JPH0766079B2 - Reactor internal structure dismantling system by plasma arc cutting technology - Google Patents
Reactor internal structure dismantling system by plasma arc cutting technologyInfo
- Publication number
- JPH0766079B2 JPH0766079B2 JP1154124A JP15412489A JPH0766079B2 JP H0766079 B2 JPH0766079 B2 JP H0766079B2 JP 1154124 A JP1154124 A JP 1154124A JP 15412489 A JP15412489 A JP 15412489A JP H0766079 B2 JPH0766079 B2 JP H0766079B2
- Authority
- JP
- Japan
- Prior art keywords
- cutting
- blower
- internal structure
- reactor
- water
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
- 238000005520 cutting process Methods 0.000 title claims description 75
- 238000005516 engineering process Methods 0.000 title description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 22
- 239000007787 solid Substances 0.000 claims description 12
- 230000004927 fusion Effects 0.000 claims 1
- 230000008018 melting Effects 0.000 claims 1
- 238000002844 melting Methods 0.000 claims 1
- 238000012544 monitoring process Methods 0.000 claims 1
- 239000007789 gas Substances 0.000 description 18
- 239000003570 air Substances 0.000 description 17
- 238000000034 method Methods 0.000 description 12
- 238000011084 recovery Methods 0.000 description 10
- 210000000078 claw Anatomy 0.000 description 9
- 230000002285 radioactive effect Effects 0.000 description 7
- 239000006227 byproduct Substances 0.000 description 4
- 230000003028 elevating effect Effects 0.000 description 4
- 239000000843 powder Substances 0.000 description 4
- 239000000126 substance Substances 0.000 description 4
- 238000011109 contamination Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 238000000746 purification Methods 0.000 description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- 230000001174 ascending effect Effects 0.000 description 2
- 238000007667 floating Methods 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 238000004804 winding Methods 0.000 description 2
- 239000012080 ambient air Substances 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 239000006185 dispersion Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- -1 ferrous metals Chemical class 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
Landscapes
- Arc Welding In General (AREA)
Description
【発明の詳細な説明】 (産業上の利用分野) 本発明は、プラズマアーク切断技術を用いて原子炉炉内
構造物を解体するシステムに関するものである。Description: TECHNICAL FIELD The present invention relates to a system for disassembling internal structures of a nuclear reactor by using a plasma arc cutting technique.
(従来技術) 原子力発電プラントは、長期使用の後、寿命を迎え原子
炉炉内構造物も他の機器と共に解体する必要が生じる。
解体する技術は、いくつか存在するが、プラズマアーク
切断技術もその内の1つである。(Prior Art) A nuclear power plant will reach the end of its life after long-term use, and it will be necessary to dismantle the reactor internals together with other equipment.
There are several techniques for dismantling, but the plasma arc cutting technique is one of them.
プラズマアーク切断技術は、従来原子炉炉内構造物の主
要構成材料であるステンレス鋼及び非鉄金属等を切断す
る技術として利用されてきたが、放射化した原子炉炉内
構造物の解体用としての技術でなかったため、原子炉炉
内構造物からの放射能被曝低減及び切断時に発生するガ
ス及び放射化切断粉を回収する等のシステム化は考慮さ
れていない。The plasma arc cutting technology has been used as a technology for cutting stainless steel and non-ferrous metals, which are the main constituent materials of the reactor internals, but for the dismantling of activated nuclear reactor internals. Since this was not a technology, systemization such as reduction of radiation exposure from reactor internals and collection of gas and activated cutting powder generated during cutting was not considered.
(発明が解決しようとする課題) 原子炉炉内構造物は、放射化あるいは放射能汚染してい
るため、解体作業を進める場合、作業員の放射線被曝低
減のため解体する炉内構造物を水中でしかも遠隔で解体
作業が必要となる。また、プラズマアーク切断技術で水
中切断を行うと切断のために供給するガス及び水分解に
よって発生する水素等のガスが水面に上昇するのにとも
なって炉内構造物の切断粉の一部が水面からでて気中浮
遊物となる。また、切断粉の一部は水中に残り水中浮遊
物となり、一部はドロスとなって原子炉圧力容器の底部
に落下する。これら切断に伴う副次生成物の対策等が必
要になる。そこで、原子炉炉内構造物をプラズマアーク
切断技術を用いて解体する場合、これら切断副次生成物
の回収を含む問題点を解決するシステムが必要となる。(Problems to be solved by the invention) Since the reactor internals are activated or radioactively contaminated, the reactor internals to be dismantled underwater to reduce the radiation exposure of workers when disassembling work is underway. Moreover, dismantling work is required remotely. In addition, when performing underwater cutting with the plasma arc cutting technology, as the gas supplied for cutting and the gas such as hydrogen generated by water decomposition rise to the water surface, part of the cutting powder of the reactor internals It becomes a floating substance in the air. Further, a part of the cutting powder remains in the water and becomes a suspended matter in the water, and a part of the cutting powder becomes dross and falls to the bottom of the reactor pressure vessel. It is necessary to take measures against by-products accompanying these cuttings. Therefore, when disassembling the reactor internals using the plasma arc cutting technique, a system that solves the problems including the recovery of these cutting byproducts is required.
原子炉炉内構造物を解体するシステムを考える場合、原
子炉施設という限られたスペースで必要な機能を有した
各機器を効率よく配置することおよび全体の効率をあげ
るため、各装置にどのような方式を採用するかが重要に
なってくる。When considering a system for disassembling the internal structure of a nuclear reactor, how should each device be installed in order to efficiently arrange the equipment that has the necessary functions in the limited space of the nuclear reactor facility and increase the overall efficiency? It is important to adopt such a method.
例えば、トーチを保持し炉内構造物を切断する切断駆動
装置において、切断対象が上部から下部の炉内構造物に
移るに従って切断位置は、下方に移る。この場合トーチ
の移動ストロークが短い装置であれば、短いストローク
をカバーするため、クレーン等で切断駆動装置を下げて
切断位置にトーチを設定する方式の場合、移動の都
度、切断駆動装置と炉内構造物の相対位置が変わり移動
後の両者の相対位置の確認が難しい、従って炉内構造物
に沿わせてトーチを移動する切断動作を行わせることが
困難となる、切断駆動装置全体が作業員と切断対象物
の間になり、作業員が切断位置等を観察するのに、視界
が切断駆動装置で範囲が狭くなる、切り離された炉内
構造物は、切断駆動装置を回避して、原子炉圧力容器か
ら取り出すことはできず、切断駆動装置を一度引き上げ
移動する作業が伴う。For example, in a cutting drive device that holds a torch and cuts the internal furnace structure, the cutting position moves downward as the cutting target moves from the upper part to the lower internal structure. In this case, if the device has a short torch movement stroke, it covers the short stroke.Therefore, in the case of the method of lowering the cutting drive device with a crane or the like to set the torch at the cutting position, the cutting drive device and the furnace should be moved every time it moves. The relative position of the structure changes and it is difficult to confirm the relative position of the two after the movement. Therefore, it becomes difficult to perform the cutting operation of moving the torch along the in-core structure. And the object to be cut, the field of view is narrowed by the cutting drive device for the worker to observe the cutting position, etc. It cannot be taken out from the furnace pressure vessel, and the work of pulling up and moving the cutting drive device once is involved.
(課題を解決するための手段) 本発明は、プラズマアーク切断技術を用いて原子炉炉内
構造物を安全かつ効率よく解体するシステムを提供する
ものである。(Means for Solving the Problem) The present invention provides a system for safely and efficiently disassembling the internal structure of a nuclear reactor by using a plasma arc cutting technique.
本発明によるプラズマアーク切断技術による原子炉炉内
構造物解体システムは、原子炉圧力容器の上部に設置し
た走行及び横行駆動が可能な装置の上部に旋回ならびに
昇降可能な昇降軸の下端にトーチを取り付けた切断駆動
装置、放射化した炉内構造物を切断する際に発生する放
射性の気中浮遊物を含んだ発生ガスを回収する発生ガス
回収処理装置、放射性の落下ドロス及び水中浮遊固形物
を回収処理する水浄化装置及び切断する際に炉内構造物
を保持固定するとともに切断後には切り離された炉内構
造物を搬送する切断物保持固定搬送装置からなってい
る。またこれらを用いて原子炉炉内構造物を解体する作
業等を監視する監視カメラを有している。The reactor internal structure dismantling system by the plasma arc cutting technology according to the present invention is a system in which a torch is installed at the upper part of the reactor pressure vessel and is capable of turning and ascending and descending at the lower end of an elevating shaft capable of ascending and descending. The attached cutting drive device, the generated gas recovery processing device that collects the generated gas containing the radioactive air suspended matter generated when cutting the activated reactor internals, the radioactive falling dross and the suspended solids in water. It comprises a water purifying device for recovery processing and a cut object holding / fixing / conveying device for holding and fixing the in-reactor internal structure at the time of cutting and for conveying the separated in-reactor internal structure after cutting. It also has a surveillance camera that monitors the work such as dismantling the reactor internals using these.
従って、第1〜6図のようなシステムが必要となる。Therefore, the system shown in FIGS. 1 to 6 is required.
切断駆動装置3は、圧力容器1内より広い開口部を有す
る作業床と同じレベルに設置し、長い昇降軸21を有する
方式として切断片を取りだす際には昇降軸21を分割上昇
したウエル部87まで移動し、切断装置全体を動かすこと
なく切断片取り出し作業が実施できるようにして、作業
の効率化円滑化を図る。The cutting drive device 3 is installed at the same level as the working floor having an opening wider than the pressure vessel 1, and has a long lifting shaft 21. When the cut piece is taken out, the lifting shaft 21 is divided and lifted up to a well portion 87. Move to the position where the cutting piece can be taken out without moving the entire cutting device, and work efficiency will be improved.
切断時に発生する副次生成物はできるだけ発生場所で回
収し、既設系統への放射能汚染拡大を防止する方式を採
用している。By-products generated at the time of cutting are collected as much as possible at the place where they are generated, and a method is adopted to prevent the spread of radioactive contamination to the existing system.
切断時に発生する気中浮遊固形物及び水素ガスを回収す
る発生ガス回収処理装置4については、原子炉上部の開
口部に設置し、その内側径は、原子炉圧力容器の外徑よ
り大きく、切断駆動装置3の切断動作及び切り離された
炉内構造物2を搬出する際の妨げとならないようにして
いる。また本装置は、給気系統及びフィルターを通過し
て排気する系統を有するエアーカーテン方式を採用して
できるだけ放射性の気中浮遊固形物がエアーカーテンよ
り上部に拡散することを防止し、汚染機器の減少を図っ
ている。The generated gas recovery processing device 4 for recovering airborne solid matter and hydrogen gas generated at the time of cutting is installed in the opening of the upper part of the reactor, and its inner diameter is larger than the outer diameter of the reactor pressure vessel. It is arranged so as not to interfere with the cutting operation of the driving device 3 and the carrying out of the separated furnace internal structure 2. In addition, this device adopts an air curtain system that has an air supply system and a system that exhausts air through a filter to prevent radioactive airborne solids from diffusing above the air curtain as much as possible, and We are trying to reduce.
切断時に発生する水中浮遊物及び落下ドロスを回収する
水浄化装置については、構成機器のポンプ、ストレー
ナ、フィルターを一体に組み込んだ機器及び水中浮遊固
形物及び落下ドロスを回収時に使用するホースなどは、
切断駆動装置の切断動作を妨げないようにウエル部に設
置または仮置し、水中浮遊物等で満杯になったストレー
ナ及びフィルターは、作業員の被曝低減を考慮止して遠
隔で交換できる方式を採用している。Regarding the water purification device that collects suspended solids and falling dross generated during cutting, equipment such as pumps, strainers, filters that incorporate components, and hoses that collect suspended solids and falling dross when collecting water are
The strainer and filter installed or temporarily placed in the well part so as not to interfere with the cutting operation of the cutting drive device and filled with underwater floating materials, etc. can be replaced remotely in consideration of reducing the exposure of workers. It is adopted.
切断終了時の切り離された炉内構造物の落下を防止する
ための保持固定と取り出し機能を兼ねた切断物保持固定
搬送装置7については、同装置を炉内構造物2に設定す
る際には炉内構造物2を内側に置き切断物保持固定搬送
装置7を炉内構造物2の外側に置くように設定し、狭い
原子炉圧力容器1と炉内構造物2の間を避けて切断対象
の炉内構造物2の内側から切断動作が行える方式を採用
している。Regarding the cut object holding / fixing / conveying device 7 having a holding and fixing function and a take-out function for preventing the fall of the separated in-core structure at the end of cutting, when the device is set to the in-core structure 2, It is set so that the internal reactor structure 2 is placed inside and the cut object holding / fixing / conveying device 7 is placed outside the internal reactor structure 2 to avoid cutting between the narrow reactor pressure vessel 1 and the internal reactor structure 2. The method that can perform the cutting operation from the inside of the furnace internal structure 2 is adopted.
(発明の効果) 本発明は、放射線量率の高い炉内構造物を水中で切断解
体することから作業員の被曝の低減化、発生した放射性
の副次生成物を解体場所で回収する機能を有することか
ら既設処理系への放射能汚染拡大防止及び原子炉上部に
設置した切断駆動装置を移動しないで切断物を搬出で
き、また、原子炉圧力容器の下部に設置されている炉内
構造物を切断する際に長く継ぎ足した昇降軸を分割して
引き上げないで損傷したトーチを交換できるなどの解体
作業の効率化を考慮した装置で原子炉炉内構造物を安全
に解体するのに効果的なシステムである。(Effect of the invention) The present invention reduces the exposure of workers by cutting and dismantling the internal structure of a reactor having a high radiation dose rate in water, and has the function of recovering the generated radioactive byproduct at the dismantling site. Since it has, it prevents the spread of radioactive contamination to the existing treatment system and can carry out the cut products without moving the cutting drive device installed in the upper part of the reactor, and the internal structure installed in the lower part of the reactor pressure vessel. It is effective for safely dismantling the reactor internals with a device that takes into consideration the efficiency of dismantling work, such as replacing the torch that has been extended for a long time when cutting, and replacing the damaged torch without pulling it up. System.
(実施例) 次に本発明の一実施例について説明する。(Example) Next, an example of the present invention will be described.
第1図は、プラズマアーク切断技術による原子炉炉内構
造物を解体するシステムの全体図であって、原子炉圧力
容器1内に設置されている炉内構造物2を切断駆動装置
3で切断し、切断時に発生するガス及び気中浮遊物は、
発生ガス回収処理装置4で回収し、水中浮遊物及び落下
ドロスは、水浄化装置5で回収する。切断片6は、切断
片保持固定搬送装置7で切断中は保持固定し、切断後は
保持固定搬送装置7と共にクレーン8で搬出する。な
お、原子炉圧力容器1の上部には、覆い9があって、発
生ガス回収処理装置4で回収できない発生ガス及び気中
浮遊物の拡散を防止している。FIG. 1 is an overall view of a system for disassembling a reactor internal structure by a plasma arc cutting technique, in which the reactor internal structure 2 installed in a reactor pressure vessel 1 is cut by a cutting drive device 3. However, the gas and airborne substances generated during cutting are
The generated gas recovery processing device 4 collects the suspended solids and the dross in water. The cutting piece 6 is held and fixed by the cutting piece holding and fixing conveying device 7 during cutting, and is carried out by the crane 8 together with the holding and fixing conveying device 7 after cutting. A cover 9 is provided on the upper part of the reactor pressure vessel 1 to prevent diffusion of generated gas and airborne substances that cannot be recovered by the generated gas recovery processing device 4.
第2図は、切断駆動装置3を示す図であり、これには水
平面を駆動する駆動用の走行駆動装置10(走行駆動機構
11と走行ガイドレール12からなる)と、走行ガイドレー
ル12の上に走行駆動装置10と直交する駆動を行う横行駆
動装置13(横行駆動機構14と横行ガイドレール15からな
る)と、横行駆動装置13の上部にある旋回駆動装置16
(旋回駆動機構17と旋回テーブル18からなる)とがあっ
て、旋回テーブル18と共に昇降駆動装置19(昇降駆動機
構20、昇降軸21及び昇降ガイドレール22からなる)全体
を旋回する。昇降駆動機構20は、昇降軸21を昇降し、昇
降軸の先端部26にはトーチ23を取り付けてあってトーチ
23により炉内構造物2を切断する。各々の駆動機構につ
いては、走行駆動機構11と横行駆動機構14はボールスク
リュウ24・ボールナット25駆動であり、旋回駆動機構17
はピニオン・ギヤー駆動であり、昇降駆動機構20はピニ
オン・ラック駆動であり、それぞれモータによって駆動
する。各駆動装置は、数値制御方式を採用し速度と位置
を任意に制御でき、制御する駆動装置の組合せによって
炉内構造物2を切断する場合の切断経路及び速度を任意
に選択することができる。昇降軸21は、すでに提出して
いる特許出願にかかる分割繋ぎ足し方式である。なおト
ーチ23を取り付けている昇降軸先端部26は、作業床から
遠隔で取り外し、引き上げてトーチ23を交換することが
できる。FIG. 2 is a diagram showing the cutting drive device 3, in which a traveling drive device 10 for driving a horizontal surface (travel drive mechanism) is shown.
11 and a traveling guide rail 12), a traverse driving device 13 (consisting of a traverse driving mechanism 14 and a traverse guide rail 15) that drives the traveling guide rail 12 orthogonally to the traveling drive device 10, and a traverse driving device. Swing drive 16 on top of 13
(Consisting of a swivel drive mechanism 17 and a swivel table 18) and swivels the swivel table 18 together with the lifting drive device 19 (comprising a lifting drive mechanism 20, a lifting shaft 21, and a lifting guide rail 22). The lifting drive mechanism 20 moves the lifting shaft 21 up and down, and the torch 23 is attached to the tip 26 of the lifting shaft.
The furnace internal structure 2 is cut by 23. Regarding each drive mechanism, the traveling drive mechanism 11 and the traverse drive mechanism 14 are driven by the ball screw 24 and the ball nut 25, and the swing drive mechanism 17 is used.
Is a pinion gear drive, and the lift drive mechanism 20 is a pinion rack drive, each driven by a motor. Each drive unit adopts a numerical control method and can arbitrarily control the speed and position, and a cutting path and a speed for cutting the in-core structure 2 can be arbitrarily selected by a combination of controlling drive units. The elevating shaft 21 is a split-and-joint system according to the patent application already submitted. The lifting shaft tip 26 to which the torch 23 is attached can be removed remotely from the work floor and pulled up to replace the torch 23.
第3図は、トーチ23を取り付けている昇降軸先端部26を
作業床から遠隔で取り外す機構を示す図であって、昇降
軸先端部26取り外し機構全体27は、ワイヤー28で吊下げ
られており、昇降軸21をガイドとして切断駆動装置上部
に設置してある手巻ウインチ29によって巻き上げ及び巻
下げを行う。FIG. 3 is a view showing a mechanism for remotely removing the lifting shaft tip end portion 26 to which the torch 23 is attached from the work floor. The lifting shaft tip end portion 26 removing mechanism 27 is entirely suspended by a wire 28. The hoisting and lowering shaft 21 is used as a guide to wind up and down by a hand winding winch 29 installed above the cutting drive device.
昇降軸先端部取り外し機構全体27を所定の位置まで巻下
げた後、ポール30をピン31にセット回転するとロッド32
を中心として矢印33の方向に爪34が旋回、爪34は昇降軸
先端部26にセットされる。さらにポール30をピン35にセ
ットし、ポール30を回転するとピン35を中心として矢印
36の方向に爪先端部37が回り昇降軸先端部26をつかむ。
エアーシリンダー38にエアーを供給すると、エアーシリ
ンダー38内のピストン39とピストン39に連結しているロ
ッド40及びロッド40と連結しているブロック41が上昇す
る。ブロック41には4個のピン42があり、ピン42もブロ
ック41とともに上昇する。ピン42が爪43の長孔に差し込
まれており、ピン42の上昇によって爪43はピン44を支店
として矢印45の方向に回転し、爪43は昇降先端部26から
外れる。爪43が昇降軸先端部26から外れるとブロック41
がリミットスイッチから離れて作動して、爪43が昇降軸
先端部26から外れたことをランプで表示する。その後ポ
ール30をピン31にセットし、矢印33と反対にポールを回
しロッド32を中心として爪34及び爪先端部37で掴んだ昇
降軸先端部26を昇降軸21の中心からずらし、昇降軸先端
部26とともに昇降軸先端部取り外し機構27を手巻ウイン
チ29で巻き上げる。After the entire lifting mechanism 27 for lifting the lifting shaft is wound down to the specified position, the pole 30 is set to the pin 31 and rotated to rotate the rod 32.
The claw 34 swivels in the direction of the arrow 33 around the center, and the claw 34 is set on the tip end portion 26 of the elevating shaft. Further, set the pole 30 to the pin 35 and rotate the pole 30 to make the arrow center around the pin 35.
The claw tip portion 37 turns in the direction of 36 and grips the lifting shaft tip portion 26.
When air is supplied to the air cylinder 38, the piston 39 in the air cylinder 38, the rod 40 connected to the piston 39, and the block 41 connected to the rod 40 rise. The block 41 has four pins 42, and the pin 42 also rises together with the block 41. The pin 42 is inserted into the long hole of the claw 43, and the claw 43 is rotated in the direction of the arrow 45 by using the pin 44 as a branch by the ascent of the pin 42, and the claw 43 is disengaged from the elevating tip 26. When the claw 43 comes off the lifting shaft tip 26, the block 41
Is operated away from the limit switch, and a lamp indicates that the pawl 43 has come off the lifting shaft tip 26. After that, the pole 30 is set on the pin 31, and the pole is turned in the opposite direction of the arrow 33 to shift the lifting shaft tip 26 gripped by the claw 34 and the claw tip 37 around the rod 32 from the center of the lifting shaft 21 to move the lifting shaft tip. The lifting shaft tip end removing mechanism 27 is wound up together with the portion 26 by a hand winding winch 29.
第4図は、発生ガス回収処理装置4を示す図であって、
送風系統49(送風機50、送風ダクト51及び送風ダクト出
口52からなる)と排風系統53(排風ダクト入口54、排風
ダクト55、フィルター56及び排風機57からなる)から構
成される。送風機50により送られた空気は、送風ダクト
51を通り送風ダクト出口52から吹き出される。吹き出さ
れた空気は、排風機57により、発生ガス、気中浮遊物及
び周囲の空気と共に排風ダクト入口54から吸引され発生
ガスを希釈するとともにこれらの気体の流れにより原子
炉上部の開口部にエアーカーテンを形成し作業床などへ
の気中浮遊物の拡散を減少させる。また、排風ダクト入
口54から吸引された空気及び発生ガス並びに気中浮遊物
は、排風ダクト55を通りフィルター56で気中浮遊物を回
収したのち排風機57より原子炉施設の既設排気系統60へ
吸引される。FIG. 4 is a diagram showing the generated gas recovery processing device 4,
It is composed of a blower system 49 (consisting of a blower 50, a blower duct 51 and a blower duct outlet 52) and an exhaust system 53 (consisting of an exhaust duct inlet 54, an exhaust duct 55, a filter 56 and a blower 57). The air sent by the blower 50 is blown by the blower duct.
It is blown out from the ventilation duct outlet 52 through 51. The blown air is sucked by the exhaust fan 57 together with the generated gas, suspended solids and ambient air from the exhaust duct inlet 54 to dilute the generated gas, and the flow of these gases causes the gas to flow into the opening in the upper part of the reactor. An air curtain is formed to reduce the dispersion of airborne substances on the work floor. Further, the air and the generated gas and air suspended matter sucked from the exhaust air duct inlet 54 pass through the air exhaust duct 55 and are collected by the filter 56, and then the air blower 57 is used to install the existing exhaust system of the reactor facility. Sucked to 60.
第5図は、水浄化装置5を示す図であって、水中浮遊固
形物あるいは、落下ドロスは、ポンプ61により、大口径
吸引ヘッド62または、小口径吸引ヘッド63より水ととも
に吸引され、ストレーナケーシング64に流入する。落下
ドロス等の大きな粒子がストレーナ65で過された後、
ベース66内の通路67を通りポンプ61からポンプ出口管68
を経て、フィルター入口69からフィルター70に流入す
る。フィルター70で水中浮遊固形物等の小さな粒子が
過され浄化された水はフィルター出口71から流出する。
落下ドロスで満杯になったストレーナ65は、ストレーナ
ケーシング64の蓋71をフックなどで開きストレーナ吊具
72を利用してワイヤーを掛け、第1図のクレーン8で吊
上げて交換する。目詰りを起こしたフィルター70は、ポ
ールをフィルターケーシング旋回ピン73にセットしたフ
ィルターケーシング74を旋回させる。フィルターケーシ
ングピン75とフィルター固定プレート切り欠き76が一致
した所でフィルター吊具77を利用してワイヤーを掛けフ
ィルターケーシング74を吊上げて交換する。FIG. 5 is a view showing the water purifying device 5, in which suspended solids in water or falling dross are sucked together with water by the large-diameter suction head 62 or the small-diameter suction head 63 by the pump 61, and the strainer casing. Inflow to 64. After large particles such as falling dross have been passed through the strainer 65,
Pump outlet pipe 68 from pump 61 through passage 67 in base 66
And then flows into the filter 70 from the filter inlet 69. The water that has been purified by the filter 70 containing small particles such as suspended solids in water flows out from the filter outlet 71.
The strainer 65, which has been filled with falling dross, opens the lid 71 of the strainer casing 64 with a hook or the like and is a strainer hanger.
Use 72 to hang a wire, and lift it with the crane 8 in Fig. 1 to replace it. The clogged filter 70 swivels the filter casing 74 with the pole set on the filter casing swiveling pin 73. When the filter casing pin 75 and the filter fixing plate cutout 76 are aligned with each other, the filter casing 77 is used to hang wires to suspend the filter casing 74 for replacement.
第6図は、切断物保持固定搬送装置7を示す図であっ
て、切断物保持固定搬送装置7の吊具78にワイヤー79を
掛け第1図のクレーン8によって炉内構造物2を内側に
して切断物保持固定搬送装置7を降ろす。その後、水圧
で駆動する8本の脚80を原子炉圧力容器1に押し付け切
断物保持固定搬送装置7を固定した後、水流で回転する
ドリル81をピストン82で矢印83の方向に押し付け炉内構
造物2を貫通して炉内構造物2と切断物保持固定搬送装
置7を固定する。炉内構造物2と切断物保持固定搬送装
置7を固定したのち、ワイヤー79を取り外し炉内構造物
2を第1図の切断駆動装置3で切断する。切断後ワイヤ
ー79を吊具78に掛け吊った後8本の脚80を引っ込め切断
物保持固定搬送装置7を原子炉圧力容器1から外し、切
り離された炉内構造物2とともに切断物保持固定搬送装
置7を吊上げる。吊上げ後、切り離された炉内構造物2
と切断物保持固定搬送装置7は、第1図の水中の通路84
を通過して第1図のプール85に置いた後、ドリル81を抜
いて切断物保持固定搬送装置7を切断片から取り外し引
き上げ、次の炉内構造物を切断する際の保持・固定・搬
送に再使用する。FIG. 6 is a view showing the cut object holding / fixing / conveying device 7, in which the wire 79 is hung on the lifting tool 78 of the cut object holding / fixing / conveying device 7 to move the internal structure 2 to the inside by the crane 8 of FIG. Then, the cut object holding / fixing / conveying device 7 is lowered. After that, eight legs 80 driven by water pressure are pressed against the reactor pressure vessel 1 to fix the cut object holding and fixing transfer device 7, and then a drill 81 rotating by a water flow is pressed by a piston 82 in a direction of an arrow 83, and a reactor internal structure The in-furnace internal structure 2 and the cut object holding / fixing and conveying device 7 are fixed by penetrating the object 2. After fixing the in-furnace internal structure 2 and the cut object holding / fixing / conveying device 7, the wire 79 is removed and the in-furnace internal structure 2 is cut by the cutting drive device 3 in FIG. After cutting, the wire 79 is hung from the suspending device 78 and then the eight legs 80 are retracted, and the cut object holding / fixing / conveying device 7 is removed from the reactor pressure vessel 1 and the cut object holding / fixing / conveying is carried out together with the separated reactor internal structure 2. Lift the device 7. Inner structure 2 separated after lifting
The cut object holding / fixing / conveying device 7 has an underwater passage 84 in FIG.
After passing through the hole and placing it in the pool 85 in FIG. 1, remove the drill 81 to remove the cut object holding and fixing conveying device 7 from the cutting piece and pull it up, and hold, fix and convey when cutting the next furnace internal structure. To reuse.
本発明のプラズマアーク切断技術による原子炉炉内構造
物解体装置は、以上のように放射線量率の高い原子炉炉
内構造物を解体する上で作業員の被曝低減に必要な水深
での切断解体に必要な機能を具備し、また、放射能汚染
拡大防止に必要な機能並びに作業の効率化を図った装置
で原子炉炉内構造物を解体する上で有効な装置である。The reactor internal structure dismantling apparatus by the plasma arc cutting technology of the present invention is a cutting at the water depth necessary for reducing the exposure of the worker in disassembling the nuclear reactor internal structure having a high radiation dose rate as described above. It is an effective device for dismantling the internal structure of a nuclear reactor with the functions required for dismantling, the functions necessary for preventing the spread of radioactive contamination and the work efficiency.
第1図は、プラズマアーク切断技術による原子炉炉内構
造物解体シシステム全体図である。 第2図(a)及び(b)は、切断駆動装置3の全体図及
びその部分詳細図である。 第3図(a),(b)及び(c)は、昇降軸先端部の取
り外し機構図及びその部分詳細図である。 第4図(a)及び(b)は、発生ガス回収処理装置4の
気中浮遊物回収装置全体の平面及び側面図である。 第5図(a),(b),(c)及び(d)は、水浄化装
置5の全体図及びその部分詳細図である。 第6図(a)及び(b)は、切断物保持固定搬送装置の
全体図及びその部分断面図である。 1……圧力容器、2……炉内構造物 3……切断駆動装置 4……発生ガス回収処理装置 5……水浄化装置、6……切断片 7……切断物保持固定搬送装置 8……クレーン、9……覆いFIG. 1 is an overall view of a system for disassembling internal structures of a nuclear reactor by a plasma arc cutting technique. 2A and 2B are an overall view and a partial detailed view of the cutting drive device 3. 3 (a), (b) and (c) are a detaching mechanism diagram of the lifting shaft tip and a partial detailed view thereof. 4 (a) and 4 (b) are a plan view and a side view of the entire airborne material recovery apparatus of the generated gas recovery processing apparatus 4. FIG. 5 (a), (b), (c) and (d) are an overall view of the water purification device 5 and a partial detailed view thereof. 6 (a) and 6 (b) are an overall view and a partial cross-sectional view of the cut object holding / fixing / conveying device. 1 ... Pressure vessel, 2 ... Reactor internal structure 3 ... Cutting drive device 4 ... Generated gas recovery processing device 5 ... Water purification device, 6 ... Cutting piece 7 ... Cutting object holding and fixing conveying device 8 ... … Crane, 9 …… Cover
───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭60−44898(JP,A) 特開 昭63−64000(JP,A) 特開 昭64−51000(JP,A) 特開 昭56−48600(JP,A) ─────────────────────────────────────────────────── ─── Continuation of the front page (56) Reference JP-A-60-44898 (JP, A) JP-A-63-14000 (JP, A) JP-A 64-51000 (JP, A) JP-A-56- 48600 (JP, A)
Claims (1)
ークの周囲にガスを供給し、アーク熱によりプラズマ化
したガスによって対象物を熔融切断する装置において、 (a)原子炉圧力容器上部に設置した走行及び横行可能
な装置に旋回と昇降が可能な昇降軸を取り付け、その先
端にプラズマアークトーチを取り付けた切断駆動装置、 (b)切断対象となる炉内構造物を保持、固定、搬送す
るための保持固定搬送装置、 (c)送風機、送風ダクト及び送風ダクト出口から構成
される送風系統に対向して排風ダクト入り口、排風ダク
ト、フィルター、排風機から構成される排風系統を備
え、この両系統が前記切断駆動装置の下部に取り付けら
れた、切断時に発生する気中浮遊物を回収する気中浮遊
物回収装置、 (d)水中浮遊物を回収する水浄化装置、及び (e)切断解体作業を確認するための監視カメラを装置
が設けられた熔融切断装置。1. An apparatus for producing an arc between an electrode and an object, supplying a gas around the arc, and melting and cutting the object with the gas turned into plasma by arc heat, comprising: (a) a reactor pressure vessel A cutting drive device in which a lifting and lowering shaft capable of turning and lifting is attached to a traveling and traversing device installed at the upper part, and a plasma arc torch is attached to the tip of the device. (B) Holds and fixes a furnace internal structure to be cut And (c) a blower, which is composed of a blower, a blower duct, and a blower duct outlet, which faces the blower system including a blower, a blower duct, a blower duct, a filter, and a blower. A system for collecting suspended solids, which is installed in the lower part of the cutting drive device, for collecting suspended solids generated during cutting, and (d) Water for collecting suspended solids in water. A fusion cutting device provided with a purifying device and (e) a monitoring camera for confirming cutting and dismantling work.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1154124A JPH0766079B2 (en) | 1989-06-16 | 1989-06-16 | Reactor internal structure dismantling system by plasma arc cutting technology |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1154124A JPH0766079B2 (en) | 1989-06-16 | 1989-06-16 | Reactor internal structure dismantling system by plasma arc cutting technology |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0318797A JPH0318797A (en) | 1991-01-28 |
| JPH0766079B2 true JPH0766079B2 (en) | 1995-07-19 |
Family
ID=15577441
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1154124A Expired - Lifetime JPH0766079B2 (en) | 1989-06-16 | 1989-06-16 | Reactor internal structure dismantling system by plasma arc cutting technology |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0766079B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20220022721A (en) * | 2020-08-19 | 2022-02-28 | 한국원자력연구원 | Apparatus and method for visualizing underwater cutting of nuclear power plant facilities |
| WO2023132581A1 (en) * | 2022-01-04 | 2023-07-13 | 한국수력원자력 주식회사 | Method and apparatus for decommissioning nuclear power plant |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5905947B2 (en) * | 2014-10-06 | 2016-04-20 | 日立Geニュークリア・エナジー株式会社 | Method for carrying out nuclear fuel material in a nuclear power plant |
| JP6158972B2 (en) * | 2016-03-17 | 2017-07-05 | 日立Geニュークリア・エナジー株式会社 | Method for carrying out nuclear fuel material in a nuclear power plant |
| CN113351969A (en) * | 2021-06-21 | 2021-09-07 | 中国核电工程有限公司 | Cutting method, device and system for radioactive container |
| CN115351383B (en) * | 2022-06-28 | 2024-01-23 | 西安理工大学 | Pipe diameter intersecting line control method of cutting robot |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6044898A (en) * | 1983-08-23 | 1985-03-11 | 株式会社熊谷組 | Dismantling system of concrete heat shield wall |
-
1989
- 1989-06-16 JP JP1154124A patent/JPH0766079B2/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20220022721A (en) * | 2020-08-19 | 2022-02-28 | 한국원자력연구원 | Apparatus and method for visualizing underwater cutting of nuclear power plant facilities |
| WO2023132581A1 (en) * | 2022-01-04 | 2023-07-13 | 한국수력원자력 주식회사 | Method and apparatus for decommissioning nuclear power plant |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0318797A (en) | 1991-01-28 |
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