JPH03238398A - Main steam pipe plug of boiling water reactor and method for testing leakage of main steam isolation valve using the same - Google Patents

Main steam pipe plug of boiling water reactor and method for testing leakage of main steam isolation valve using the same

Info

Publication number
JPH03238398A
JPH03238398A JP2034698A JP3469890A JPH03238398A JP H03238398 A JPH03238398 A JP H03238398A JP 2034698 A JP2034698 A JP 2034698A JP 3469890 A JP3469890 A JP 3469890A JP H03238398 A JPH03238398 A JP H03238398A
Authority
JP
Japan
Prior art keywords
main steam
steam pipe
plug
isolation valve
valve
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
Application number
JP2034698A
Other languages
Japanese (ja)
Other versions
JP3005234B2 (en
Inventor
Takeshi Saijo
西條 武司
Takahiro Konno
今野 隆博
Takashi Sekigami
隆 関上
Toshihiro Kodama
俊博 児玉
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.)
HESCO
Hitachi Ltd
Original Assignee
HESCO
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 HESCO, Hitachi Ltd filed Critical HESCO
Priority to JP2034698A priority Critical patent/JP3005234B2/en
Publication of JPH03238398A publication Critical patent/JPH03238398A/en
Application granted granted Critical
Publication of JP3005234B2 publication Critical patent/JP3005234B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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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
    • 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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To simplify the leak test of a main steam isolation valve by mounting a main steam line (pipe) plug to the main steam line between a reactor pressure vessel and the main steam isolation valve. CONSTITUTION:After a main steam escape safety valve is detached, a bag body 10 is inserted in the opening part of a main steam escape safety valve tube base 5, which is fixed to a flange 8 by bolts. Next, a nitrogen gas cylinder 12 is connected to an air guide pipe 9 to open a source-valve 11. By this operation, nitrogen gas is guided to a main steam pipe plug, that is, the bag body 10 through the air guide pipe 9. The main steam pipe plug 10 expands and closely comes into contact with the inner wall of a main steam pipe 4 to complete sealing. Herein, the source-valve 11 is fully closed to cut off the connection with the nitrogen gas cylinder 12. When a main steam line 4 is isolated from a reactor 3, compressed air is supplied to the main steam line between the main steam pipe plug 10 and the main steam isolation valve 6 to make it possible to perform the leak test of the main steam isolation valve 6 apart from in-pile work.

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、沸騰水型原子炉圧力容器から延在しその途中
に主蒸気隔離弁を備えた主蒸気ラインに着脱自在に取付
けられる主蒸気ラインプラグと。
[Detailed Description of the Invention] [Field of Industrial Application] The present invention relates to a main steam line that extends from a boiling water reactor pressure vessel and is detachably attached to a main steam line that is provided with a main steam isolation valve in the middle. with line plug.

これを用いた主蒸気隔離弁漏洩試験方法に関するもので
ある。
This article relates to a main steam isolation valve leakage test method using this method.

[従来の技術] 従来の主蒸気ラインを含む原子炉圧力容器近傍の構造は
、概略第5図に示すように構成されている。すなわち炉
(M子炉圧力容器)3の上方部分からは複数本の主蒸気
ライン4が出ており、これらのラインに主蒸気逃し安全
弁(但し、図では該弁自体の図示は省略し、該弁を取付
ける管台5のみを図示しである)および主蒸気隔離弁6
が設けられている。
[Prior Art] A conventional structure in the vicinity of a nuclear reactor pressure vessel including a main steam line is generally constructed as shown in FIG. That is, a plurality of main steam lines 4 come out from the upper part of the furnace (M child reactor pressure vessel) 3, and a main steam relief safety valve (however, the illustration of the valve itself is omitted in the figure) is connected to these lines. (Only the nozzle stub 5 on which the valve is attached is shown) and the main steam isolation valve 6
is provided.

定期点検の際には、特開昭58−166290号公報、
同56−30693号公報等に開示されているように、
主蒸気ライン4が接続されている原子炉圧力容器3の主
蒸気ノズルには、圧力容器3内から主蒸気ラインプラグ
が着脱可能に取付けられるようになっている。なお第5
図中では主蒸気ラインプラグを取付けるための装M2が
示されている。
During periodic inspections, please refer to Japanese Patent Application Laid-Open No. 58-166290,
As disclosed in Publication No. 56-30693, etc.,
A main steam line plug is detachably attached to the main steam nozzle of the reactor pressure vessel 3 to which the main steam line 4 is connected from inside the pressure vessel 3. Furthermore, the fifth
In the figure, a mounting M2 for attaching the main steam line plug is shown.

上記のような原子炉の定期点検に伴う炉内作業及び主蒸
気管関連作業は第6図に示すような手順で従来実施され
ている。主蒸気管関連作業の中で、主蒸気隔離弁6の点
検には、主蒸気隔離弁分解前後に漏洩試験を行なう。漏
洩試験は、主蒸気管入口(主蒸気ノズル)に炉内から主
蒸気ラインプラグを取付け、主蒸気隔離弁6を全開状態
にして、この両者間に空気圧をかけて実施している。
Work inside the reactor and work related to the main steam pipes accompanying periodic inspections of nuclear reactors as described above have conventionally been carried out according to the procedure shown in FIG. Among the main steam pipe-related work, the main steam isolation valve 6 is inspected by performing a leakage test before and after disassembling the main steam isolation valve. The leakage test is carried out by attaching a main steam line plug to the main steam pipe inlet (main steam nozzle) from inside the furnace, fully opening the main steam isolation valve 6, and applying air pressure between the two.

定検全体の工程長は、炉内作業を主体とした一連のシー
ケンスで決まる(即ち炉内作業がいわゆるクリティカル
バスとなる)ため、炉内作業を優先させたシーケンスが
組まれる。第6図に示す原子炉圧力容器上蓋取外、スチ
ームドライヤ取外、スチームセパレータ取外まで進むと
炉内から燃料を移動させることができる状態となる。た
だし、スチームセパレータ及び燃料は、高線量機器のた
め大気中で移動することは出来ない。従って、スチーム
セパレータ取外に合わせて、主蒸気管下の通常水位から
主蒸気管上のウェル満水まで水位を上昇させ、水中でこ
れ等の機器を取扱う。ところが、水位を上昇させると主
蒸気管内が水没し、漏洩試験で始まる主蒸気隔離弁6の
点検が出来なくなる。従って、スチームセパレータを取
外した後、原子炉圧力容器3内の主蒸気管入口に主蒸気
ラインプラグを設置し、原子炉圧力容器3内と主蒸気管
4を隔離する。
The overall process length of regular inspections is determined by a series of sequences that mainly involve in-furnace work (in other words, the in-furnace work constitutes a so-called critical bus), so a sequence is established that gives priority to the in-furnace work. When the reactor pressure vessel top cover is removed, the steam dryer is removed, and the steam separator is removed as shown in FIG. 6, the fuel can be moved from inside the reactor. However, the steam separator and fuel cannot be moved in the atmosphere because they are high-dose equipment. Therefore, in conjunction with the removal of the steam separator, the water level is raised from the normal water level below the main steam pipe to a full well above the main steam pipe, and these devices are handled underwater. However, when the water level rises, the inside of the main steam pipe becomes submerged, making it impossible to inspect the main steam isolation valve 6 starting with the leakage test. Therefore, after removing the steam separator, a main steam line plug is installed at the inlet of the main steam pipe inside the reactor pressure vessel 3 to isolate the inside of the reactor pressure vessel 3 and the main steam pipe 4.

主蒸気ラインプラグの設置後、主蒸気管に溜った水抜き
を行ない、主蒸気ラインプラグと主蒸気隔離弁6の間に
空気圧をかけることにより主蒸気隔離弁の漏洩試験を行
なうことが可能となる。
After installing the main steam line plug, it is possible to perform a leakage test on the main steam isolation valve by draining the water accumulated in the main steam pipe and applying air pressure between the main steam line plug and the main steam isolation valve 6. Become.

一方、主蒸気管4には、主蒸気入口と主蒸気隔離弁の間
に、主蒸気逃し安全弁が設置されている。
On the other hand, a main steam relief safety valve is installed in the main steam pipe 4 between the main steam inlet and the main steam isolation valve.

水弁も点検のため、フランジ構造をした主蒸気逃し安全
弁管台5より取外され、管台5には主蒸気隔離弁漏洩試
験のため閉止フランジが取付けられる。
The water valve is also removed from the main steam safety relief valve nozzle 5 having a flange structure for inspection, and a closing flange is attached to the nozzle 5 for a main steam isolation valve leakage test.

[発明が解決しようとする課題] 以上のように、クリティカルバスとなる炉内作業を優先
させた作業シーケンスを組むため、主蒸気ラインプラグ
の設置が必要であり、かつ、従来の技術では主蒸気ライ
ンプラグの取付及び取外が、炉内作業の一連のシーケン
スに含まれているため、これがクリティカルバスとなっ
ていた。
[Problem to be solved by the invention] As described above, in order to set up a work sequence that prioritizes the work inside the reactor, which is a critical bus, it is necessary to install a main steam line plug, and in the conventional technology, the main steam line The installation and removal of line plugs was included in the sequence of in-furnace work, so this was a critical bus.

また第7図に示すように、インターナルポンプ16を内
臓した沸騰水型原子炉においては、インターナルポンプ
16を点検する際、インペラ・シャフト17は、燃料取
替機18からワイヤ15を鉛直に吊り上げて引き抜く、
ところが、従来型の主蒸気ラインプラグ設置構造は、炉
内壁に沿ってリング状の構造となっているため、上記の
引き抜き時にこれと干渉する。従って従来型の主蒸気ラ
インプラグを使用した場合、インペラ・シャフト17を
引き抜くためには、主蒸気ラインプラグの取外が新たに
必要になる。さらに、この主蒸気ラインプラグの取外は
、主蒸気隔離弁6の点検作業に新しい工程的制約を作る
ことになる。
Further, as shown in FIG. 7, in a boiling water reactor equipped with an internal pump 16, when inspecting the internal pump 16, the impeller shaft 17 is connected vertically to the wire 15 from the fuel exchanger 18. Lift it up and pull it out.
However, since the conventional main steam line plug installation structure has a ring-shaped structure along the inner wall of the furnace, it interferes with this during the above-mentioned extraction. Therefore, when a conventional main steam line plug is used, the main steam line plug must be removed in order to extract the impeller shaft 17. Furthermore, removal of this main steam line plug creates new process constraints on the main steam isolation valve 6 inspection work.

以上のように、炉内に主蒸気ラインプラグを設ける従来
技術では、その取付・取外し作業がクリティカルパスに
なるため、作業工程が長くなり、また沸騰水型原子炉の
インターナルポンプの点検に支障を来たさないための工
程的制約問題があった。また従来の主蒸気ラインプラグ
は炉内すなわち圧力容器内に設けられているので、プラ
グの取付・取外しは治具等を使用して遠隔操作を必要と
し、作業性が悪かった。
As described above, in the conventional technology of installing a main steam line plug inside the reactor, the installation and removal work becomes a critical path, which lengthens the work process and also hinders inspection of the internal pump of a boiling water reactor. There was a problem of process constraints to prevent this from occurring. Further, since the conventional main steam line plug is provided inside the furnace, that is, inside the pressure vessel, the installation and removal of the plug requires remote control using a jig or the like, resulting in poor workability.

したがって、本発明は、主蒸気隔離弁の漏洩試験が簡単
にできる方法を提供することを目的とし、更に他の目的
は、上記方法の実施に用いるに好適であり、治具などの
機器を使用することなく、簡単に着脱できる主蒸気ライ
ンプラグを提供することを目的としている。
Therefore, it is an object of the present invention to provide a method for easily performing a leak test of a main steam isolation valve, and another object of the present invention is to provide a method suitable for carrying out the above method, using equipment such as a jig. The purpose of the main steam line plug is to provide a main steam line plug that can be easily attached and detached without having to do so.

[課題を解決するための手段] 本発明は、特許請求の範囲の請求項1ないし5の夫々に
記載の主蒸気管プラグを提供し、また、これを用いた請
求項6記戦の主蒸気隔離弁漏洩試験方法を提供する。
[Means for Solving the Problems] The present invention provides a main steam pipe plug according to each of claims 1 to 5, and also provides a main steam pipe plug according to claim 6 using the main steam pipe plug. An isolation valve leak test method is provided.

[作   用コ 本発明では、原子炉圧力容器内作業(炉内作業)とは別
に並行して主蒸気隔離弁の漏洩試験ができる。すなわち
原子炉圧力容器と主蒸気隔離弁との間の主蒸気ラインに
主蒸気ライン(管)プラグを取付けることにより、主蒸
気ラインは原子炉圧力容器から切り離されるので、主蒸
気ライン(管)に空気圧を加えて、主蒸気隔離弁の漏洩
試験ができる。
[Function] In the present invention, a leakage test of the main steam isolation valve can be performed in parallel with and separately from the work inside the reactor pressure vessel (work inside the reactor). In other words, by attaching a main steam line (pipe) plug to the main steam line (pipe) between the reactor pressure vessel and the main steam isolation valve, the main steam line is separated from the reactor pressure vessel. The main steam isolation valve can be tested for leaks by applying air pressure.

以上のように、本発明によると主蒸気隔離弁の試験をク
リティカルパスである炉内作業とは切り離すことができ
、試験工程を短縮できる。しかも主蒸気ラインプラグの
着脱が炉外で実施できるので、治具などの格別の器具も
必要としない。
As described above, according to the present invention, testing of main steam isolation valves can be separated from in-furnace work, which is a critical path, and the testing process can be shortened. Moreover, since the main steam line plug can be installed and removed outside the furnace, no special equipment such as a jig is required.

主蒸気ラインプラグは、主蒸気逃し安全弁の管台に着脱
自在であるので、まず安全弁を外し、その管台に主蒸気
ラインプラグを取付けることができる。
The main steam line plug is removably attached to the nozzle stub of the main steam relief safety valve, so first the safety valve can be removed and the main steam line plug can be attached to the nozzle stub.

好ましくは主蒸気ラインプラグの本体を袋体となし、原
子炉圧力容器と主蒸気隔離弁との間の主蒸気管に、例え
ば主蒸気逃し安全弁の管台を利用して、袋体を主蒸気管
内に挿入する。そして圧力気体、例えば窒素ガスを供給
すると袋体は主蒸気管内いっばいに膨張して鎖管を閉塞
する。このようにして、前述したようにして主蒸気隔離
弁の漏洩試験ができる。プラグの取外は、袋体の流体を
放出し、体積を減少させて引き抜く。
Preferably, the body of the main steam line plug is a bag body, and the bag body is connected to the main steam pipe between the reactor pressure vessel and the main steam isolation valve using, for example, the nozzle holder of the main steam relief safety valve. Insert into the tube. When pressurized gas, for example nitrogen gas, is supplied, the bag expands all the way into the main steam pipe and closes the chain pipe. In this way, the main steam isolation valve can be leak tested as previously described. Removal of the plug releases the fluid in the bag, reduces its volume, and pulls it out.

[実 施 例] 本発明は、その実施に当っては、原子炉圧力容器と主蒸
気隔離弁との間の主蒸気ラインに設けられた任意の管台
を利用して主蒸気ラインプラグを取付けることができる
が、主蒸気逃し安全弁の管台を利用するのが便利である
。したがって、図示の実施例では主蒸気逃し安全弁の管
台に取付ける例のみが示されている。
[Embodiment] In carrying out the present invention, the main steam line plug can be attached using any nozzle stub provided in the main steam line between the reactor pressure vessel and the main steam isolation valve. However, it is convenient to use the main steam relief safety valve nozzle. Therefore, in the illustrated embodiment, only an example in which the main steam safety relief valve is attached to the nozzle stub is shown.

以下、本発明の実施例について説明する。Examples of the present invention will be described below.

さて、第1図を参照すると、炉(原子炉圧力容器)3か
らは従来のものと同様に主蒸気管(主蒸気ライン)4が
延び、この管に主蒸気隔離弁6と主蒸気逃し安全弁管台
5が設けられている。第1図には、本発明に基づき、主
蒸気ラインプラグ7を取り付けた状態が示されている。
Now, referring to Fig. 1, a main steam pipe (main steam line) 4 extends from the reactor (reactor pressure vessel) 3 as in the conventional system, and a main steam isolation valve 6 and a main steam relief safety valve are connected to this pipe. A nozzle 5 is provided. FIG. 1 shows a main steam line plug 7 installed in accordance with the present invention.

主蒸気ラインプラグ7の詳細が、第2図に示されている
。すなわち該プラグは、安全弁の管台5を挟んで両側の
管4内に挿入できるように構成されている袋体10.工
Oと、これらの袋体に流体例えば窒素ガスを供給するた
めの流体案内管9と、流体案内管を支持しているフラン
ジ8とから構成されている。その使用に際しては、主蒸
気逃し安全弁を取外した後の主蒸気逃し安全弁管台5の
開口部より袋体10,10を挿入し、主蒸気逃し安全弁
管台5とフランジ8をボルト締めにより固定する。フラ
ンジ8には、元弁11.流体案内管9、これに接続した
主蒸気管プラグ本体すなわち袋体10が取付けられてい
る。フランジ8を固定した後、窒素ガスボンベ12と空
気案内管9を接続し。
Details of the main steam line plug 7 are shown in FIG. That is, the plug is a bag body 10. which is configured to be inserted into the pipes 4 on both sides of the safety valve nozzle 5. The bag body is composed of a fluid guide pipe 9 for supplying fluid such as nitrogen gas to these bags, and a flange 8 supporting the fluid guide pipe. When using it, insert the bags 10, 10 through the opening of the main steam safety relief valve nozzle 5 after removing the main steam relief safety valve, and fix the main steam relief valve nozzle 5 and the flange 8 with bolts. . The flange 8 has a main valve 11. A fluid guide pipe 9 and a main steam pipe plug body or bag body 10 connected thereto are attached. After fixing the flange 8, the nitrogen gas cylinder 12 and the air guide pipe 9 are connected.

元弁11を開ける。これにより、窒素ガスが空気案内管
9を通り、主蒸気管プラグすなわち袋体10に導びかれ
る。主蒸気管プラグ1oは膨張し、主蒸気管4の内壁と
密着しシールを完成させる。
Open the main valve 11. Thereby, nitrogen gas is guided through the air guide pipe 9 to the main steam pipe plug or bag 10. The main steam pipe plug 1o expands and comes into close contact with the inner wall of the main steam pipe 4 to complete a seal.

ここで元弁11を全閉とし、窒素ボンベ12との接続を
切る。以上のようにして主蒸気ライン4が炉3から分離
されたら、加圧空気を上記主蒸管プラグ10と主蒸気隔
離弁6との間の主蒸気ラインに供給して、炉内作業とは
別に主蒸気隔離弁6の漏洩試験を実施することができる
At this point, the main valve 11 is fully closed and the connection with the nitrogen cylinder 12 is cut off. After the main steam line 4 is separated from the furnace 3 as described above, pressurized air is supplied to the main steam line between the main steam pipe plug 10 and the main steam isolation valve 6, and the work inside the furnace is started. Separately, a leakage test of the main steam isolation valve 6 can be performed.

第3図は上記の様な主蒸気管設置型の簡易主蒸気ライン
プラグを用いる場合の作業シーケンスを示す、同図に示
すように、炉内作業と主蒸気管関連作業は、水頭りの時
のみの関連となる。つまり、水頭りを行なう前に上記の
主蒸気ラインプラグを設置するという条件を満たすこと
により、基本的には、炉内作業と主蒸気管関連作業を並
行して行なうことが可能である。また、上記条件を満た
すことは、水頭までに十分の時間的余裕があるため、充
分に可能であり、主蒸気管側の作業はクリティカルにな
ることはない。
Figure 3 shows the work sequence when using a simple main steam line plug installed in the main steam pipe as described above. It is only relevant. In other words, by satisfying the above-mentioned condition of installing the main steam line plug before performing the water head, it is basically possible to perform the work inside the furnace and the work related to the main steam pipe in parallel. Furthermore, it is entirely possible to satisfy the above conditions because there is sufficient time to reach the water head, and the work on the main steam pipe side will not become critical.

第3図にも示されているように、本実施例によると炉内
作業においては主蒸気ラインプラグ取付は作業が不要と
なり、また主蒸気管関連作業においては主蒸気管の水抜
き作業が不要となり試験工程が大幅に短縮できる。
As shown in Fig. 3, according to this embodiment, there is no need to install a main steam line plug when working inside the furnace, and there is no need to drain water from the main steam pipe when working on main steam pipes. Therefore, the testing process can be significantly shortened.

前記プラグの取外は、逆手順で行ない、元弁11を全開
にして袋10の内圧を大気開放する。
Removal of the plug is performed in reverse order, and the main valve 11 is fully opened to release the internal pressure of the bag 10 to the atmosphere.

これにより、主蒸気管プラグ本体すなわち袋10をしぼ
ませる。そしてフランジ8のボルトを緩め、装置を取り
外す。
This causes the main steam pipe plug body, ie, the bag 10, to deflate. Then, loosen the bolts on flange 8 and remove the device.

第4図(a)、(b)に、主蒸気ラインプラグの別の実
施例を示す。本装置は、フランジ8とこれに結合した閉
塞板14で構成される。管台の位置にて主蒸気管4の内
側に、あらかじめガイド13を設置しておく。主蒸気逃
し安全弁を取外した後、主蒸気逃し安全弁管台5の開口
部より閉塞板14を主蒸気管4内のガイド13に沿って
降ろす。そしてフランジ8のボルトを締めつけ、ガイド
13と閉塞板14を密着させシールを完成させる。
FIGS. 4(a) and 4(b) show another embodiment of the main steam line plug. The device consists of a flange 8 and a closure plate 14 connected thereto. A guide 13 is installed in advance inside the main steam pipe 4 at the position of the nozzle stand. After removing the main steam relief safety valve, the closing plate 14 is lowered from the opening of the main steam relief valve stub 5 along the guide 13 in the main steam pipe 4. Then, the bolts on the flange 8 are tightened to bring the guide 13 and the closing plate 14 into close contact to complete the seal.

本実施例に係わる主蒸気ラインプラグも、第2図に示さ
れている実施例のものに準じて使用されることは明らか
である。
It is clear that the main steam line plug according to this embodiment can also be used in accordance with the embodiment shown in FIG.

[発明の効果コ 以上のように、本発明によれば、従来炉内作業としてク
リティカルパスになっていた主蒸気ラインプラグの取付
取外をクリティカルパスより外すことが可能となり、定
検工程を短縮することが出来る。また、主蒸気管関連作
業を炉内作業と並行して行うことが可能となるため、主
蒸気管関連作業に余裕ができる。
[Effects of the Invention] As described above, according to the present invention, it is now possible to remove the installation and removal of the main steam line plug from the critical path, which was traditionally a critical path for in-furnace work, thereby shortening the periodic inspection process. You can. Furthermore, since it becomes possible to perform work related to the main steam pipe in parallel with work in the furnace, there is more time for work related to the main steam pipe.

また、主蒸気ラインプラグは、構造が簡単で安価に製作
でき、また炉外の主蒸気ラインに管台を利用して取付け
られるので、治具などを用いた遠隔操作が不要で取付・
取外作業性も容易である。
In addition, the main steam line plug has a simple structure and can be manufactured at low cost, and can be installed on the main steam line outside the furnace using a nozzle stand, so there is no need for remote control using a jig or the like.
Removal workability is also easy.

更には、インターナルポンプを内臓した沸騰水型原子炉
において、インターナルポンプの点検が。
Furthermore, the internal pumps of boiling water nuclear reactors with built-in internal pumps are inspected.

主蒸気ラインプラグに干渉されることな〈実施できると
いう効果がある。
This has the advantage that it can be carried out without being interfered with by the main steam line plug.

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

第1図は本発明の1実施例の概略を示す全体的な正面図
、第2図は主蒸気ラインプラグの1実施例を示す側面図
、第3@は本発明の実施例による作業手順を示す図、第
4図(a)は主蒸気ラインプラグの他の実施例を示す側
面図、第4図(b)はその正面図、第5〜7図は従来例
を示す図で、第5図は主蒸気ラインプラグの取付けを示
す全体的正面図、第6図はその作業手順を示す図、第7
図はインターナルポンプ点検の場合の概略正面図である
。 3・・・炉(原子炉圧力容器) 4・・・主蒸気ライン(管) 5・・・主蒸気逃し安全弁の管台 6・・・主蒸気隔離弁  7・・・主蒸気ラインプラグ
8・・フランジ    9・・・流体案内管10・・・
袋体(プラグ本体) (他1名) 第 1 図 第 図 第 4 図 (0) (t)1 第 図
Fig. 1 is an overall front view showing an outline of an embodiment of the present invention, Fig. 2 is a side view showing an embodiment of a main steam line plug, and Fig. 3 shows a working procedure according to an embodiment of the present invention. 4(a) is a side view showing another embodiment of the main steam line plug, FIG. 4(b) is a front view thereof, and FIGS. 5 to 7 are views showing conventional examples. The figure is an overall front view showing the installation of the main steam line plug, Figure 6 is a diagram showing the work procedure, and Figure 7 is a diagram showing the work procedure.
The figure is a schematic front view when inspecting the internal pump. 3...Reactor (reactor pressure vessel) 4...Main steam line (pipe) 5...Main steam relief safety valve nozzle 6...Main steam isolation valve 7...Main steam line plug 8.・Flange 9...Fluid guide pipe 10...
Bag body (plug body) (1 other person) Fig. 1 Fig. 4 Fig. (0) (t) 1 Fig.

Claims (1)

【特許請求の範囲】 1 原子炉圧力容器から延在しその途中に主蒸気隔離弁
を有する主蒸気管に対して、主蒸気隔離弁よりも原子炉
圧力容器寄りの該主蒸気管の途中部位に着脱自在に取付
可能であり、該途中部位にて主蒸気管を閉塞する様に構
成した、沸騰水型原子炉の主蒸気管プラグ。2 主蒸気
管プラグは、主蒸気管の途中に設けられた管台に着脱自
在に取付可能なフランジと、該フランジから支持され且
つ主蒸気管内に位置してこれを閉塞するプラグ本体とか
らなる請求項1記載の沸騰水型原子炉の主蒸気管プラグ
。 3 プラグ本体は気体を供給されて主蒸気管内壁に当接
する様に膨む可撓性の袋体よりなる請求項2記載の沸騰
水型原子炉の主蒸気管プラグ。 4 プラグ本体は主蒸気管内に側方から挿入される閉塞
板よりなる請求項2記載の沸騰水型原子炉の主蒸気管プ
ラグ。 5 前記管台は主蒸気逃し安全弁用の管台である、請求
項2、3又は4記載の沸騰水型原子炉の主蒸気管プラグ
。 6 原子炉圧力容器から延在する主蒸気管の途中に設け
られた主蒸気隔離弁よりも原子炉圧力容器寄りの該主蒸
気管の途中部位に請求項1、2、3、4又は5記載の主
蒸気管プラグを取付けて該途中部位にて主蒸気管を閉塞
した後に、該主蒸気管プラグと主蒸気隔離弁との間の主
蒸気管に圧力気体を導入することを特徴とする、沸騰水
型原子炉の主蒸気隔離弁の漏洩試験方法。
[Scope of Claims] 1. With respect to a main steam pipe that extends from a reactor pressure vessel and has a main steam isolation valve in the middle thereof, a midway portion of the main steam pipe that is closer to the reactor pressure vessel than the main steam isolation valve. A main steam pipe plug for a boiling water reactor, which can be detachably attached to a boiling water reactor and configured to block the main steam pipe at an intermediate point. 2. The main steam pipe plug consists of a flange that can be detachably attached to a nozzle stub provided in the middle of the main steam pipe, and a plug body that is supported by the flange and located within the main steam pipe to close it. A main steam pipe plug for a boiling water nuclear reactor according to claim 1. 3. The main steam pipe plug for a boiling water nuclear reactor according to claim 2, wherein the plug body comprises a flexible bag that expands to come into contact with the inner wall of the main steam pipe when gas is supplied. 4. The main steam pipe plug for a boiling water reactor according to claim 2, wherein the plug body comprises a closing plate inserted into the main steam pipe from the side. 5. The main steam pipe plug for a boiling water reactor according to claim 2, 3 or 4, wherein the nozzle stub is a nozzle stub for a main steam relief safety valve. 6. Claim 1, 2, 3, 4, or 5 is provided in a part of the main steam pipe extending from the reactor pressure vessel that is closer to the reactor pressure vessel than the main steam isolation valve provided in the middle of the main steam pipe. After installing the main steam pipe plug and closing the main steam pipe at the midway point, pressurized gas is introduced into the main steam pipe between the main steam pipe plug and the main steam isolation valve, Leakage test method for main steam isolation valves of boiling water reactors.
JP2034698A 1990-02-15 1990-02-15 Main steam pipe plug of boiling water reactor and leak test method of main steam isolation valve using the same Expired - Fee Related JP3005234B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2034698A JP3005234B2 (en) 1990-02-15 1990-02-15 Main steam pipe plug of boiling water reactor and leak test method of main steam isolation valve using the same

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2034698A JP3005234B2 (en) 1990-02-15 1990-02-15 Main steam pipe plug of boiling water reactor and leak test method of main steam isolation valve using the same

Publications (2)

Publication Number Publication Date
JPH03238398A true JPH03238398A (en) 1991-10-24
JP3005234B2 JP3005234B2 (en) 2000-01-31

Family

ID=12421586

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2034698A Expired - Fee Related JP3005234B2 (en) 1990-02-15 1990-02-15 Main steam pipe plug of boiling water reactor and leak test method of main steam isolation valve using the same

Country Status (1)

Country Link
JP (1) JP3005234B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20220082392A (en) * 2020-12-10 2022-06-17 한국수력원자력 주식회사 Direct cooling water filling system of nuclear reactor containment building

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20220082392A (en) * 2020-12-10 2022-06-17 한국수력원자력 주식회사 Direct cooling water filling system of nuclear reactor containment building

Also Published As

Publication number Publication date
JP3005234B2 (en) 2000-01-31

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