Reactor water leakage shielding device for reactor pressure vessel

Country Status (1)

Country Link
JP (1) JPS58200195A (en)

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS547987A (en) * 1977-06-20 1979-01-20 Hitachi Ltd Method and system for inspecting reactor
JPS5930237B2 (en) * 1978-09-12 1984-07-25 株式会社東芝 Reactor drain plug installation device
JPS562593A (en) * 1979-06-22 1981-01-12 Hitachi Ltd Method of sealing main steam nozzle

Also Published As

Publication number Publication date
JPS58200195A (en) 1983-11-21

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