JP2006189378A - Facility for and method of dismantling and removing reactor - Google Patents

Facility for and method of dismantling and removing reactor Download PDF

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JP2006189378A
JP2006189378A JP2005002702A JP2005002702A JP2006189378A JP 2006189378 A JP2006189378 A JP 2006189378A JP 2005002702 A JP2005002702 A JP 2005002702A JP 2005002702 A JP2005002702 A JP 2005002702A JP 2006189378 A JP2006189378 A JP 2006189378A
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calandria
pipe
pressure pipe
pressure
tank
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JP2006189378A5 (en
JP4256349B2 (en
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Yasumasa Oginoya
康正 萩野谷
Eiji Hayakawa
英二 早川
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Hitachi Engineering and Services Co Ltd
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Hitachi Engineering and Services Co Ltd
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Abstract

<P>PROBLEM TO BE SOLVED: To achieve cutting work of pressure pipes and dismantling and removing work of a reactor body in parallel by withdrawing only pressure pipes downward in advance by using a simple facility. <P>SOLUTION: A tentative tank placed at a part of building concrete floor downward the reactor body and injected with water, a storage shelf of pressure pipes placed in the tank, a cutting work stage of the pressure pipes, a cutting device for the pressure pipes, disposal vessels of the pressure pipes, a pressure pipe handling device placed at the upper part of the tentative tank, a first wire hung from the first dolly for work and a second wire hung from the second dolly for work are provided. The pressure pipes are withdrawn from the reactor body with the first wire and the second wire and the pressure pipe handling device, and stored on the storage shelf. <P>COPYRIGHT: (C)2006,JPO&NCIPI

Description

本発明は、原子炉施設において廃炉となった原子炉格納容器内の原子炉を、安全に廃棄するために行う解体および撤去装置並びに解体および撤去方法に関する。   The present invention relates to a dismantling and removal apparatus and a dismantling and removal method for safely disposing of a nuclear reactor in a containment vessel that has been decommissioned in a nuclear reactor facility.

原子炉の解体及び撤去に関する方法は各種の提案がなされており、例えば特許文献１，特許文献２に示すものがある。これらの方法において、原子炉の解体及び撤去作業は炉室外から遠隔操作により、マニピュレータを用いて原子炉を上部から下部へ順次部材毎に切断して解体した後に、解体物を炉室上部から炉室外に移送するものである。   Various proposals have been made for methods relating to the dismantling and removal of the nuclear reactor. For example, Patent Documents 1 and 2 disclose the methods. In these methods, the dismantling and removal of the reactor is carried out by remote control from outside the reactor chamber, and the manipulator is used to cut and disassemble the reactor in order from the upper part to the lower part. It is transferred outside the room.

また他の方法として、特許文献３に示すように、コアボーリングマシンを使用して圧力管型原子炉の鉄水遮へい体及びカランドリアタンク管板を刳り貫き、圧力管集合体（以下圧力管）を内装したカランドリア管を先行して引き抜いてから、カランドリア管及び圧力管を一時貯蔵室に移送して解体する一次作業と、残った原子炉を解体する二次作業とに分けて行う工法が提案されている。   As another method, as shown in Patent Document 3, a core boring machine is used to pierce the iron water shield of the pressure tube reactor and the calandria tank tube plate to form a pressure tube assembly (hereinafter referred to as pressure tube). A construction method is proposed in which the Calandria pipe with the interior is pulled out in advance and then divided into a primary work in which the Calandria pipe and pressure pipe are transferred to the temporary storage room and disassembled, and a secondary work in which the remaining reactor is disassembled. Has been.

特開平８−７５８９２号公報JP-A-8-75892 特開平１０−９０４９３号公報JP-A-10-90493 特開２００４−２１２１４９号公報JP 2004-212149 A

特許文献１，２の工法において、マニピュレータによる遠隔操作で切断する作業は、長期間を要して経済的な損失を生じるとともに、放射能レベルの高い作業環境で解体作業を継続しなければならず、作業者の安全性を確保するための管理，作業性の改善及び切断装置のメンテナンス性向上を図る必要がある。   In the construction methods of Patent Documents 1 and 2, cutting by remote operation with a manipulator requires a long period of time and causes an economic loss, and the dismantling work must be continued in a working environment with a high radioactivity level. Therefore, management for ensuring the safety of workers, improvement of workability, and maintenance of the cutting device need to be improved.

特許文献３の工法においては、多数本あるカランドリア管及び圧力管周囲の鉄水遮へい体及びカランドリタンク管板を、深さが十数ｍにも及ぶ刳り貫き作業で解体する作業、引き抜いたカランドリア管を一時貯蔵室へ搬送する作業及び圧力管を内装した二重構造のカランドリア管を切断する作業等に大幅な期間がかかり、解体工程の短縮化を図ることが困難であった。また、それらの解体装置は遠隔操作で高精度の切断技術が必要となり、開発に長期間と多額な費用が掛かることが問題であった。   In the construction method of Patent Document 3, a large number of calandria pipes and iron water shields around the pressure pipe and calandri tank pipe plate are dismantled by punching work with a depth of more than a dozen meters, and the drawn calandria is pulled out. It took a considerable period of time to transport the pipe to the temporary storage chamber and to cut the double-structured Calandria pipe with the pressure pipe built in, and it was difficult to shorten the dismantling process. In addition, these dismantling devices require a high-precision cutting technique by remote control, and the development takes a long time and a large amount of cost.

本発明は前記問題に鑑みなされたもので、先行して圧力管のみを簡易な装置を用いて引き抜くことにより、圧力管の切断作業と圧力管以外の原子炉本体の解体及び撤去作業とを併行して行うことを可能とし、作業者の安全性を確保するとともに工程の大幅な短縮を図ることを目的とするものである。   The present invention has been made in view of the above problems, and by cutting only the pressure tube using a simple device, the cutting operation of the pressure tube and the dismantling and removal operation of the reactor main body other than the pressure tube are performed in parallel. The purpose of this is to ensure the safety of the operator and to greatly shorten the process.

カランドリア管とその内部に収納された圧力管とからなる集合体と、上部鉄水遮へい体と、下部鉄水遮へい体と、側部鉄水遮へい体と、カランドリアタンクとで原子炉本体の一部が構成され、前記原子炉本体下方の建屋コンクリート床の一部に設置して注水された仮設タンクと、このタンク内に設置された圧力管の保管棚と、圧力管の切断作業台と、圧力管の切断装置と、圧力管の処分容器と、前記仮設タンクの上部に設置された圧力管ハンドリング装置と、第一の作業用台車から吊り下げられた第一のワイヤと、第二の作業用台車から吊り下げられた第二のワイヤとを備え、前記第一のワイヤと前記第二のワイヤと前記圧力管ハンドリング装置とにより、前記原子炉本体から前記圧力管を引き抜いて前記保管棚に保管した後、これを前記切断作業台に載置して前記切断装置により複数に分割切断し、これを前記処分容器に収納して前記第三のワイヤで引き上げるとともに、前記上部鉄水遮へい体の解体及び撤去、前記カランドリア管を含む前記カランドリアタンクの解体及び撤去、前記側部鉄水遮へい体の解体及び撤去及び前記下部鉄水遮へい体の解体及び撤去を併行して行う原子炉の解体及び撤去方法により前記課題を解決できる。   An assembly consisting of a calandria pipe and a pressure pipe housed therein, an upper iron water shielding body, a lower iron water shielding body, a side iron water shielding body, and a calandria tank constitute a reactor main body. A temporary tank in which water is injected by being installed on a part of the building concrete floor below the reactor main body, a pressure pipe storage shelf installed in the tank, a pressure pipe cutting work table, Pressure tube cutting device, pressure tube disposal container, pressure tube handling device installed above the temporary tank, a first wire suspended from the first work carriage, and a second operation A second wire suspended from a trolley, and with the first wire, the second wire, and the pressure tube handling device, the pressure tube is pulled out from the reactor main body to the storage shelf. After storage, Placed on a work table and divided and divided into a plurality of pieces by the cutting device, accommodated in the disposal container and pulled up by the third wire, dismantling and removing the upper iron water shielding body, the Calandria tube The above-mentioned problem can be solved by a method of dismantling and removing the nuclear reactor including the dismantling and removal of the calandria tank, the dismantling and removal of the side iron water shielding body, and the dismantling and removal of the lower iron water shielding body. .

本発明は、炉心タンクと、多数のカランドリア管と各カランドリア管の内部に収納された圧力管と、前記カランドリア管の上部に配設された上部鉄水遮へい体と、前記カランドリア管の下部に配設された下部鉄水遮へい体と、前記カランドリア管と前記圧力管とで構成された集合体の側部に配置された側部鉄水遮へい体と、前記集合体を収納するカランドリアタンクとを含んで構成された原子炉本体の解体および撤去装置であって、前記原子炉本体の上方に配置され、横行走行可能な第一の作業用台車を有し、前記原子炉本体の下方であって、建屋コンクリート床に配置され、注水可能な前記圧力管の保管棚を備えた仮設タンクを有し、該仮設タンクの上方で、前記原子炉本体の下方に配置され、横行走行可能な第二の作業用台車を有し、第一の作業用台車に配設され、前記圧力管の上端部に連結されて前記カランドリア管から前記圧力管を引き抜いて保持する第一のワイヤ手段と、第二の作業用台車に配置され、当該圧力管の下端部に連結されて横方向に牽引する第二のワイヤ手段とを有し、前記圧力管を前記仮設タンク内の前記保管棚に保管する手段を有し、
前記仮設タンクに近接して設けられ、保管されている前記圧力管を切断する手段を有し、切断された前記圧力管を収納する処分容器を有する原子炉本体の解体および撤去装置を提供する。 The present invention includes a core tank, a number of calandria pipes, a pressure pipe accommodated inside each calandria pipe, an upper iron water shield disposed on the calandria pipe, and a lower part of the calandria pipe. A lower iron water shielding body provided, a side iron water shielding body arranged at a side portion of the assembly composed of the calandria pipe and the pressure pipe, and a calandria tank storing the aggregate. An apparatus for disassembling and removing a nuclear reactor main body configured to include a first working carriage that is disposed above the nuclear reactor main body and capable of traversing, and below the nuclear reactor main body. A temporary tank provided on the building concrete floor and provided with a storage shelf for the pressure pipe capable of water injection, and is disposed above the temporary tank and below the reactor main body and is capable of traversing the second tank. Have a working carriage, The first wire means connected to the upper end of the pressure pipe and pulling out the pressure pipe from the calandria pipe, and the second work carriage. Second wire means connected to the lower end of the pipe and pulled laterally, and having means for storing the pressure pipe in the storage shelf in the temporary tank,
A reactor main body disassembly and removal device having means for cutting the pressure tube stored near the temporary tank and having a disposal container for storing the cut pressure tube is provided.

また、前記原子炉本体の上方に配置された第三の作業用台車に配設されて前記処分容器を運搬する第三のワイヤ手段を有する原子炉本体の解体および撤去装置を提供する。   Also provided is a reactor body dismantling and removal apparatus having a third wire means disposed on a third work carriage disposed above the reactor body and transporting the disposal container.

本発明は、更に炉心タンクと、多数のカランドリア管と各カランドリア管の内部に収納された圧力管と、前記カランドリア管の上部に配設された上部鉄水遮へい体と、前記カランドリア管の下部に配設された下部鉄水遮へい体と、前記カランドリア管と前記圧力管とで構成された集合体の側部に配置された側部鉄水遮へい体と、前記集合体を収納するカランドリアタンクとを含んで構成された原子炉本体の解体および撤去装置であって、前記原子炉本体の上方に配置され、横行走行可能な第一の作業用台車に配設され、前記圧力管の上端部に連結されて前記カランドリア管から前記圧力管を引き抜いて保持する第一のワイヤ手段と、前記原子炉本体の下方に配置され、横行走行可能な第二の作業用台車に配置され、当該圧力管の下端部に連結されて横方向に牽引する第二のワイヤ手段とによって、前記圧力管を、前記原子炉本体の下方であって、建屋コンクリート床に配置され、注水可能な仮設タンクの内部の保管棚に保管する原子炉本体の解体および撤去方法を提供する。   The present invention further includes a core tank, a number of calandria pipes, a pressure pipe accommodated in each calandria pipe, an upper iron water shield disposed above the calandria pipe, and a lower part of the calandria pipe. A lower iron water shielding body disposed; a side iron water shielding body disposed on a side portion of the assembly composed of the calandria pipe and the pressure pipe; and a calandria tank storing the aggregate. An apparatus for disassembling and removing a nuclear reactor main body, comprising: a first working carriage disposed above the nuclear reactor main body and capable of traversing; and disposed at an upper end portion of the pressure pipe. A first wire means connected to draw and hold the pressure tube from the calandria tube; and a second work carriage disposed below the reactor body and capable of traversing, Connected to bottom The pressure pipe is stored in a storage shelf inside a temporary tank that is disposed on the concrete floor of the building and under the reactor main body and can be injected by a second wire means that pulls in a lateral direction. A method for dismantling and removing the reactor body is provided.

また、保管されている圧力管を切断手段によって切断し、および切断された圧力管を処分容器に収納し、該処分容器を搬送する工程と、前記炉心タンクと、前記上部鉄水遮へい体、前記下部鉄水遮へい体および前記側部鉄水遮へい体、前記カランドリア管を含むカランドリアタンクの解体および撤去工程とを併行して行う原子炉本体の解体および撤去方法を提供する。   In addition, the stored pressure pipe is cut by a cutting means, and the cut pressure pipe is stored in a disposal container, and the disposal container is transported, the core tank, the upper iron water shield, Disclosed is a method for dismantling and removing a reactor main body in parallel with a dismantling and removing step of a calandria tank including a lower iron water shielding body, a side iron water shielding body, and the calandria pipe.

したがって本発明によれば、下記の効果を奏する。
１．先行引き抜きされた圧力管の切断及び収納作業を原子炉本体の解体作業と併行して行 うことが出来るため、解体工程の大幅短縮を図ることができる。
２．圧力管を上端及び下端に取り付けた２本のワイヤで仮設タンク内に吊降ろし、また切
断作業と収納作業を分ける単純な作業手順とし、使用する装置として一般的に使用実績
のある装置を採用することで、技術的な課題を少なくすることができる。
３．圧力管を引き抜いた後のカランドリア管に水を充填する等の放射線防護策を施すこと
により、原子炉上部及び下部に対する放射線遮へい効果を高めることができ、作業者の
放射線被ばくを低減する事ができる。
４．様々な構成材質からなり、様々な放射能分布を有する圧力管を複数に分割切断するこ
とが可能であるため、それらの切断片を放射能レベル毎または材質毎に分別して処分容
器へ収納することができる。
５．高線量の圧力管を仮設タンク内の水中で切断し、処分容器へ収納するので、水遮へい
効果により作業者の被ばく低減を図ることができる。 Therefore, according to the present invention, the following effects can be obtained.
1. Since the cutting and storage work of the previously drawn pressure tube can be performed in parallel with the dismantling work of the reactor body, the dismantling process can be greatly shortened.
2. The pressure pipe is hung in the temporary tank with two wires attached to the upper and lower ends, and the work procedure is simple, separating the cutting work from the storage work. By doing so, technical problems can be reduced.
3. By taking radiation protection measures such as filling the Calandria tube after the pressure tube has been pulled out, the radiation shielding effect on the upper and lower parts of the reactor can be enhanced, and the radiation exposure of workers can be reduced. .
4). Since pressure pipes made of various constituent materials and having various radioactivity distributions can be divided and cut into multiple parts, the cut pieces are separated into radioactivity levels or materials and stored in the disposal container. can do.
5. Since the high-dose pressure pipe is cut in the water in the temporary tank and stored in the disposal container, the exposure of workers can be reduced by the water shielding effect.

以下、本発明の好適な実施形態について、添付図面を参照して詳細に説明する。図１から図８は、本発明に係わる実施例を示すものである。   DESCRIPTION OF EXEMPLARY EMBODIMENTS Hereinafter, preferred embodiments of the invention will be described in detail with reference to the accompanying drawings. 1 to 8 show an embodiment according to the present invention.

図１は、圧力管型原子炉１００の概略構成および圧力管型原子炉本体２００の解体および撤去装置を示す構成図であり、図２は圧力管型原子炉本体２００の詳細を示す断面図であり、図３は圧力管型原子炉本体２００を構成する圧力管を収納するカランドリア管からなる集合体４００の構成を示す図である。   FIG. 1 is a schematic diagram showing a schematic configuration of a pressure tube reactor 100 and a dismantling and removal apparatus for the pressure tube reactor main body 200, and FIG. 2 is a sectional view showing details of the pressure tube reactor main body 200. FIG. 3 is a diagram showing a configuration of an assembly 400 composed of a Calandria tube that houses a pressure tube constituting the pressure tube reactor main body 200.

まず、図２および図３を使って圧力管型原子炉本体２００および集合体４００の詳細について説明する。   First, the details of the pressure tube reactor main body 200 and the assembly 400 will be described with reference to FIGS. 2 and 3.

１は炉心タンクで、通常運転時には、減速材である重水が注入されているが、解体時には重水が抜きとられた状態となる。炉心タンク１の内側にはカランドリア管２とそれぞれに内装された圧力管３の複数本（２２４本）が設置されている。通常運転時には、圧力管３の内部に燃料が挿入されているが、解体時には燃料は抜かれた状態となる。４Ａは入口管で、圧力管３の内部に連通しており、これに挿入される燃料棒冷却用の冷却水が通過し、上部の上昇管４Ｂを介し循環する。   1 is a core tank, and heavy water as a moderator is injected during normal operation, but heavy water is removed during dismantling. Inside the core tank 1, a plurality (224) of calandria pipes 2 and pressure pipes 3 provided therein are installed. During normal operation, the fuel is inserted into the pressure pipe 3, but the fuel is removed during dismantling. Reference numeral 4A denotes an inlet pipe that communicates with the inside of the pressure pipe 3, through which cooling water for cooling the fuel rods inserted passes and circulates through the upper ascending pipe 4B.

炉心タンク１の外側はカランドリアタンク５、さらにその外側は上部鉄水遮へい体６，下部鉄水遮へい体７及び側部鉄水遮へい体８にて取り囲まれている。   The outer side of the core tank 1 is surrounded by a calandria tank 5, and the outer side thereof is surrounded by an upper iron water shielding body 6, a lower iron water shielding body 7 and a side iron water shielding body 8.

すなわち、原子炉本体２００は、炉心タンク１と、多数のカランドリア管２と各カランドリア管の内部に収納された圧力管３からなる集合体４００と、カランドリア管２の上部に配設された上部鉄水遮へい体６と、カランドリア管２の下部に配設された下部鉄水遮へい体７と、集合体４００の側部に配置された側部鉄水遮へい体８と、集合体４００を収納する、すなわち炉心タンク１を囲むカランドリアタンク５とを含んで構成されている。   That is, the reactor main body 200 includes a core tank 1, an assembly 400 composed of a number of calandria pipes 2 and a pressure pipe 3 housed in each calandria pipe, and an upper iron disposed on the top of the calandria pipe 2. The water shielding body 6, the lower iron water shielding body 7 disposed in the lower part of the calandria pipe 2, the side iron water shielding body 8 disposed on the side of the assembly 400, and the assembly 400 are accommodated. That is, it includes a calandria tank 5 surrounding the core tank 1.

また、９は生体遮へいコンクリート壁で、原子炉本体２００を支持している。なお、図２は２組のカランドリア管２のみが示してある。   Reference numeral 9 denotes a biological shielding concrete wall that supports the reactor main body 200. FIG. 2 shows only two sets of calandria pipes 2.

図３は圧力管３が内装されたカランドリア管２の詳細構成および配置を示す断面図である。   FIG. 3 is a sectional view showing a detailed configuration and arrangement of the calandria pipe 2 in which the pressure pipe 3 is installed.

圧力管３は、圧力管本体３１と、圧力管上部延長管３２と、入口管ノズル３４が接続された圧力管下部延長管３３とから構成されており、上部支持フランジ１１と下部支持フランジ１２とによって、上部鉄水スリーブ１３，下部鉄水スリーブ１４、およびカランドリア管２の内径部に収納されている。   The pressure pipe 3 includes a pressure pipe main body 31, a pressure pipe upper extension pipe 32, and a pressure pipe lower extension pipe 33 to which an inlet pipe nozzle 34 is connected. Are accommodated in the inner diameter portion of the upper iron water sleeve 13, the lower iron water sleeve 14, and the calandria pipe 2.

カランドリア管２の上下両端部は、カランドリアタンク上管板１５とカランドリアタンク下管板１６との間に結合され、上部鉄水スリーブ１３，下部鉄水スリーブ１４の外面は、カランドリアタンク上管板１５と上部支持フランジ１１及びカランドリアタンク上管板１５間の上部鉄水遮へい体６，カランドリアタンク下管板１６、下部支持フランジ１２及びカランドリアタンク下管板１６間の下部鉄水遮へい体７に、それぞれ結合されている。これらの圧力管３とカランドリア管２とは対になり、合計２２４本設置されている。   The upper and lower end portions of the calandria pipe 2 are coupled between the calandria tank upper tube plate 15 and the calandria tank lower tube plate 16, and the outer surfaces of the upper iron water sleeve 13 and the lower iron water sleeve 14 are arranged on the calandria tank Upper iron water shield 6 between the tube plate 15 and the upper support flange 11 and the Calandria tank upper tube plate 15, lower iron water between the Calandria tank lower tube plate 16, the lower support flange 12 and the Calandria tank lower tube plate 16. Each is coupled to the shielding body 7. These pressure pipes 3 and calandria pipes 2 are paired, and a total of 224 are installed.

２１は主としてコンクリート壁２２で構成された原子炉建屋で、上部に第三のレール２３上を走行できる第三の作業用台車２４が、原子炉本体２００上部には、第一のレール２５及び第一の作業用台車２６が、原子炉本体２００下部には第二のレール２７と、この上を走行できる第二の作業用台車２８すなわち圧力管ハンドリング装置３０とが、それぞれ設置されている。   21 is a reactor building mainly composed of a concrete wall 22, and a third work carriage 24 that can run on the third rail 23 is disposed on the upper portion, and the first rail 25 and the second rail are disposed on the upper portion of the reactor body 200. One working carriage 26 is provided at the lower part of the reactor main body 200 with a second rail 27 and a second working carriage 28 that can travel on the rail, that is, a pressure pipe handling device 30.

第一のレール２５と第一の作業用台車２６と圧力管ハンドリング装置３０を備えた第二の作業用台車２８は、原子炉本体２００の解体および撤去作業を行うために設置したものである。原子炉本体２００の下部であって建屋コンクリート床２９には仮設タンク４１が設けてあり、水が注入されている。なお第二のレール２７は、燃料交換用の装置（図示せず）を走行させるために既に設置してあるもので、圧力管３の撤去のために利用される。   The second work carriage 28 including the first rail 25, the first work carriage 26, and the pressure tube handling device 30 is installed to dismantle and remove the reactor body 200. A temporary tank 41 is provided in the building concrete floor 29 at the lower part of the reactor main body 200, and water is injected. The second rail 27 is already installed for running a fuel exchange device (not shown), and is used for removing the pressure pipe 3.

このように、原子炉本体２００の上方に配置され、横行走行可能な第一の作業用台車２６と、原子炉本体２００の下方であって、建屋コンクリート床２９に配置され、注水可能な仮設タンク４１と、仮設タンク４１上方で、原子炉本体２００の下方に配置され、横行走行可能な第二の作業用台車（圧力管ハンドリング装置３０）２８が設けられる。   As described above, the first working carriage 26 that is disposed above the reactor body 200 and is capable of traversing, and the temporary tank that is disposed below the reactor body 200 and disposed on the building concrete floor 29 and capable of water injection. 41 and a temporary work tank 41 and a second work carriage (pressure pipe handling device 30) 28 which is disposed below the reactor main body 200 and capable of traversing.

第一の作業用台車２６には、圧力管３の上端部（上部）に連結されたワイヤを含み、圧力管３を引き抜いて保持する第一のワイヤ手段４２が、そして第二の作業用台車２８には、この上に設けたワイヤ巻き取り機（ワイヤ巻き上げ装置）４４、および圧力管３の下端部（下部）に連結されたワイヤを含み、圧力管３の移動を行う第二のワイヤ手段４３が設けられている。   The first work carriage 26 includes a wire connected to the upper end (upper part) of the pressure tube 3, a first wire means 42 for pulling out and holding the pressure tube 3, and a second work carriage. 28 includes a wire winding machine (wire winding device) 44 provided thereon, and a wire connected to the lower end (lower part) of the pressure tube 3, and second wire means for moving the pressure tube 3 43 is provided.

仮設タンク４１の内部には、移動された圧力管３を横置可能とする保管棚４５が設けられ、保管棚４５の横側で仮設タンク４１内に切断作業台４６および切断装置（切断手段）４７（４７ａ，４７ｂ）が設けられ、コンピュータによって制御されるように構成されている。   Inside the temporary tank 41, there is provided a storage shelf 45 in which the moved pressure pipe 3 can be placed horizontally. A cutting work table 46 and a cutting device (cutting means) are provided in the temporary tank 41 on the side of the storage shelf 45. 47 (47a, 47b) is provided and is configured to be controlled by a computer.

また、切断作業台４６の横側で仮設タンク４１内に処分容器（すなわち搬送容器）４８が置かれ、切断された圧力管３を収容可能としている。   A disposal container (that is, a transport container) 48 is placed in the temporary tank 41 on the side of the cutting work table 46 so that the cut pressure pipe 3 can be accommodated.

第三の作業用台車２４は、図に示すように、原子炉建屋２１の上部に設けられており、処分容器４８に引っかけられたワイヤを含んだ第三のワイヤ手段４９が設けてある。このワイヤ手段４９によって処分容器ごと切断された圧力管を原子炉建屋２１の上方部に搬送可能とされている。   As shown in the drawing, the third working carriage 24 is provided at the upper part of the reactor building 21 and is provided with third wire means 49 including a wire hooked on the disposal container 48. The pressure tube cut along with the disposal container by the wire means 49 can be conveyed to the upper part of the reactor building 21.

このように、炉心タンク１，上部鉄水遮へい体６，下部鉄水遮へい体７および側部鉄水遮へい体８，カランドリア管２を含むカランドリアタンクの解体および撤去作業に先行して圧力管３のみ簡易な装置を用いて下方に引き抜くことにより、圧力管３の切断作業，撤去作業と圧力管以外の原子炉本体２００の解体および撤去作業とを併行して行うことを可能とする。   Thus, the pressure pipe 3 prior to the dismantling and removal of the calandria tank including the core tank 1, the upper iron water shielding body 6, the lower iron water shielding body 7, the side iron water shielding body 8, and the calandria pipe 2 is performed. Only by pulling downward using a simple device, it is possible to perform the cutting and removal work of the pressure tube 3 and the disassembly and removal work of the reactor main body 200 other than the pressure pipe in parallel.

以上のように、炉心タンク１と、多数のカランドリア管２と各カランドリア管の内部に収納された圧力管３と、カランドリア管２の上部に配設された上部鉄水遮へい体６と、カランドリア管２の下部に配設された下部鉄水遮へい体７と、カランドリア管２と圧力管３とで構成された集合体４００の側部、すなわち炉心タンク１の側部に配置された側部鉄水遮へい体８と、集合体４００を収納するカランドリアタンク５とを含んで構成された原子炉本体２００の解体および撤去装置であって、原子炉本体２００の上方に配置され、横行走行可能な第一の作業用台車２６を有し、原子炉本体２００の下方であって、建屋コンクリート床２９に配置され、注水可能な圧力管３の保管棚４５を備えた仮設タンク４１を有し、仮設タンク４１の上方で、原子炉本体２００の下方に配置され、横行走行可能な第二の作業用台車２８、すなわちハンドリング装置３０を有し、第一の作業用台車２６に配設され、圧力管３の上端部に連結されてカランドリア管２から圧力管３を引き抜いて保持する第一のワイヤ手段４２と、第二の作業用台車２８に配置され、圧力管３の下端部に連結されて横方向に牽引する第二のワイヤ手段４３とを有し、圧力管３を仮設タンク４１内の保管棚４５に保管する手段を有し、仮設タンク４１に近接して設けられ、保管されている圧力管３を切断装置４７を有し、切断された圧力管３を収納する処分容器４８を有する原子炉本体の解体および撤去装置が構成される。   As described above, the core tank 1, the many calandria pipes 2, the pressure pipes 3 housed in the calandria pipes, the upper iron water shielding body 6 disposed above the calandria pipes 2, and the calandria pipes. 2, a side iron water disposed at the side of the assembly 400 composed of the lower iron water shielding body 7, the calandria pipe 2 and the pressure pipe 3, that is, the side of the core tank 1. An apparatus for disassembling and removing a reactor main body 200 including the shielding body 8 and the calandria tank 5 that houses the assembly 400, which is disposed above the reactor main body 200 and is capable of traversing. A temporary work tank 26, a temporary tank 41 provided below the reactor body 200, disposed on the building concrete floor 29, and provided with a storage shelf 45 of the pressure pipe 3 capable of water injection; Above 41, A second working carriage 28, that is, a traversing travelable vehicle 28, that is, a handling device 30, which is disposed below the reactor body 200, is disposed on the first working carriage 26, and is connected to the upper end of the pressure tube 3. The first wire means 42 for pulling and holding the pressure tube 3 from the calandria tube 2 and the second work carriage 28 are connected to the lower end of the pressure tube 3 and pulled in the lateral direction. And a means for storing the pressure pipe 3 in a storage shelf 45 in the temporary tank 41, and a cutting device 47 for cutting the pressure pipe 3 provided close to the temporary tank 41 and stored therein. And a reactor main body dismantling and removal apparatus having a disposal container 48 for storing the cut pressure tube 3 is constructed.

また、上述のように、原子炉本体２００の上方に配置された第三の作業用台車２８に配設されて処分容器４８に収納されている切断された圧力管３を運搬する第三のワイヤ手段４９を有する。   In addition, as described above, the third wire that conveys the cut pressure tube 3 that is disposed in the third work carriage 28 disposed above the reactor main body 200 and stored in the disposal container 48. Means 49 are included.

図１において、圧力管３はその上端部が第一の作業用台車２６によりワイヤ手段４２で吊り下げられており、その下端部が第二の作業用台車２８の圧力管ハンドリング装置３０に搭載されているワイヤ巻き取り装置４４を含むワイヤ手段４３に連結されている。それらワイヤ手段４２，４３の２本のワイヤを使用して圧力管３は原子炉本体２００から下方に引き抜かれ、引き抜かれた圧力管３は順次保管棚４５に保管される。保管棚４５に保管されてある圧力管３は第二の作業用台車２８にて切断作業台４６に移送され、切断装置４７にて切断される。４８は、前述のように、複数に切断された圧力管３を収納する処分容器で、第三の作業用台車２４のワイヤ手段４９で吊り上げられようとする状態を示す。   In FIG. 1, the upper end of the pressure pipe 3 is suspended by the wire means 42 by the first work carriage 26, and the lower end is mounted on the pressure pipe handling device 30 of the second work carriage 28. It is connected to wire means 43 including a wire winding device 44. Using these two wire means 42, 43, the pressure tube 3 is drawn downward from the reactor main body 200, and the drawn pressure tubes 3 are sequentially stored in the storage shelf 45. The pressure pipe 3 stored in the storage shelf 45 is transferred to the cutting work table 46 by the second work carriage 28 and cut by the cutting device 47. As described above, reference numeral 48 denotes a disposal container for storing the plurality of pressure pipes 3 cut, and shows a state in which the pressure means 3 is about to be lifted by the wire means 49 of the third working carriage 24.

図４〜図８は本発明になる圧力管の吊り降ろし方法を示す図であり、図７，図８は圧力管吊り降ろし後の圧力管の切断及び収納方法を示す図である。   4 to 8 are views showing a method of hanging a pressure tube according to the present invention, and FIGS. 7 and 8 are views showing a method of cutting and storing the pressure tube after the pressure tube is suspended.

図４は原子炉本体２００から圧力管３を引き抜く第一の作業ステップを示す図である。   FIG. 4 is a diagram showing a first work step of pulling out the pressure tube 3 from the reactor main body 200.

吊り下げ用のリング５１が圧力管上部延長管３２の上端部に設置されており、横倒し用のリング５２と一体化されたクランパ５３が圧力管下部延長管３３の外面部に結合されている。吊り下げ用リング５１に圧力管３の吊り降ろし用の第一のワイヤ手段４２のワイヤを取り付け、吊り降ろしリング５２に圧力管３の横倒し作業を行うための第二のワイヤ手段４３のワイヤを取り付け、後述の圧力管引き抜き作業に移る。ここで、第二のワイヤ手段４３のワイヤは圧力管ハンドリング装置３０を備えた第二の作業用台車２８のワイヤ巻上げ装置４４に連結されている。   A suspension ring 51 is installed at the upper end of the pressure pipe upper extension pipe 32, and a clamper 53 integrated with the sideways ring 52 is coupled to the outer surface of the pressure pipe lower extension pipe 33. The wire of the first wire means 42 for suspending the pressure tube 3 is attached to the suspension ring 51, and the wire of the second wire means 43 for performing the sideways operation of the pressure tube 3 is attached to the suspension ring 52. Then, the operation moves to the pressure tube drawing operation described later. Here, the wire of the second wire means 43 is connected to the wire winding device 44 of the second working carriage 28 provided with the pressure pipe handling device 30.

第一の作業用台車２６で圧力管３を吊って保持しておき、その後、図３に示す圧力管支持フランジ１２を圧力管３から取り外すことにより、圧力管３の自重によって下方に降ろせるようになる。   The pressure tube 3 is suspended and held by the first working carriage 26, and then the pressure tube support flange 12 shown in FIG. 3 is removed from the pressure tube 3 so that the pressure tube 3 can be lowered by its own weight. become.

図５は吊り降ろし作業と、横倒し作業を行う第二の作業ステップを示す図である。なお、図５には圧力管３と下部鉄水遮へい体７のみを記載しており、その他の原子炉本体２００の構造体は省略している。   FIG. 5 is a diagram showing a second work step for performing a hanging work and a sideways work. FIG. 5 shows only the pressure pipe 3 and the lower iron water shielding body 7, and other structural bodies of the reactor main body 200 are omitted.

第一のワイヤ手段４２で吊り下げられた圧力管３を、第二の作業用台車２８に搭載したワイヤ巻き取り機４４で第二のワイヤ手段４３のワイヤを巻き取りながら、仮設タンク４１内に設置された保管棚４５に横倒して保管する。仮設タンク４１内の保管棚４５には全本数、すなわち２２４本の圧力管３が保管できる。なお、図では第二のワイヤ手段４３のワイヤを複数本表示しているが、操作時の圧力管３の倒れ状況を説明するために示したものであり、実際には圧力管１本について第一のワイヤ手段４２と、第二のワイヤ手段４３のワイヤの各１本を用いて交互あるいは両方一緒にあやつることで横倒し、保管棚４５に保管する。   The pressure pipe 3 suspended by the first wire means 42 is placed in the temporary tank 41 while winding the wire of the second wire means 43 by the wire winder 44 mounted on the second work carriage 28. Store on the storage shelf 45 installed. The storage shelf 45 in the temporary tank 41 can store the total number, that is, 224 pressure pipes 3. In the figure, a plurality of wires of the second wire means 43 are displayed, but are shown for explaining the fall state of the pressure tube 3 during operation. By using one of the wires of the one wire means 42 and the second wire means 43 alternately or both together, they are laid down and stored in the storage shelf 45.

図６は第三の作業ステップを示す圧力管引き抜き後の原子炉本体２００の断面図である。   FIG. 6 is a cross-sectional view of the reactor main body 200 after the pressure tube is drawn, showing a third work step.

まず下部鉄水スリーブ１４に閉止栓６２を取り付け、カランドリア管２内に水を注入し、上部鉄水スリーブ１３の上面に閉止板６１を取り付ける。   First, a closing plug 62 is attached to the lower iron-water sleeve 14, water is injected into the calandria pipe 2, and a closing plate 61 is attached to the upper surface of the upper iron-water sleeve 13.

第一の作業ステップから第三の作業ステップまでの手順により、１本ずつ順次圧力管３の引き抜き作業を繰り返し行い、合計２２４本の圧力管３を引き抜く。全ての圧力管３が保管棚４５に保管された後、圧力管３の切断作業及び図８に示す処分容器４８への収容作業に移る。   According to the procedure from the first work step to the third work step, the drawing operation of the pressure pipes 3 is sequentially repeated one by one, and a total of 224 pressure pipes 3 are drawn. After all the pressure tubes 3 are stored in the storage shelf 45, the operation moves to the cutting operation of the pressure tubes 3 and the storing operation in the disposal container 48 shown in FIG.

図７は圧力管の切断作業方法を示す図である。   FIG. 7 is a diagram showing a pressure tube cutting operation method.

建屋コンクリート床２９の上に設置した仮設タンク４１には保管棚４５とそのとなりに切断作業台４６とが設置されており、水が注入されている。原子炉本体２００から引き抜かれた圧力管３は保管棚４５に保管されており、切断作業待ちの状態にある。仮設タンク４１の上部には、レール２７上を走行可能な圧力管ハンドリング装置３０を設置し、車輪７２を有した第二の作業用台車２８にマニピュレータ７４（７４ａ）とマニピュレータ７４（７４ｂ）と、ワイヤの巻き取り装置４４とを備えている。   The temporary tank 41 installed on the building concrete floor 29 is provided with a storage shelf 45 and a cutting work table 46 adjacent thereto, and water is injected. The pressure tube 3 pulled out from the reactor main body 200 is stored in the storage shelf 45 and is in a state of waiting for cutting work. On the upper part of the temporary tank 41, a pressure pipe handling device 30 capable of traveling on the rail 27 is installed, and a manipulator 74 (74a) and a manipulator 74 (74b) are provided on a second working carriage 28 having wheels 72, A wire winding device 44.

圧力管３を切断作業台４６へ移動するには、第二の作業用台車２８上の圧力管ハンドリング装置３０を操作し、マニピュレータ７４ａとマニピュレータ７４ｂによって圧力管３を掴み、第二の作業用台車２８を走行させて切断作業台４６に載置する。切断作業台４６は、載置された圧力管３を遠隔操作によってＫで示すように回転できる保持部を備えており、切断装置４７を固定したまま円筒形の圧力管３を切断する。あるいは、圧力管３を固定で切断装置４７を回転させて切断することも可能としている。切断装置４７は水中でも容易に作業できる切断装置で、例えばウォータジェット切断機やプラズマ切断機等を用いることができる。   In order to move the pressure pipe 3 to the cutting work table 46, the pressure pipe handling device 30 on the second work carriage 28 is operated, the pressure pipe 3 is grasped by the manipulator 74a and the manipulator 74b, and the second work carriage is obtained. 28 is run and placed on the cutting work table 46. The cutting work table 46 includes a holding unit that can rotate the mounted pressure tube 3 as indicated by K by remote control, and cuts the cylindrical pressure tube 3 while the cutting device 47 is fixed. Alternatively, it is possible to perform cutting by rotating the cutting device 47 while fixing the pressure tube 3. The cutting device 47 is a cutting device that can be easily operated even in water. For example, a water jet cutting machine or a plasma cutting machine can be used.

図８に圧力管切断作業後の処分容器４８への収容作業状況を示す。   FIG. 8 shows the status of the storage operation in the disposal container 48 after the pressure tube cutting operation.

圧力管３の長さは約１０ｍにも及び、引き抜いた状態のまま地上に取り出して処分することは困難であり、所定の長さに分割する必要がある。このため３ａ，３ｂ，３ｃで示すように、切断装置４７により３個に切断した後、マニピュレータ７４ｂで掴み、矢印のように搬送して処分容器４８に収納する。分割個数は、本図では３個としたが、切断された圧力管の材質及び放射能レベル並びに処分容器４８の大きさにより任意の長さと個数が選定される。５０は処分容器４８の側壁に取り付けられた吊具で、図１に示したワイヤ手段４９で引き上げる際の連結部材となる。   The length of the pressure pipe 3 is about 10 m, and it is difficult to take out and dispose of the pressure pipe 3 on the ground as it is pulled out, and it is necessary to divide it into a predetermined length. For this reason, as shown by 3a, 3b, 3c, after being cut into three pieces by the cutting device 47, it is grasped by the manipulator 74b, conveyed as shown by the arrow, and stored in the disposal container 48. Although the number of divisions is three in this figure, an arbitrary length and number are selected according to the material and radioactivity level of the cut pressure tube and the size of the disposal container 48. Reference numeral 50 denotes a hanging tool attached to the side wall of the disposal container 48, which becomes a connecting member when the wire means 49 shown in FIG.

切断作業，処分容器への収容作業，上部原子炉本体の解体作業を併行して行える。また、圧力管３を上端部及び下端部に取り付けた２本のワイヤで仮設タンク４１内に吊り降ろし、切断作業と収納作業を分ける作業手順とし、使用する装置として一般的に使用実績のある装置を採用できる。   The cutting work, the storage work in the disposal container, and the dismantling work of the upper reactor main body can be performed at the same time. In addition, the pressure pipe 3 is suspended in the temporary tank 41 with two wires attached to the upper end and the lower end, and the work procedure is divided into a cutting operation and a storage operation, and a device that has generally been used as a device to be used. Can be adopted.

本実施例の方法によれば、とくに先行引き抜きされた圧力管の切断及び収納作業を原子炉の解体作業と併行して行うため、解体工程の大幅短縮を図ることができる。   According to the method of the present embodiment, the cutting and storing operation of the previously drawn pressure tube is performed in parallel with the dismantling operation of the nuclear reactor, so that the dismantling process can be greatly shortened.

本実施例によれば、炉心タンクと、多数のカランドリア管と各カランドリア管の内部に収納された圧力管と、前記カランドリア管の上部に配設された上部鉄水遮へい体と、前記カランドリア管の下部に配設された下部鉄水遮へい体と、前記カランドリア管と前記圧力管とで構成された集合体の側部に配置された側部鉄水遮へい体と、前記集合体を収納するカランドリアタンクとを含んで構成された原子炉本体の解体および撤去方法であって、
前記原子炉本体の上方に配置され、横行走行可能な第一の作業用台車に配設され、前記圧力管の上端部に連結されて前記カランドリア管から前記圧力管を引き抜いて保持する第一のワイヤ手段と、前記原子炉本体の下方に配置され、横行走行可能な第二の作業用台車に配置され、当該圧力管の下端部に連結されて横方向に牽引する第二のワイヤ手段とによって、前記圧力管を、前記原子炉本体の下方であって、建屋コンクリート床に配置され、注水可能な仮設タンクの内部の保管棚に保管し、保管されている圧力管を切断手段によって切断し、および切断された圧力管を処分容器に収納し、該処分容器を搬送する工程と、前記炉心タンクと、前記上部鉄水遮へい体、前記下部鉄水遮へい体および前記側部鉄水遮へい体、前記カランドリア管を含むカランドリアタンクの解体および撤去工程とを併行して行う原子炉本体の解体および撤去方法を構成することができる。 According to the present embodiment, a core tank, a number of calandria pipes, a pressure pipe accommodated inside each calandria pipe, an upper iron water shield disposed on the calandria pipe, and the calandria pipe A lower iron water shielding body disposed in a lower portion; a side iron water shielding body disposed on a side portion of an assembly composed of the calandria tube and the pressure tube; and a calandria housing the assembly. A method for dismantling and removing a reactor body including a tank,
A first working carriage disposed above the reactor main body and disposed on a first working carriage capable of traversing; connected to an upper end portion of the pressure pipe; and pulling and holding the pressure pipe from the calandria pipe. A wire means and a second wire means disposed below the reactor main body and disposed on a second working carriage capable of traversing and connected to the lower end of the pressure pipe and pulled laterally. The pressure pipe is stored in a storage shelf inside the temporary tank, which is disposed below the reactor main body and on the building concrete floor and capable of water injection, and the stored pressure pipe is cut by a cutting means. And storing the cut pressure tube in a disposal container and transporting the disposal container, the core tank, the upper iron water shielding body, the lower iron water shielding body, and the side iron water shielding body, Calandria tube Dismantling and removing method of the reactor body carried out concurrently with the dismantling and removal process of free Curran Doria tank can be configured.

また、圧力管３を上端及び下端に取り付けた２本のワイヤで仮設タンク４１内に吊り降ろし、切断作業と収納作業を分ける単純な作業手順とし、使用する装置として一般的に使用実績のある装置を採用することで、技術的な課題を少なくすることができる。また、圧力管を引き抜いた後のカランドリア管２に水を充填する等の放射線防護策を施すことにより、原子炉上部及び下部に対する放射線遮へい効果を高めることができ、作業者の放射線被ばくを低減する事ができる。また、様々な構成材質からなり、様々な放射能分布を有する圧力管を複数に分割切断することが可能であるため、それらの切断片を放射能レベル毎または材質毎に分別して処分容器へ収納することができる。また、高線量の圧力管を仮設タンク内の水中で切断し、処分容器へ収納するので、水遮へい効果により作業員の被ばく低減を図ることができるという利点を有する。   In addition, the pressure pipe 3 is suspended in the temporary tank 41 with two wires attached to the upper end and the lower end, and a simple work procedure that separates the cutting work and the storage work is used. By adopting, technical problems can be reduced. In addition, by taking radiation protection measures such as filling the Calandria tube 2 after drawing out the pressure tube, the radiation shielding effect on the upper and lower parts of the reactor can be enhanced, and the radiation exposure of the operator is reduced. I can do things. In addition, because it is possible to divide and cut a pressure tube made of various constituent materials and having various radioactivity distributions into a plurality of pieces, the cut pieces are sorted according to radioactivity level or material and stored in a disposal container. can do. In addition, since the high-dose pressure pipe is cut in the water in the temporary tank and stored in the disposal container, there is an advantage that the exposure of workers can be reduced due to the water shielding effect.

原子炉の概略構成および圧力管型原子炉の解体および撤去装置を示す構成図。BRIEF DESCRIPTION OF THE DRAWINGS The block diagram which shows the schematic structure of a nuclear reactor, and the dismantling and removal apparatus of a pressure tube reactor. 圧力管型原子炉本体の詳細を示す断面図。Sectional drawing which shows the detail of a pressure tube reactor main body. 原子炉本体を構成する圧力管を収納するカウンドリア管からなる集合体の構成を示す図。The figure which shows the structure of the aggregate | assembly which consists of a Kaundria pipe | tube which accommodates the pressure pipe which comprises a nuclear reactor main body. 原子炉本体から圧力管を引き抜く第一の作業ステップを示す図。The figure which shows the 1st operation | work step which pulls out a pressure pipe from a reactor main body. 吊り降ろし作業と、横倒し作業を行う第二の作業ステップを示す図。The figure which shows the 2nd operation | work step which performs suspension work and sideways work. 第三の作業ステップを示す圧力管引き抜き後の原子炉本体の断面図。Sectional drawing of the reactor main body after pressure tube drawing which shows a 3rd operation step. 圧力管の切断作業方法を示す図。The figure which shows the cutting work method of a pressure pipe. 圧力管切断作業後の処分容器への収容作業状況を示す図。The figure which shows the accommodation operation | work situation to the disposal container after a pressure pipe cutting operation.

符号の説明Explanation of symbols

１…炉心タンク、２…カランドリア管、３…圧力管、５…カランドリアタンク、６…上部鉄水遮へい体、７…下部鉄水遮へい体、８…側部鉄水遮へい体、１１…上部支持フランジ部、１２…下部支持フランジ部、１３…上部鉄水スリーブ、１４…下部鉄水スリーブ、１５…カランドリアタンク上管板、１６…カランドリアタンク下管板、２１…原子炉建屋、２２…コンクリート壁、２４…第三の作業用台車、２６…第一の作業用台車、２８…第二の作業用台車、２９…建屋コンクリート床、３０…圧力管ハンドリング装置、３１…圧力管本体、３２…圧力管上部延長管、３３…圧力管下部延長管、４１…仮設タンク、４２…第一のワイヤ手段、４３…第二のワイヤ手段、４４…ワイヤ巻き取り機（ワイヤ巻き上げ装置）、４５…保管棚、４６…切断作業台、４７…切断装置、４８…処分容器、４９…第三のワイヤ手段、１００…圧力管型原子炉、２００…原子炉（原子管型原子炉本体）本体、４００…集合体。
DESCRIPTION OF SYMBOLS 1 ... Core tank, 2 ... Calandria pipe, 3 ... Pressure pipe, 5 ... Calandria tank, 6 ... Upper iron water shielding body, 7 ... Lower iron water shielding body, 8 ... Side iron water shielding body, 11 ... Upper support Flange part, 12 ... Lower support flange part, 13 ... Upper iron water sleeve, 14 ... Lower iron water sleeve, 15 ... Calandria tank upper tube plate, 16 ... Calandria tank lower tube plate, 21 ... Reactor building, 22 ... Concrete wall, 24 ... third working carriage, 26 ... first working carriage, 28 ... second working carriage, 29 ... building concrete floor, 30 ... pressure pipe handling device, 31 ... pressure pipe body, 32 ... pressure pipe upper extension pipe, 33 ... pressure pipe lower extension pipe, 41 ... temporary tank, 42 ... first wire means, 43 ... second wire means, 44 ... wire winder (wire winding device), 45 ... Storage shelf, 46 Cutting worktable, 47 ... cutting apparatus, 48 ... disposal container, 49 ... third wire unit, 100 ... pressure tube reactor, 200 ... Reactor (atom tube reactor body) body, 400 ... collection.

Claims (4)

炉心タンクと、多数のカランドリア管と各カランドリア管の内部に収納された圧力管と、前記カランドリア管の上部に配設された上部鉄水遮へい体と、前記カランドリア管の下部に配設された下部鉄水遮へい体と、前記カランドリア管と前記圧力管とで構成された集合体の側部に配置された側部鉄水遮へい体と、前記集合体を収納するカランドリアタンクとを含んで構成された原子炉本体の解体および撤去装置であって、
前記原子炉本体の上方に配置され、横行走行可能な第一の作業用台車を有し、
前記原子炉本体の下方であって、建屋コンクリート床に配置され、注水可能な前記圧力管の保管棚を備えた仮設タンクを有し、
該仮設タンクの上方で、前記原子炉本体の下方に配置され、横行走行可能な第二の作業用台車を有し、
第一の作業用台車に配設され、前記圧力管の上端部に連結されて前記カランドリア管から前記圧力管を引き抜いて保持する第一のワイヤ手段と、第二の作業用台車に配置され、当該圧力管の下端部に連結されて横方向に牽引する第二のワイヤ手段とを有し、前記圧力管を前記仮設タンク内の前記保管棚に保管する手段を有し、
前記仮設タンクに近接して設けられ、保管されている前記圧力管を切断する手段を有し、
切断された前記圧力管を収納する処分容器を有すること
を特徴とする原子炉本体の解体および撤去装置。 A core tank, a number of calandria pipes, a pressure pipe housed inside each calandria pipe, an upper iron water shield disposed above the calandria pipe, and a lower part disposed below the calandria pipe An iron water shielding body, a side iron water shielding body disposed on a side portion of an assembly composed of the calandria pipe and the pressure pipe, and a calandria tank that stores the aggregate. A reactor body dismantling and removal device,
A first working carriage disposed above the reactor body and capable of traversing;
Below the reactor main body, disposed on a building concrete floor, and having a temporary tank provided with a storage shelf for the pressure pipes capable of water injection,
Above the temporary tank, below the reactor main body, having a second working carriage capable of traversing,
Disposed on the first work carriage, connected to the upper end of the pressure pipe, and first wire means for pulling out and holding the pressure pipe from the calandria pipe, and disposed on the second work carriage, Second wire means connected to the lower end of the pressure pipe and pulling in the lateral direction, and having means for storing the pressure pipe in the storage shelf in the temporary tank,
A means for cutting the pressure pipe provided and stored in the vicinity of the temporary tank;
An apparatus for disassembling and removing a reactor main body, comprising a disposal container for storing the cut pressure tube. 請求項１において、前記原子炉本体の上方に配置された第三の作業用台車に配設されて前記処分容器を運搬する第三のワイヤ手段を有することを特徴とする原子炉本体の解体および撤去装置。   2. The dismantling of the reactor main body according to claim 1, further comprising third wire means disposed on a third work carriage disposed above the reactor main body and transporting the disposal container. Removal device. 炉心タンクと、多数のカランドリア管と各カランドリア管の内部に収納された圧力管と、前記カランドリア管の上部に配設された上部鉄水遮へい体と、前記カランドリア管の下部に配設された下部鉄水遮へい体と、前記カランドリア管と前記圧力管とで構成された集合体の側部に配置された側部鉄水遮へい体と、前記集合体を収納するカランドリアタンクとを含んで構成された原子炉本体の解体および撤去方法であって、
前記原子炉本体の上方に配置され、横行走行可能な第一の作業用台車に配設され、前記圧力管の上端部に連結されて前記カランドリア管から前記圧力管を引き抜いて保持する第一のワイヤ手段と、前記原子炉本体の下方に配置され、横行走行可能な第二の作業用台車に配置され、当該圧力管の下端部に連結されて横方向に牽引する第二のワイヤ手段とによって、前記圧力管を、前記原子炉本体の下方であって、建屋コンクリート床に配置され、注水可能な仮設タンクの内部の保管棚に保管すること
を特徴とする原子炉本体の解体および撤去方法。 A core tank, a number of calandria pipes, a pressure pipe housed inside each calandria pipe, an upper iron water shield disposed above the calandria pipe, and a lower part disposed below the calandria pipe An iron water shielding body, a side iron water shielding body disposed on a side portion of an assembly composed of the calandria pipe and the pressure pipe, and a calandria tank that stores the aggregate. A method for dismantling and removing the reactor body,
A first working carriage disposed above the reactor main body and disposed on a first working carriage capable of traversing; connected to an upper end portion of the pressure pipe; and pulling and holding the pressure pipe from the calandria pipe. A wire means and a second wire means disposed below the reactor main body and disposed on a second working carriage capable of traversing and connected to the lower end of the pressure pipe and pulled laterally. A method of dismantling and removing a reactor main body, characterized in that the pressure pipe is stored on a storage shelf inside a temporary tank that is disposed on a concrete floor of the building below the main body of the reactor and can be injected with water. 請求項３において、
保管されている圧力管を切断手段によって切断し、および切断された圧力管を処分容器に収納し、該処分容器を搬送する工程と、前記炉心タンクと、前記上部鉄水遮へい体、前記下部鉄水遮へい体および前記側部鉄水遮へい体、前記カランドリア管を含むカランドリアタンクの解体および撤去工程とを併行して行うこと
を特徴とする原子炉本体の解体および撤去方法。
In claim 3,
Cutting the stored pressure pipe by a cutting means, and storing the cut pressure pipe in a disposal container and transporting the disposal container; the core tank; the upper iron water shield; the lower iron A method for disassembling and removing a reactor main body, wherein the water shielding body, the side iron water shielding body, and the calandria tank including the calandria pipe are disassembled and removed.
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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2012255742A (en) * 2011-06-10 2012-12-27 Hitachi-Ge Nuclear Energy Ltd Conveyance method of radioactive structure member
KR102300638B1 (en) * 2020-12-01 2021-09-09 한국수력원자력 주식회사 Apparatus for decommissioning pressure heavy water reactor facilities
KR102345673B1 (en) * 2020-11-03 2021-12-29 한국수력원자력 주식회사 Method for decommissioning pressure heavy water reactor facilities
KR102345672B1 (en) * 2020-10-30 2021-12-29 한국수력원자력 주식회사 Method for decommissioning pressure heavy water reactor facilities

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55122197A (en) * 1979-03-14 1980-09-19 Hitachi Ltd Device for handling radioactive material
JPH0875892A (en) * 1994-09-07 1996-03-22 Toshiba Eng Co Ltd Nuclear reactor dismantling method and apparatus therefor
JPH1090493A (en) * 1996-09-12 1998-04-10 Fuji Electric Co Ltd Device for demolishing nuclear reactor remotely
JPH10170690A (en) * 1996-12-10 1998-06-26 Hitachi Ltd Method to irradiate irradiated object in pressure pipe type nuclear reactor for short period
JP2004212149A (en) * 2002-12-27 2004-07-29 Sumitomo Mitsui Construction Co Ltd Method of disjointing and removing nuclear reactor
JP2004361113A (en) * 2003-06-02 2004-12-24 Japan Nuclear Cycle Development Inst States Of Projects Disassembly method for pressure tube of advanced thermal reactor

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55122197A (en) * 1979-03-14 1980-09-19 Hitachi Ltd Device for handling radioactive material
JPH0875892A (en) * 1994-09-07 1996-03-22 Toshiba Eng Co Ltd Nuclear reactor dismantling method and apparatus therefor
JPH1090493A (en) * 1996-09-12 1998-04-10 Fuji Electric Co Ltd Device for demolishing nuclear reactor remotely
JPH10170690A (en) * 1996-12-10 1998-06-26 Hitachi Ltd Method to irradiate irradiated object in pressure pipe type nuclear reactor for short period
JP2004212149A (en) * 2002-12-27 2004-07-29 Sumitomo Mitsui Construction Co Ltd Method of disjointing and removing nuclear reactor
JP2004361113A (en) * 2003-06-02 2004-12-24 Japan Nuclear Cycle Development Inst States Of Projects Disassembly method for pressure tube of advanced thermal reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2012255742A (en) * 2011-06-10 2012-12-27 Hitachi-Ge Nuclear Energy Ltd Conveyance method of radioactive structure member
KR102345672B1 (en) * 2020-10-30 2021-12-29 한국수력원자력 주식회사 Method for decommissioning pressure heavy water reactor facilities
KR102345673B1 (en) * 2020-11-03 2021-12-29 한국수력원자력 주식회사 Method for decommissioning pressure heavy water reactor facilities
KR102300638B1 (en) * 2020-12-01 2021-09-09 한국수력원자력 주식회사 Apparatus for decommissioning pressure heavy water reactor facilities

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