JPS5926100A - Method of dismantling reactor - Google Patents

Method of dismantling reactor

Info

Publication number
JPS5926100A
JPS5926100A JP57135571A JP13557182A JPS5926100A JP S5926100 A JPS5926100 A JP S5926100A JP 57135571 A JP57135571 A JP 57135571A JP 13557182 A JP13557182 A JP 13557182A JP S5926100 A JPS5926100 A JP S5926100A
Authority
JP
Japan
Prior art keywords
reactor
drive mechanism
dismantling
center
control 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.)
Granted
Application number
JP57135571A
Other languages
Japanese (ja)
Other versions
JPS6341519B2 (en
Inventor
正人 白井
修 橋本
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.)
Toshiba Corp
Mitsui Engineering and Shipbuilding Co Ltd
Mitsui Zosen KK
Original Assignee
Mitsui Engineering and Shipbuilding Co Ltd
Tokyo Shibaura Electric Co Ltd
Mitsui Zosen KK
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 Mitsui Engineering and Shipbuilding Co Ltd, Tokyo Shibaura Electric Co Ltd, Mitsui Zosen KK filed Critical Mitsui Engineering and Shipbuilding Co Ltd
Priority to JP57135571A priority Critical patent/JPS5926100A/en
Publication of JPS5926100A publication Critical patent/JPS5926100A/en
Publication of JPS6341519B2 publication Critical patent/JPS6341519B2/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

  • Processing Of Solid Wastes (AREA)
  • Arc Welding In General (AREA)

Abstract

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

Description

【発明の詳細な説明】 杢発明は原子炉の解体方法、より詳しくは原子炉の内部
に切断トーチを配置し、該切断トーチを遠隔操作により
移動させて原子炉本体または該本体内部に設けられてい
る附属物を切断するようにした原子炉の解体方法に関す
るものである。
[Detailed Description of the Invention] The present invention provides a method for dismantling a nuclear reactor, more specifically, a method for dismantling a nuclear reactor, and more specifically, a method for dismantling a nuclear reactor, in which a cutting torch is disposed inside the reactor, and the cutting torch is moved by remote control. This article relates to a method for dismantling a nuclear reactor that involves cutting off the attached parts.

近来、発電所においては原子炉の開発が進むにつれて運
転効率の悪くなった原子炉を解体する必要に迫られ、こ
の解体方法が検討されている。
BACKGROUND ART In recent years, as the development of nuclear reactors has progressed at power plants, it has become necessary to dismantle reactors whose operating efficiency has deteriorated, and methods of dismantling these reactors are being considered.

ところで、かかる原子炉はそれ自体が高レベルの放射性
廃棄物であるため作業員が直接原子炉に接近もしくは内
部に入って解体作業を行うことが出来ず、必然的に遠隔
操作によらなければならない。そしてこの遠隔操作によ
る解体装置は軽量かつ小型化することが実用上重大であ
るO このようなことから炉内に存在する燃料棒や制御棒また
は炉の内壁に配置されている各種配管類ヤシエツトポン
プディフューザー等の附属物を切断除去したのち炉本体
を炉内に配置した切断トーチにより切断することが考え
られる。
By the way, since such nuclear reactors themselves are high-level radioactive waste, workers cannot directly approach or enter the reactor to dismantle it, and must necessarily use remote control. . In practical terms, it is important that this remote-controlled dismantling equipment be lightweight and compact.For this reason, the fuel rods and control rods present in the reactor, as well as the various pipes and pipes located on the inner wall of the reactor, are important for practical purposes. It is conceivable that after accessories such as a pump diffuser are cut and removed, the furnace body is cut using a cutting torch placed inside the furnace.

しかしながらこのように炉本体内に切断トーチを配置す
ると目視出来なくなるため該切断トーチの位置制御は困
難である。
However, when the cutting torch is disposed within the furnace body in this manner, it is difficult to control the position of the cutting torch because it cannot be visually observed.

本発明者等は、かかる点に鑑み鋭意検討した結果、原子
炉本体が円筒形をなしていることおよびその底部に設け
られている制御棒駆動機構ハウジング群の内一つは原子
炉本体の中心に配置されている点に着目し、本発明をな
すに到った。
As a result of intensive studies in view of the above points, the present inventors have determined that the reactor body has a cylindrical shape and that one of the control rod drive mechanism housing groups provided at the bottom of the reactor body is located at the center of the reactor body. The present invention was developed by paying attention to the fact that

即ち炉内の燃料と制御棒を取り除いたのち、該炉内の底
部に残存する制御棒駆動機構用ハウジング群の円中心に
存在する制御棒駆動機構ハウジングに下端を支持しかつ
その上部を炉中心に保持した支持棒を中心として切断ト
ーチを移動させながら少なくとも炉内壁に設けられた附
属物を切断するようにした原子炉の解体方法を提供せん
、七するものである。
That is, after the fuel and control rods in the reactor are removed, the lower end is supported by the control rod drive mechanism housing that exists at the center of the circle of the control rod drive mechanism housing group remaining at the bottom of the reactor, and the upper part is supported at the center of the reactor. The present invention provides a method for dismantling a nuclear reactor, in which at least an accessory provided on the inner wall of the reactor is cut while moving a cutting torch around a support rod held in the reactor.

以下図面に基づき本発明の一実施例を説明する。An embodiment of the present invention will be described below based on the drawings.

第1図は本発明の方法を実施するための装置を原子炉に
設置した状態を示す断面図である。
FIG. 1 is a sectional view showing a state in which an apparatus for carrying out the method of the present invention is installed in a nuclear reactor.

原子炉Aは、図示しない上部半球部と円筒部taと、そ
の下方に形成された半球部すよりなる本体1と、その半
球部bK複数本植立された制御棒駆動機構のハウジング
2と、円筒部aの内壁に設けられた配管6と、前記円筒
部aと半球部すとの境目に設けられたバッファープレー
ト4とこのバッファープレート4上に設けられたジェッ
トポンプディフューザー5の如き附属物と、内部に配置
された燃料部6および制御棒7等により構成されている
The reactor A includes a main body 1 consisting of an upper hemisphere and a cylindrical part ta (not shown), a hemisphere formed below the hemisphere, a housing 2 for a control rod drive mechanism in which a plurality of hemispheres bK are installed, A pipe 6 provided on the inner wall of the cylindrical portion a, a buffer plate 4 provided at the boundary between the cylindrical portion a and the hemispherical portion, and accessories such as a jet pump diffuser 5 provided on the buffer plate 4. , a fuel section 6, a control rod 7, etc. arranged inside.

そして制御棒駆動機構ハウジング2内の−っの制御棒駆
動機構用ハウジング2aは本体1の中心に配置されてい
ると共に配管6やジェットポンプディフューザー5は本
体1の内壁に沿って複数個設けられている。
The control rod drive mechanism housing 2a in the control rod drive mechanism housing 2 is arranged at the center of the main body 1, and a plurality of piping 6 and jet pump diffusers 5 are provided along the inner wall of the main body 1. There is.

本発明を実施するための装置は、回転式ガーダ−8と伸
m俸9と、先端にプラズマアークトーチ10を有する揺
動腕11とにより構成されている。
The apparatus for carrying out the present invention is composed of a rotary girder 8, an extension arm 9, and a swinging arm 11 having a plasma arc torch 10 at its tip.

詳述すれば回転式ガーダ−8の下部周縁には複数個のロ
ーラー12が取り付けられており、該ローラ12の内部
なくとも一つにはモーターの如き駆動装置16が連結さ
れている。
Specifically, a plurality of rollers 12 are attached to the lower peripheral edge of the rotary girder 8, and a drive device 16 such as a motor is connected to at least one of the rollers 12 inside.

そして回転式ガーダ−8の中心にはテレスコピックに形
成された伸縮棒9を懸吊すると共にその上部には前記伸
縮棒9を伸縮させるための上下駆動機構14が設けられ
ている。
A telescopically formed telescopic rod 9 is suspended from the center of the rotary girder 8, and a vertical drive mechanism 14 for extending and contracting the telescopic rod 9 is provided above the rod.

伸縮棒9の下端には第2図に示すように下部にテーパー
15aを有する支持部15が設けられ、伸縮棒9を下降
させた時その先端が制御棒駆動機構用ハウジング2aの
中に入り易いようになっている。
As shown in FIG. 2, the lower end of the telescoping rod 9 is provided with a support portion 15 having a taper 15a at the bottom, so that when the telescoping rod 9 is lowered, its tip easily enters the control rod drive mechanism housing 2a. It looks like this.

先端にブラズーマアークトーチ10を有する揺動腕11
はリンク機構で少なくとも上下方向に屈曲可能なように
構成されると共に伸縮棒9に取付部材16により取付け
られている。この取付部材16は必要に応じて着脱可能
としてもよく、また上下に移動可能なように構成しても
よい。
A swinging arm 11 having a Blazuma arc torch 10 at its tip
is constructed such that it can be bent at least in the vertical direction by a link mechanism, and is attached to the telescopic rod 9 by an attachment member 16. The mounting member 16 may be detachable as required, or may be configured to be movable up and down.

かかる構成において今原子炉Aを解体しようとする場合
、まず公知の手段により図示しない上部半球部、燃料部
6および制御棒部7を取り除いたのち回転式ガーダ−8
をクレーン等により円筒部aの上縁羨乗せる。これによ
り支持棒9の上部は本体1の中心に保持される。かかる
位置から上下駆動機構14を作動させ伸縮棒9の先端を
下降させてたテーパ一部15aを制御棒駆動機構用ハウ
ジング2aに挿入し、固定する。
If reactor A is to be dismantled with this configuration, first the upper hemisphere, fuel section 6 and control rod section 7 (not shown) are removed by known means, and then the rotary girder 8 is removed.
is placed on the upper edge of the cylindrical part a using a crane or the like. As a result, the upper part of the support rod 9 is held at the center of the main body 1. From this position, the vertical drive mechanism 14 is operated to lower the tip of the telescopic rod 9, and the tapered portion 15a is inserted into the control rod drive mechanism housing 2a and fixed.

しかる後、揺動腕11を作動させてプラズマアークトー
チ10を被切断箇所へ位置させ切断を開始すると共に、
駆動装置16を駆動すると回転式カー ター 8 カ回
転するためプラズマアークトーチ10を伸縮棒9を中心
として水平方向に円弧移動させるのである。この場合、
本体1の内壁に設けられた配管6やバッファープレート
4 更にはジェットポンプディフューザー5等の附属物
が先ず切断され、図示しないマニピレータにより切断片
が炉外へ取り出されたのち本体1を構成する円筒部aを
切断するのがよい。
Thereafter, the swinging arm 11 is operated to position the plasma arc torch 10 to the location to be cut and start cutting,
When the drive device 16 is driven, the rotary carter 8 rotates, so that the plasma arc torch 10 is moved in an arc in the horizontal direction around the telescopic rod 9. in this case,
The piping 6, buffer plate 4, jet pump diffuser 5, and other accessories provided on the inner wall of the main body 1 are first cut, and the cut pieces are taken out of the furnace by a manipulator (not shown). It is better to cut a.

第3図および第4図は伸縮棒9の上部保持機構の別の実
施例を示すものであって、ドーナツ状保持部材21の少
なくとも三方に油圧等により伸縮自在な保持腕26と傘
歯車22を有する駆動装置26とが設けられると共に中
央部には傘歯車24を有する油圧装置25が回転可能な
如く取付けられている。かかる保持機構によれば、各保
持腕26の油圧源を同一にすれば容易に伸縮棒9の上部
を、、;’、1の中心に合せることができる。
FIGS. 3 and 4 show another embodiment of the upper holding mechanism for the telescopic rod 9, in which holding arms 26 and bevel gears 22 are provided on at least three sides of the donut-shaped holding member 21, which are extendable and retractable by hydraulic pressure or the like. A hydraulic device 25 having a bevel gear 24 is rotatably attached to the center thereof. According to such a holding mechanism, if the oil pressure source for each holding arm 26 is made the same, the upper part of the telescopic rod 9 can be easily aligned with the center of .

こOノ保持機構の場合伸縮棒9の下端に設けられる支持
部15には回転を円滑に行うためボールベアリング等を
設けることが好ましい。
In the case of this O-holding mechanism, it is preferable that the support portion 15 provided at the lower end of the telescoping rod 9 is provided with a ball bearing or the like to ensure smooth rotation.

以上の説明のように本発明によれば、本体内部中心に配
置された制御棒駆動機構ハウジング2aを基準として伸
縮棒9を配置するため、その芯合せは極めて容易であり
かつ予め揺動腕11の取付部材16の取り付は高さを切
断箇所の高さに合せてセットしておくことによりプラズ
マアークトーチ10の位置合せは迅速かつ容易である。
As described above, according to the present invention, since the telescoping rod 9 is arranged with reference to the control rod drive mechanism housing 2a arranged at the center inside the main body, the alignment is extremely easy, and the swing arm 11 By setting the height of the mounting member 16 to match the height of the cutting location, alignment of the plasma arc torch 10 is quick and easy.

特に本体1と回忌的な円弧を有する附属物を切断する場
合は最初の切断位置にプラズマアークトーチ10をセッ
トすれば単に伸縮棒9を回転させるだけでよいためその
効果は大きい。
Particularly when cutting an appendage that has an arc that is similar to the main body 1, setting the plasma arc torch 10 at the initial cutting position is very effective as it is only necessary to rotate the telescopic rod 9.

勿論本発明は前記実施例に限定されるものではない。本
発明の重要な点は炉底部中心に残存する制御棒駆動機構
用ハウジングを利用して伸縮棒と本体の芯合せを行ない
この伸縮棒を基にして切断トーチを移動制御するという
技術的思想にある。従ってかかる思想を逸脱しない範囲
で種々の変更ができることは明らかである。
Of course, the present invention is not limited to the above embodiments. The important point of the present invention is the technical concept of aligning the telescopic rod and the main body using the housing for the control rod drive mechanism that remains at the center of the furnace bottom, and controlling the movement of the cutting torch based on this telescopic rod. be. Therefore, it is clear that various changes can be made without departing from this concept.

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

第1図は本発明の方法を実施するための装置を原子炉に
設置した状態を示す断面図、第2図は第1図C部拡大断
面図、第3図および第4図は本発明の方法を実施するた
めの伸縮棒の上部を保持する他の装置の説明図で、第3
図は平面図であり、第4図は第3図B−Biにおける断
面図である。 1・Φ本体、2.2a・・バッファープレート、5@争
ジエツトポンプデイフユーザー、6・・燃料部、7・・
制御棒部、 8・・回転式ガーダ−19・・伸縮棒、10・・プラズ
マアークトーチ、11・・揺動腕、15・・支持部、2
1・・保持部材、26・・保持腕、A・・原子炉、a・
・円筒部、b・・半球部。 第3図       第4図 手続補正書(方式) 特許庁長官殿 ′“”″′“+1251“1、事件の表
示 昭和57に1・特許願 第13557]82、発明の名
称 原子炉の解体方法 3、補正をする者 jG1′1..!:の関係 特許出願人4、代 理 人
Fig. 1 is a sectional view showing the state in which an apparatus for carrying out the method of the present invention is installed in a nuclear reactor, Fig. 2 is an enlarged sectional view of section C in Fig. 1, and Figs. FIG. 3 is an illustration of another device for holding the upper part of the telescopic rod for carrying out the method;
The figure is a plan view, and FIG. 4 is a sectional view taken along the line B-Bi in FIG. 3. 1. Φ body, 2.2a.. buffer plate, 5 @ conflict jet pump differential user, 6.. fuel section, 7..
Control rod part, 8... Rotating girder 19... Telescopic rod, 10... Plasma arc torch, 11... Swinging arm, 15... Support part, 2
1. Holding member, 26. Holding arm, A.. Nuclear reactor, a.
- Cylindrical part, b... Hemispherical part. Figure 3 Figure 4 Procedural amendment (method) Mr. Commissioner of the Japan Patent Office '""'"+1251"1, Indication of the case 1980 1/Patent application No. 13557] 82, Name of the invention Method for dismantling a nuclear reactor 3 , the person making the amendment jG1'1...!: Patent applicant 4, agent

Claims (1)

【特許請求の範囲】[Claims] 炉内の燃料部と制御棒部を取り除いたのち、該炉内の底
部に残存する制御棒駆動機構用ハウジング群の内、中心
に存在す不制御俸駆動機構用ハウジングに下端を支持し
、かつその上部を炉中心に保持した支持体を中心として
切断トーチを移動させながら少なくとも炉内壁に設けら
れた附属物を切断するようにしたことを特徴とする原子
炉の解体方法。
After removing the fuel part and the control rod part in the reactor, the lower end of the control rod drive mechanism housing group remaining at the bottom of the reactor is supported by the uncontrolled salary drive mechanism housing in the center, and A method for dismantling a nuclear reactor, characterized in that at least an accessory provided on an inner wall of the reactor is cut while a cutting torch is moved around a support whose upper part is held at the center of the reactor.
JP57135571A 1982-08-03 1982-08-03 Method of dismantling reactor Granted JPS5926100A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57135571A JPS5926100A (en) 1982-08-03 1982-08-03 Method of dismantling reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57135571A JPS5926100A (en) 1982-08-03 1982-08-03 Method of dismantling reactor

Publications (2)

Publication Number Publication Date
JPS5926100A true JPS5926100A (en) 1984-02-10
JPS6341519B2 JPS6341519B2 (en) 1988-08-17

Family

ID=15154923

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57135571A Granted JPS5926100A (en) 1982-08-03 1982-08-03 Method of dismantling reactor

Country Status (1)

Country Link
JP (1) JPS5926100A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4813313A (en) * 1985-11-25 1989-03-21 Kabushiki Kaisha Kobe Seiko Sho Apparatus for demolishing a reactor shield wall
JP5681318B1 (en) * 2014-08-05 2015-03-04 田中 光 Method for dismantling a damaged reactor core

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4813313A (en) * 1985-11-25 1989-03-21 Kabushiki Kaisha Kobe Seiko Sho Apparatus for demolishing a reactor shield wall
JP5681318B1 (en) * 2014-08-05 2015-03-04 田中 光 Method for dismantling a damaged reactor core

Also Published As

Publication number Publication date
JPS6341519B2 (en) 1988-08-17

Similar Documents

Publication Publication Date Title
WO1987003325A1 (en) Reactor shielding wall dismantling apparatus
CN112647697A (en) Construction platform for housing construction engineering
CN209801119U (en) port crane operation monitoring support
JPS5926100A (en) Method of dismantling reactor
US3370888A (en) Furnace refractory delining apparatus
FI111244B (en) Load Orientation Device
JPS6043573A (en) Method and apparatus for cutting concrete structure
JPS62260999A (en) Erector device for extension shield
CN208009615U (en) A kind of blowdown pipe network inspection shaft, septic tank, underwater salvage handgrip of removing contamination
CN212825485U (en) Hollow joint with fixing effect
CN210968791U (en) Detachable temporary support for constructional engineering construction
JP2934578B2 (en) Lining construction equipment and construction method using it
CN216889818U (en) Hoisting equipment for maintaining gas underground pressure regulating tank
JPH0521534Y2 (en)
JPS6332945B2 (en)
JP2006143445A (en) Climbing type jib crane
JPH08200682A (en) Replacing apparatus for burner
JPS62125165A (en) Apparatus for constructing inner wall of cylindrical structure
JP2640562B2 (en) Tube tower dismantling device
CN208008351U (en) A kind of portable instrument for workboat installs hoisting apparatus
JPH0640672Y2 (en) Excavation equipment for extracting existing piles
JPS60188895A (en) Maintenance device for pump
JPS6232992Y2 (en)
JPS6126479Y2 (en)
JP2769152B2 (en) Steel pipe cutting equipment