JPH05312992A - Repair method for core structure and water seal chamber - Google Patents

Repair method for core structure and water seal chamber

Info

Publication number
JPH05312992A
JPH05312992A JP4120326A JP12032692A JPH05312992A JP H05312992 A JPH05312992 A JP H05312992A JP 4120326 A JP4120326 A JP 4120326A JP 12032692 A JP12032692 A JP 12032692A JP H05312992 A JPH05312992 A JP H05312992A
Authority
JP
Japan
Prior art keywords
shroud
chamber
reactor
pressure vessel
guide
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
JP4120326A
Other languages
Japanese (ja)
Inventor
Toshiichi Kikuchi
敏一 菊地
Sukenobu Sato
佑信 佐藤
Noriaki Wada
則明 和田
Koichi Kurosawa
孝一 黒沢
Hiroshi Tsujimura
浩 辻村
Kunio Enomoto
邦夫 榎本
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
Hitachi Nuclear Engineering Co Ltd
Original Assignee
Hitachi Ltd
Hitachi Nuclear Engineering Co 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, Hitachi Nuclear Engineering Co Ltd filed Critical Hitachi Ltd
Priority to JP4120326A priority Critical patent/JPH05312992A/en
Publication of JPH05312992A publication Critical patent/JPH05312992A/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To reduce exposure of workers by performing preventive maintenance and repair, keeping the laid in-reactor equipment in air environment and keeping the reactor chamber and the outside of small chamber filled with reactor water. CONSTITUTION:In-reactor chamber main body 8 is constituted of a guide pipe 9 for using in inserting various devices for preventive maintenance and repair and surveillance devices in the chamber, a guide 10 for insertion, an extending arm 11 capable of fixing the heads of the various devices, a placing and fixing mechanism 15 to fix the chamber main body, a gas supply pipe 12 to supply gas, a guide drive mechansim 22 and a reactor chamber control device 23.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、原子炉炉内構造物の予
防保全,補修及び取替に係り、特に、シュラウドの構造
を利用した原子炉内チャンバ及び狭あい部への追従可能
な小型チャンバの構造に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to preventive maintenance, repair and replacement of reactor internals, and more particularly to a compact reactor chamber utilizing a shroud structure and capable of following narrow spaces. It relates to the structure of the chamber.

【0002】[0002]

【従来の技術】従来の炉内構造物の取替は、給水スパー
ジャの取替工法の場合を一例として、原子炉圧力容器1
内の水を抜いた状態で作業を実施している。原子炉圧力
容器1の内面に、遮へい壁を設置し、作業者が原子炉圧
力容器1内に入り、各作業を一部の遠隔装置を利用して
実施しているのが現状である。従って、今後の原子炉炉
内構造物の予防保全,補修及び取替作業を考慮した場
合、作業者の被ばく低減も考慮した遠隔による工法を確
立する必要がある。
2. Description of the Related Art A conventional reactor pressure vessel 1 is replaced by a conventional water supply sparger replacement method, for example.
The work is carried out with the water inside drained. Under the present circumstances, a shielding wall is installed on the inner surface of the reactor pressure vessel 1, and a worker enters the reactor pressure vessel 1 and carries out each work by using some remote devices. Therefore, in consideration of preventive maintenance, repair, and replacement work of the reactor internal structure in the future, it is necessary to establish a remote construction method in consideration of reduction of exposure of workers.

【0003】[0003]

【発明が解決しようとする課題】上記従来技術は、給水
スパージャの取替工法に代表される様に遠隔による取替
工法が確立されておらず、気中状態で原子炉内からの放
射線の遮へいを遮へい体により行い、作業者の被ばく低
減が困難な状況にあった。
In the above-mentioned prior art, no remote replacement method has been established as represented by the replacement method of the water supply sparger, and the radiation from the inside of the reactor is shielded in the air. It was difficult to reduce the exposure of workers by using a shield.

【0004】本発明の目的は、シュラウド2,上部格子
板5,炉心支持板6から代表される炉心支持及び炉内構
造物の予防保全,補修及び取替作業において、原子炉の
水位を上げた状態で前記炉心支持構造物を利用して、作
業の遠隔自動化及び作業者の被ばく低減に好適な原子炉
内用チャンバを提供することにある。
An object of the present invention is to raise the water level of a nuclear reactor in preventive maintenance, repair and replacement work of a core support and a core structure represented by a shroud 2, an upper lattice plate 5 and a core support plate 6. In this state, the core support structure is utilized to provide a reactor internal chamber suitable for remote automation of work and reduction of worker exposure.

【0005】[0005]

【課題を解決するための手段】上記課題を解決するため
の本発明に係る原子炉内チャンバは、原子炉炉水を前記
原子炉圧力容器内に保持した状態で、前記原子炉圧力容
器内の前記炉心シュラウド上に取付けられた蒸気乾燥
器,シュラウドヘッド兼気水分離器等の機器、を順次,
取外し、さらに前記炉心シュラウド内の燃料集合体,制
御棒案内管等を取外し、前記炉心シュラウドの上端フラ
ンジ面及びラグを利用してチャンバ本体を設置,固定す
る。但し、本作業前に、前記原子炉圧力容器内に設置さ
れているジェットポンプ上部に位置するノズル部にシー
ルプラグを設置し、前記原子炉圧力容器内下部への流水
を防止する。次に、前記原子炉内チャンバ上部よりガス
を供給し、チヤンバ内及び前記シュラウド内下部まで気
中雰囲気とし、前記シュラウド内の気中雰囲気部に前記
原子炉内チャンバ上部より装置挿入用ガイド及び装置操
作用アームを利用して、各種装置ヘッドを挿入して、予
防保全及び補修作業等が可能となる。
A chamber in a reactor according to the present invention for solving the above-mentioned problems is provided in the reactor pressure vessel in a state where reactor water is held in the reactor pressure vessel. A steam dryer mounted on the core shroud, a device such as a shroud head and a steam separator, and the like,
Then, the fuel assembly, the control rod guide tube, and the like in the core shroud are removed, and the chamber main body is installed and fixed using the upper end flange surface and the lug of the core shroud. However, before this work, a seal plug is installed in the nozzle part located above the jet pump installed in the reactor pressure vessel to prevent running water to the lower part in the reactor pressure vessel. Next, a gas is supplied from the upper part of the chamber in the reactor to create an air atmosphere in the chamber and the lower part of the shroud, and a guide and a device for inserting the device into the air atmosphere part in the shroud from the upper part of the chamber in the reactor. Preventive maintenance and repair work can be performed by inserting various device heads using the operation arm.

【0006】また、前記シュラウドと原子炉圧力容器と
の狭あい部に、ワイヤ等により挿入可能な小型チャンバ
を前記シュラウド外壁及び原子炉圧力容器内壁を利用し
て設置し固定する。前記小型チャンバは、複数の空気袋
を利用してチャンバ内をガスの供給により気中雰囲気と
し、内部に各種装置のベッドを駆動可能な複数の駆動部
をもっている。
A small chamber that can be inserted by a wire or the like is installed and fixed in the narrow portion between the shroud and the reactor pressure vessel by using the outer wall of the shroud and the inner wall of the reactor pressure vessel. The small chamber has a plurality of driving units capable of driving the beds of various devices, with the inside of the chamber made into an air atmosphere by supplying gas using a plurality of air bags.

【0007】[0007]

【作用】本発明の原子炉内チャンバ及び小型チャンバに
よれば、既設シュラウド,シュラウドサポートシリン
ダ,シュラウドサポートレグの内面を気中雰囲気に保ち
ながら、前記原子炉内チャンバの外側を炉水の入った状
態で、シュラウド,シュラウドサポートシリンダ,シュ
ラウドサポートレグ,上部格子板,炉心支持板等の炉内
構造物の予防保全,補修等の装置を、原子炉内チャンバ
上部より装置挿入ガイド及び装置操作用アームを利用し
て挿入することにより、予防保全,補修等の信頼性向上
及び作業者の被ばく低減が図れる。
According to the reactor internal chamber and the small chamber of the present invention, reactor water enters the outside of the reactor internal chamber while keeping the inner surfaces of the existing shroud, shroud support cylinder, and shroud support leg in the air atmosphere. In this state, the equipment for preventive maintenance and repair of internal structures such as the shroud, shroud support cylinder, shroud support leg, upper lattice plate, core support plate, etc. is installed from the upper part of the chamber in the reactor to the equipment insertion guide and the equipment operation arm. By inserting by using, it is possible to improve the reliability of preventive maintenance and repair, and reduce the exposure of workers.

【0008】本発明の小型チャンバによれば、既設シュ
ラウドの外側及び原子炉圧力容器の内側の一部分のみを
気中雰囲気にした後、その部分の予防保全,補修等の信
頼性向上及び作業者の被ばく低減が図れる。
According to the small chamber of the present invention, only the outside of the existing shroud and part of the inside of the reactor pressure vessel are put into the atmospheric atmosphere, and then the reliability of preventive maintenance, repair, etc. of the part is improved and the operator's reliability is improved. The exposure can be reduced.

【0009】[0009]

【実施例】以下、本発明の一実施例を図1ないし図6に
より説明する。図1は、本実施例で用いる原子炉内チャ
ンバの全体構成図の一例及び小型チャンバの挿入した状
態を示す。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS. FIG. 1 shows an example of the overall configuration of an internal reactor chamber used in this embodiment and a state in which a small chamber is inserted.

【0010】本実施例は、原子炉内チャンバ本体8をシ
ュラウド2のフランジ面に設置,固定し、原子炉内チャ
ンバ本体8の上部のガイドパイプ9より伸縮アーム11
が任意位置に固定され、また、シュラウド2の外側に伸
縮アーム11と同位置に小型チャンバ本体24が設置さ
れている場合である。同図では、原子炉圧力容器1を断
面とし、本発明の原子炉内チャンバ本体8及び小型チャ
ンバ本体24に、直接、関係のある原子炉炉内構造物の
シュラウド2,シュラウドサポードシリンダ3,シュラ
ウドサポートレグ4,上部格子板5,炉心支持板6,ジ
ェットポンプ7のみを示したものである。
In this embodiment, the reactor internal chamber body 8 is installed and fixed on the flange surface of the shroud 2, and the telescopic arm 11 is extended from the guide pipe 9 above the reactor internal chamber body 8.
Is fixed at an arbitrary position, and the small chamber body 24 is installed outside the shroud 2 at the same position as the telescopic arm 11. In the same figure, the reactor pressure vessel 1 is shown as a cross section, and the shroud 2, shroud support cylinder 3, 3 of the reactor internal structure directly related to the reactor internal chamber body 8 and the small chamber body 24 of the present invention. Only the shroud support leg 4, the upper lattice plate 5, the core support plate 6, and the jet pump 7 are shown.

【0011】従って、その他の原子炉炉内構造物である
蒸気乾燥器,気水分離器,シュラウドヘッド,燃料集合
体等は除いている。
Therefore, the steam dryers, steam separators, shroud heads, fuel assemblies, etc., which are other internal reactor structures, are excluded.

【0012】原子炉内チャンバ本体8は、予防保全及び
補修等の各種装置及び監視装置をチャンバ内に挿入する
場合に使用するガイドパイプ9,挿入用ガイド10,各
種装置のヘッドを固定可能な伸縮アーム11,チャンバ
本体を固定する装置固定機構15,ガスを供給するガス
供給用パイプ12,ガイド駆動機構22,原子炉チャン
バ制御装置23より構成される。原子炉内チャンバ本体
8の取扱いは、原子炉水位をシュラウド2等における予
防保全、又は、補修対象箇所以下にした状態で、専用吊
り具又は、既原子力発電プラントに準備してある吊り具
を、吊り具ロッド16および原子炉圧力容器1内に設置
されているガイドロッドを利用して、シュラウド2の上
部フランジ部に位置決め固定する。次に、ガス供給用パ
イプ12からドライガスを供給しながら原子炉水位を原
子炉圧力容器1のフランジ下まで上げて、シュラウド2
の内面を気中雰囲気とする。但し、この時、シュラウド
2内への炉水流入防止のために、原子炉圧力容器1内に
設置されているジェットポンプ7のノズル部へのシール
プラグ、及び、再循環配管部の弁の閉止等を行った状態
で実施する。なお、予防保全および補修作業において、
シュラウド2の外壁側も気中雰囲気にする必要がある場
合には、小型チャンバ本体24をあらかじめ設置し、チ
ャンバ内を気中雰囲気状態としておく。原子炉内チャン
バ本体8および小型チャンバ本体24内に異常がないこ
とを、監視カメラ及び照明33等により確認後、伸縮ア
ーム11の先端に各種装置を取付けガイドパイプ9,挿
入用ガイド10を利用して、予防保全または、補修対象
箇所へ原子炉内チャンバ制御装置23によりガイド駆動
機構22を動作させて、位置決め、固定を行う。その
後、予防保全または、補修作業を実施する。なお、各種
装置の挿入,位置決め,固定および引き抜き等の動作監
視は、監視カメラおよび照明33等により行う。また、
原子炉内チャンバ本体8は、ガイドパイプ9からの各種
装置およびケーブル等の出入れ作業時を考慮して、原子
炉圧力容器1のフランジ面に、サービスプラットホーム
32を取付けられる構造としている。
The in-reactor chamber main body 8 is a telescopic unit that can fix the guide pipe 9, insertion guide 10 and heads of various devices used for inserting various devices for preventive maintenance and repair and monitoring devices into the chamber. It comprises an arm 11, a device fixing mechanism 15 for fixing the chamber body, a gas supply pipe 12 for supplying gas, a guide drive mechanism 22, and a reactor chamber control device 23. As for the handling of the chamber body 8 in the reactor, with the preventive maintenance of the reactor water level in the shroud 2 or the like, or in a state where the repair target is equal to or lower than the repair target part, a dedicated suspender or a suspender prepared in the existing nuclear power plant, The suspender rod 16 and the guide rod installed in the reactor pressure vessel 1 are used for positioning and fixing to the upper flange portion of the shroud 2. Next, while supplying dry gas from the gas supply pipe 12, the reactor water level is raised to below the flange of the reactor pressure vessel 1, and the shroud 2
The inside is made to be an air atmosphere. However, at this time, in order to prevent the reactor water from flowing into the shroud 2, the seal plug to the nozzle portion of the jet pump 7 installed in the reactor pressure vessel 1 and the valve of the recirculation piping portion are closed. It is carried out in the state where the above has been done. In preventive maintenance and repair work,
When the outer wall side of the shroud 2 also needs to be in the air atmosphere, the small chamber body 24 is installed in advance and the inside of the chamber is kept in the air atmosphere state. After confirming that there is no abnormality in the reactor main body 8 and the small chamber main body 24 by the monitoring camera and the illumination 33, various devices are attached to the tip of the telescopic arm 11 using the guide pipe 9 and the insertion guide 10. Then, the guide drive mechanism 22 is operated by the in-reactor chamber control device 23 to the preventive maintenance or repair target position, and positioning and fixing are performed. After that, preventive maintenance or repair work is performed. It should be noted that operation monitoring such as insertion, positioning, fixing and pulling out of various devices is performed by the monitoring camera, the illumination 33 and the like. Also,
The in-reactor chamber body 8 has a structure in which the service platform 32 can be attached to the flange surface of the reactor pressure vessel 1 in consideration of the operation of putting in and out various devices and cables from the guide pipe 9.

【0013】図2は、原子炉内チャンバ本体8の構成図
を示す。挿入用ガイド10は、ガイドパイプ9内を位置
精度良く、また、スムーズに挿入可能な様に、ガイド補
助パッド17を複数個配置した構造としている。伸縮ア
ーム11部の動作は、エアシリンダ駆動からなるアーム
振り上げ機構18およびエアシリンダ、または、電気モ
ータ駆動からなる伸縮機構,電気モータ駆動からなるガ
イド駆動機構22により各種方向への駆動が可能であ
る。また、各種装置ヘッドをアーム固定用ヘッド19に
取付けシュラウド2の内壁に押付けながら作業が可能で
ある。シュラウド2の上部フランジとの水シール機構2
1は、Oリングとガスの供給によるシール機構とし、装
置固定機構15は、シュラウド2のラグ部との間をエア
シリンダ駆動等により締め付けを可能とし、装置据付時
に原子炉圧力容器1内に設置してあるガイドロッドを据
付ガイドとして利用できる様に、ガイドブロック34を
備えた構造としている。次に、監視カメラ及び照明33
は、原子炉内チャンバ本体8内の全体的な監視をするた
めに、チャンバ内に複数個設置し、回転および首振り駆
動を遠隔操作により可能な構造としている。尚、アーム
固定用ヘッド19に取付ける各種装置ヘッドには、それ
ぞれ専用の監視カメラおよび照明を取付ける構造として
いる。
FIG. 2 is a block diagram of the chamber body 8 in the nuclear reactor. The insertion guide 10 has a structure in which a plurality of guide auxiliary pads 17 are arranged so that the guide pipe 9 can be inserted into the guide pipe 9 with high positional accuracy and smoothly. The operation of the telescopic arm 11 can be driven in various directions by an arm swing-up mechanism 18 and an air cylinder driven by an air cylinder, or a telescopic mechanism driven by an electric motor, and a guide drive mechanism 22 driven by an electric motor. .. Further, it is possible to attach various device heads to the arm fixing head 19 and press them against the inner wall of the shroud 2. Water seal mechanism 2 with upper flange of shroud 2
Reference numeral 1 denotes a sealing mechanism by supplying an O-ring and gas, and a device fixing mechanism 15 enables tightening between the lug portion of the shroud 2 by driving an air cylinder or the like, and is installed in the reactor pressure vessel 1 when the device is installed. The guide block 34 is provided so that the existing guide rod can be used as an installation guide. Next, surveillance camera and lighting 33
In order to monitor the entire inside of the chamber body 8 in the nuclear reactor, a plurality of them are installed in the chamber, and rotation and swing drive can be performed by remote control. It should be noted that each device head attached to the arm fixing head 19 has a structure in which a dedicated surveillance camera and a dedicated illumination are attached.

【0014】図3は、本実施例で用いる小型チャンバの
全体構成図の一例を示す。本実施例は、シュラウド2と
原子炉圧力容器1の間より挿入,固定し、シュラウド2
の任意の外面部を予防保全,補修等の作業を実施する場
合の縦断面を示す。
FIG. 3 shows an example of the overall configuration of a small chamber used in this embodiment. In this embodiment, the shroud 2 is inserted and fixed between the shroud 2 and the reactor pressure vessel 1, and
The vertical cross section is shown when performing work such as preventive maintenance and repair on any outer surface of the.

【0015】小型チャンバ本体24は、装置全体をワイ
ヤ等により吊り下げ方式により挿入し、装置の概略位置
決め用推進器36,装置を固定する固定用パッド25,
チャンバ前面に位置する開口部への炉水をシールするた
めの水シール用空気袋26,チャンバ前面の開口部の開
閉を自在可能でチャンバ内への炉水をシールするための
開口部水シール用空気袋27,各種装置ヘッドの複数軸
の駆動が可能な駆動機構28,チャンバ内へドライガス
を供給するガス供給口29,ガスを排除するガス排除口
30,チャンバ内の全体的な監視をするための監視カメ
ラ及び照明35,小型チャンバ制御装置31より構成さ
れる。小型チャンバ本体24の取扱いは、予防保全また
は、補修対象箇所が気中および水中状態でも取付けが可
能な構造としている。水中状態における一例を図4,5
により説明する。図4は、シュラウド2と原子炉圧力容
器1の任意の箇所へ挿入する場合の縦断面を示す。図5
は、任意の箇所へ位置決め、固定した場合の平面図を示
す。チャンバを任意の箇所へ挿入する場合、開口部水シ
ール用空気袋27に空気を供給してガイドバー37をガ
イドに上方向へふくらませた状態で炉水をシールし、ガ
ス供給口29によりドライガスを供給しながらチャンバ
内を気中状態で、チャンバの上下,左右に複数個配置し
た推進器36の推力により任意の位置へ移動することが
可能な構造としている。チャンバの位置決め,固定は、
エアシリンダ駆動からなる固定用パッド25により行
い、その後、チャンバ前面に複数個配置した水シール用
空気袋26に空気を供給してふくらませ炉水をシールし
た状態で、チャンバ内面に配置した水シール用空気袋2
7の空気を抜くことにより縮めることが可能な構造とし
ている。この状態で、各種装置ヘッドを取付けた駆動機
構28を小型チャンバ制御装置31により遠隔操作に
て、予防保全または、補修作業を実施する。尚、チャン
バ内の異常監視および各種装置ヘッドの動作監視は、チ
ャンバ内に設置して回転および首振り駆動が可能な監視
カメラおよび照明35により行う。
The small chamber body 24 is inserted into the small chamber main body 24 with a wire or the like by a suspending method, and a propulsion device 36 for roughly positioning the device, a fixing pad 25 for fixing the device,
Air bag 26 for water sealing for sealing the reactor water to the opening located in the front of the chamber, for opening the water sealing for sealing the reactor water in the chamber which can be opened and closed freely An air bag 27, a drive mechanism 28 capable of driving a plurality of axes of various device heads, a gas supply port 29 for supplying a dry gas into the chamber, a gas exclusion port 30 for excluding the gas, and an overall monitoring of the inside of the chamber. It is composed of a monitoring camera and lighting 35, and a small chamber control device 31. The small chamber body 24 is handled such that it can be attached for preventive maintenance or even when the repair target is in the air or underwater. An example underwater condition
Will be explained. FIG. 4 shows a vertical cross section when the shroud 2 and the reactor pressure vessel 1 are inserted into arbitrary positions. Figure 5
Shows a plan view when positioning and fixing to an arbitrary place. When inserting the chamber into an arbitrary position, air is supplied to the opening water sealing air bag 27 to seal the reactor water in a state where the guide bar 37 is bulged upward with the guide, and the dry gas is supplied by the gas supply port 29. While the chamber is being supplied with air, the structure is such that it can be moved to any position by the thrust of a plurality of propulsion devices 36 arranged above and below and to the left and right of the chamber. Positioning and fixing the chamber
Performed by a fixing pad 25 that is driven by an air cylinder, and then supplies air to a plurality of water sealing air bags 26 that are arranged on the front surface of the chamber to inflate and seal the reactor water. Air bag 2
It has a structure that can be shortened by removing the air in 7. In this state, the drive mechanism 28 to which various device heads are attached is remotely operated by the small chamber control device 31 to perform preventive maintenance or repair work. It should be noted that abnormality monitoring in the chamber and operation monitoring of various apparatus heads are performed by a monitoring camera and an illumination 35 which are installed in the chamber and can rotate and swing.

【0016】[0016]

【発明の効果】本発明の原子炉内チャンバ及び小型チャ
ンバによれば、既設のシュラウド内外面及び上部格子
板,炉心支持板,シュラウドサポートシリンダ,シュラ
ウドサポートレグ等を気中雰囲気に保ちながら、該原子
炉内チャンバ及び小型チャンバの外側を炉水の入った状
態で、予防保全,補修等の信頼性向上及び作業者の被ば
く低減が図れる。
According to the chamber and small chamber of the present invention, while maintaining the inside and outside surfaces of the existing shroud, the upper lattice plate, the core support plate, the shroud support cylinder, the shroud support leg, etc. in the air atmosphere, It is possible to improve the reliability of preventive maintenance and repairs and reduce the exposure of workers while the reactor water and the small chamber are filled with reactor water.

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

【図1】本発明の一実施例による原子炉内チャンバの断
面図。
FIG. 1 is a sectional view of a chamber in a nuclear reactor according to an embodiment of the present invention.

【図2】原子炉内チャンバの断面図。FIG. 2 is a sectional view of a chamber in a nuclear reactor.

【図3】小型チャンバの補修作業状態の横断面図。FIG. 3 is a cross-sectional view of a small chamber in a repair work state.

【図4】小型チャンバの補修作業状態の平面図。FIG. 4 is a plan view of a repair work state of a small chamber.

【図5】小型チャンバの原子炉内への挿入状態の横断面
図。
FIG. 5 is a transverse cross-sectional view of a small chamber inserted into a nuclear reactor.

【符号の説明】[Explanation of symbols]

1…原子炉圧力容器、2…シュラウド、3…シュラウド
サポートシリンダ、4…シュラウドサポートレグ、5…
上部格子板、6…炉心支持板、7…ジェットポンプ、8
…原子炉内チャンバ本体、9…ガイドパイプ、10…挿
入用ガイド、11…伸縮アーム、12…ガス供給用パイ
プ、13…下部固定用リング、14…上部固定用リン
グ、15…装置固定機構、16…吊り具ロッド、17…
ガイド補助パッド、18…アーム振り上げ機構、22…
ガイド駆動機構、23…原子炉内チャンバ制御装置、2
4…小型チャンバ本体。
1 ... Reactor pressure vessel, 2 ... Shroud, 3 ... Shroud support cylinder, 4 ... Shroud support leg, 5 ...
Upper lattice plate, 6 ... Core support plate, 7 ... Jet pump, 8
... Reactor chamber body, 9 ... Guide pipe, 10 ... Insertion guide, 11 ... Telescopic arm, 12 ... Gas supply pipe, 13 ... Lower fixing ring, 14 ... Upper fixing ring, 15 ... Device fixing mechanism, 16 ... Hanging tool rod, 17 ...
Guide assist pad, 18 ... Arm raising mechanism, 22 ...
Guide drive mechanism, 23 ... Reactor chamber control device, 2
4 ... Small chamber body.

フロントページの続き (72)発明者 佐藤 佑信 茨城県日立市幸町三丁目2番2号 日立ニ ュークリアエンジニアリング株式会社内 (72)発明者 和田 則明 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 黒沢 孝一 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 辻村 浩 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 榎本 邦夫 茨城県土浦市神立町502番地 株式会社日 立製作所機械研究所内Front Page Continuation (72) Inventor Yunobu Sato 3-2-2 Sachimachi, Hitachi City, Ibaraki Prefecture Hitachi New Engineering Co., Ltd. (72) Noriaki Wada 3-1-1, Saiwaicho, Hitachi City, Ibaraki Prefecture No. 1 Hitachi Ltd., Hitachi Works (72) Inventor Koichi Kurosawa 3-1-1, Saiwai-cho, Hitachi, Ibaraki Hitachi Ltd. Hitachi Works, Hitachi (72) Inventor, Hiroshi Tsujimura Saiwaicho, Hitachi, Ibaraki 3-1-1, Hitachi Ltd., Hitachi Works (72) Inventor, Kunio Enomoto, 502, Kamidate-cho, Tsuchiura-shi, Ibaraki Hiritsu Seisakusho Co., Ltd.

Claims (4)

【特許請求の範囲】[Claims] 【請求項1】原子炉圧力容器の炉心部及び炉心下部に取
付けられる炉心支持及び炉内構造物の予防保全,補修及
び取替において、前記原子炉圧力容器内のシュラウド上
及び前記シュラウド内に取付けられた取外し可能な機器
を取外し、前記シュラウドの上部フランジ面を利用して
水シールチャンバを設置し、前記原子炉の水位を前記原
子炉圧力容器のフランジ下部まで上げた状態でも、前記
シュラウド内への炉水の流入をガスの封入等により阻止
して、前記シュラウド内全面を気中状態に保持しながら
前記水シールチヤンバの上部より挿入した各種装置によ
り、前記シュラウド内の全面及び設置してある前記炉心
支持構造物の前記予防保全,補修及び取替作業を水中遠
隔にてできるようにしたことを特徴とする炉内構造物の
補修方法。
1. A shroud inside a reactor pressure vessel and a shroud within a reactor pressure vessel for preventive maintenance, repair and replacement of core support and core internals attached to the core and lower part of the reactor pressure vessel. Even if the removable equipment is removed and a water seal chamber is installed using the upper flange surface of the shroud, and the water level of the reactor is raised up to the lower part of the flange of the reactor pressure vessel, the water is introduced into the shroud. The inflow of reactor water is blocked by enclosing gas, etc., and various devices inserted from the upper part of the water seal chamber while keeping the entire inside of the shroud in the air are installed on the entire inside of the shroud and installed. A method for repairing an in-core structure, characterized in that the preventive maintenance, repair and replacement work of a core support structure can be performed remotely underwater.
【請求項2】請求項1において、前記シュラウドの上部
フランジ部に前記原子炉圧力容器内壁に取付けられてい
るガイドロッド及び前記シュラウド上部に取付けてある
ブラケット,ラグを利用して据付けるためのガイドブロ
ック及び装置固定機構を設け、前記シュラウド内全面を
気中状態に保持するための水シール機構,ガス供給用パ
イプと各種装置及びケーブル等の出し入れに必要なガイ
ドパイプ,挿入用ガイド及び各種装置を取付けて任意の
位置へ動作可能な伸縮アーム,ガイド駆動機構を設け、
前記水シールチャンバ内全面の監視が可能な監視カメ
ラ,照明を兼ね備えている原子炉内チャンバ。
2. The guide according to claim 1, wherein a guide rod is attached to an inner wall of the reactor pressure vessel at an upper flange portion of the shroud, and a bracket and a lug are attached to an upper portion of the shroud. A block and a device fixing mechanism are provided, and a water sealing mechanism for keeping the entire inside of the shroud in the air, a gas supply pipe and various devices, and a guide pipe necessary for putting in and out a cable, an insertion guide and various devices are provided. Provided with a telescopic arm that can be attached to move to any position and a guide drive mechanism,
A monitoring chamber that can monitor the entire surface of the water seal chamber and a chamber inside the reactor that also has lighting.
【請求項3】請求項1において、前記原子炉圧力容器と
シュラウドの間の狭あい部にワイヤ等の吊り下げにより
挿入可能であり、チャンバ内を気中状態にするために複
数の空気袋から構成される水シール機構を備え、複数の
推進器の推力により任意の位置に移動可能であり、位置
決め,固定するための固定機構を備えている小型チャン
バ。
3. The device according to claim 1, which can be inserted into the narrow portion between the reactor pressure vessel and the shroud by suspending a wire or the like, and from a plurality of air bags for putting the chamber into an air state. A small chamber that has a water seal mechanism that is configured, can be moved to any position by the thrust of multiple thrusters, and has a fixing mechanism for positioning and fixing.
【請求項4】請求項3において、前記小型チャンバ内
に、各種装置ヘッドを取付け可能とし、ヘッドを任意の
位置へ駆動する駆動機構を備え、前記チャンバ内全面の
監視をするための監視カメラ,照明を兼ね備えて、前記
水シールチャンバと同時または、単独で前記シュラウド
等の外面を前記予防保全,補修及び取替作業を水中遠隔
で可能とした小型チャンバ。
4. A surveillance camera for monitoring the entire surface of the chamber according to claim 3, further comprising a drive mechanism capable of mounting various device heads in the small chamber and driving the heads to arbitrary positions. A small chamber that also has illumination and that enables the preventive maintenance, repair, and replacement of the outer surface of the shroud and the like simultaneously or independently with the water seal chamber underwater remotely.
JP4120326A 1992-05-13 1992-05-13 Repair method for core structure and water seal chamber Pending JPH05312992A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4120326A JPH05312992A (en) 1992-05-13 1992-05-13 Repair method for core structure and water seal chamber

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4120326A JPH05312992A (en) 1992-05-13 1992-05-13 Repair method for core structure and water seal chamber

Publications (1)

Publication Number Publication Date
JPH05312992A true JPH05312992A (en) 1993-11-26

Family

ID=14783490

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4120326A Pending JPH05312992A (en) 1992-05-13 1992-05-13 Repair method for core structure and water seal chamber

Country Status (1)

Country Link
JP (1) JPH05312992A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20110051878A1 (en) * 2009-08-31 2011-03-03 Hitachi-Ge Nuclear Energy, Ltd. Method for Managing Internal Equipment in Reactor Pressure Vessel and Apparatus Thereof

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20110051878A1 (en) * 2009-08-31 2011-03-03 Hitachi-Ge Nuclear Energy, Ltd. Method for Managing Internal Equipment in Reactor Pressure Vessel and Apparatus Thereof
US8687758B2 (en) * 2009-08-31 2014-04-01 Hitachi-Ge Nuclear Energy, Ltd. Method for managing internal equipment in reactor pressure vessel and apparatus thereof

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