JP2013029334A - Nuclear reactor building dismantling system - Google Patents

Nuclear reactor building dismantling system Download PDF

Info

Publication number
JP2013029334A
JP2013029334A JP2011163822A JP2011163822A JP2013029334A JP 2013029334 A JP2013029334 A JP 2013029334A JP 2011163822 A JP2011163822 A JP 2011163822A JP 2011163822 A JP2011163822 A JP 2011163822A JP 2013029334 A JP2013029334 A JP 2013029334A
Authority
JP
Japan
Prior art keywords
building
dismantling
reactor building
reactor
nuclear reactor
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
JP2011163822A
Other languages
Japanese (ja)
Other versions
JP5627117B2 (en
Inventor
Minoru Koyama
実 小山
Hirotoshi Ikeda
宏俊 池田
Akira Ito
章 伊東
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.)
Taisei Corp
Original Assignee
Taisei Corp
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 Taisei Corp filed Critical Taisei Corp
Priority to JP2011163822A priority Critical patent/JP5627117B2/en
Publication of JP2013029334A publication Critical patent/JP2013029334A/en
Application granted granted Critical
Publication of JP5627117B2 publication Critical patent/JP5627117B2/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Landscapes

  • Working Measures On Existing Buildindgs (AREA)

Abstract

PROBLEM TO BE SOLVED: To provide a nuclear reactor building dismantling system capable of speedily dismantling a nuclear reactor building while preventing radioactive matter from scattering out and reducing exposure of operators.SOLUTION: A nuclear reactor building dismantling system 1 dismantles a nuclear reactor building 11 which stores a nuclear reactor 10 in which nuclear fuel reacts. The nuclear reactor building dismantling system 1 includes a protection building 20 which covers the nuclear reactor building 11, an access gantry 30 provided inside the protection building 20, and a ceiling travel type dismantling machine 26 and a conveyance crane 27 provided on a ceiling surface of the protection building 20. The access gantry 30 is provided with a radiation shield area 31 surrounded with a shield wall 32 for blocking radiation.

Description

本発明は、原子炉建屋解体システムに関する。詳しくは、原子炉が収容された原子炉建屋を解体する原子炉建屋解体システムに関する。   The present invention relates to a reactor building dismantling system. Specifically, the present invention relates to a reactor building dismantling system that dismantles a reactor building in which a nuclear reactor is housed.

従来より、日本国内では、軽水炉と呼ばれる形式の原子炉を用いて原子力発電を行っている。具体的には、原子炉は、鉄筋コンクリ−ト構造の原子炉建屋に収納されており、核燃料が収納された鋼製の圧力容器と、この圧力容器を格納する鋼製の格納容器と、この格納容器を囲む厚い鉄筋コンクリート製の主隔壁と、で構成される。
この原子炉では、圧力容器内で核燃料を核分裂反応させて、核分裂反応に伴う熱エネルギーを取り出している。
Conventionally, nuclear power generation has been performed in Japan using a type of nuclear reactor called a light water reactor. Specifically, the nuclear reactor is housed in a reinforced concrete reactor building, a steel pressure vessel containing nuclear fuel, a steel containment vessel for storing the pressure vessel, and this And a main bulkhead made of thick reinforced concrete surrounding the containment vessel.
In this nuclear reactor, nuclear fuel is fissioned in a pressure vessel, and the thermal energy associated with the fission reaction is taken out.

ところで、原子炉の老朽化や自然災害などの事情により、以上の原子炉を廃炉にして解体する場合がある。この場合、例えば、原子炉建屋の最地下階の下を深く掘り下げて、この掘り下げた空間に原子炉を埋設する方法が提案されている(特許文献1参照)。   By the way, due to circumstances such as aging of the nuclear reactor and natural disasters, the above nuclear reactor may be dismantled and demolished. In this case, for example, a method of deeply digging under the lowest basement floor of the reactor building and burying the reactor in the dug space has been proposed (see Patent Document 1).

特開2001−116876号公報JP 2001-116676 A

しかしながら、この場合、作業員が解体重機に搭乗し、この解体重機で原子炉建屋を解体することになるが、核分裂反応で放出された中性子により原子炉建屋の鉄筋コンクリート躯体が放射化されていたり、放射性物質が原子炉建屋の躯体に付着していたりして、原子炉建屋内の放射線量が高くなることがある。   However, in this case, the worker boarded the dismantling machine and dismantled the reactor building with this dismantling machine, but the reinforced concrete frame of the reactor building was activated by the neutrons released by the fission reaction, Radioactive material may adhere to the reactor building enclosure, resulting in a high radiation dose in the reactor building.

よって、作業員の被曝量を抑制するため、作業員が原子炉建屋の近傍で長時間作業することができず、原子炉建屋を迅速に解体することが困難になる、という問題があった。また、原子炉建屋の解体時に、粉塵とともに放射性物質が外部に飛散するおそれがあった。   Therefore, in order to suppress the exposure amount of the worker, there is a problem that the worker cannot work in the vicinity of the reactor building for a long time and it is difficult to quickly dismantle the reactor building. In addition, when the reactor building was dismantled, there was a risk that radioactive materials would be scattered outside along with dust.

本発明は、放射性物質が外部に飛散するのを防止し、かつ、作業員の被曝量を低減して原子炉建屋を迅速に解体できる原子炉建屋解体システムを提供することを目的とする。   An object of the present invention is to provide a reactor building dismantling system that prevents radioactive materials from being scattered to the outside and that can reduce the exposure amount of workers and quickly dismantle the reactor building.

請求項1に記載の原子炉建屋解体システムは、核燃料を反応させる原子炉が収容された原子炉建屋を解体するための原子炉建屋解体システムであって、前記原子炉建屋を覆う防護建屋と、当該防護建屋の内部に設けられたアクセス構台と、前記防護建屋の天井面に設けられた天井走行式の解体用機械および搬送クレーンと、を備え、前記アクセス構台には、放射線を遮蔽する遮蔽部材で囲まれた放射線遮蔽エリアが設けられることを特徴とする。   The reactor building dismantling system according to claim 1 is a reactor building dismantling system for dismantling a reactor building in which a nuclear reactor that reacts with nuclear fuel is housed, and a protective building that covers the reactor building; An access gantry provided inside the protective building; and an overhead traveling dismantling machine and a transport crane provided on the ceiling surface of the protective building, wherein the access gantry includes a shielding member that shields radiation. A radiation shielding area surrounded by is provided.

この発明によれば、アクセス構台の放射線遮蔽エリアから解体状況を適宜確認しながら、床走行式の解体用機械、天井走行式の解体用機械、天井走行式の搬送クレーンなどを遠隔操作して、原子炉建屋を解体する。   According to the present invention, while confirming the dismantling status from the radiation shielding area of the access gantry as appropriate, the floor traveling type dismantling machine, the overhead traveling type dismantling machine, the overhead traveling transport crane, etc. are remotely operated, Dismantle the reactor building.

ここで、原子炉建屋を防護建屋で覆ったので、放射性物質が外部に飛散するのを防止できる。また、アクセス構台に遮蔽部材で囲まれた放射線遮蔽エリアを設け、この放射線遮蔽エリア内から解体状況を確認するようにしたので、作業員の被曝量を低減して、原子炉建屋を迅速に解体できる。   Here, since the reactor building is covered with the protective building, it is possible to prevent radioactive materials from being scattered outside. In addition, a radiation shielding area surrounded by a shielding member is provided on the access gantry, and the dismantling status is confirmed from within this radiation shielding area, reducing the exposure of workers and quickly dismantling the reactor building. it can.

請求項2に記載の原子炉建屋解体システムは、前記防護建屋は、複数のモジュールが上下に積層されて構成されることを特徴とする。   The reactor building dismantling system according to claim 2 is characterized in that the protective building is configured by stacking a plurality of modules vertically.

この発明によれば、防護建屋を複数のモジュールに分割しておき、大型クレーンによりこれらモジュールを揚重して積層して、防護建屋を構築する。よって、防護建屋を構築する際、作業員が原子炉建屋に長時間接近する必要がなく、作業員の被曝量をさらに低減できる。   According to this invention, a protection building is divided | segmented into a some module, these modules are lifted and laminated | stacked with a large crane, and a protection building is constructed | assembled. Therefore, when constructing the protective building, it is not necessary for the worker to approach the reactor building for a long time, and the exposure amount of the worker can be further reduced.

請求項3に記載の原子炉建屋解体システムは、前記防護建屋の内部を負圧に維持する換気設備を備えることを特徴とする。   The reactor building dismantling system according to claim 3 is provided with a ventilation facility for maintaining the inside of the protective building at a negative pressure.

この発明によれば、防護建屋の内部を負圧に維持したので、作業員や搬出車両が防護建屋に出入りする際、放射性物質が外部に飛散するのを防止でき、周辺環境の安全性を向上できる。   According to the present invention, since the inside of the protective building is maintained at a negative pressure, it is possible to prevent radioactive substances from being scattered outside when workers and carry-out vehicles enter and leave the protective building, and improve the safety of the surrounding environment. it can.

本発明によれば、アクセス構台の放射線遮蔽エリアから解体状況を適宜確認しながら、床走行式の解体用機械、天井走行式の解体用機械、天井走行式の搬送クレーンなどを遠隔操作して、原子炉建屋を解体する。ここで、原子炉建屋を防護建屋で覆ったので、放射性物質が外部に飛散するのを防止できる。また、アクセス構台に遮蔽部材で囲まれた放射線遮蔽エリアを設け、この放射線遮蔽エリア内から解体状況を確認するようにしたので、作業員の被曝量を低減して、原子炉建屋を迅速に解体できる。   According to the present invention, while appropriately checking the dismantling status from the radiation shielding area of the access gantry, remotely operating a floor traveling type dismantling machine, an overhead traveling dismantling machine, an overhead traveling transport crane, etc. Dismantle the reactor building. Here, since the reactor building is covered with the protective building, it is possible to prevent radioactive materials from being scattered outside. In addition, a radiation shielding area surrounded by a shielding member was provided on the access gantry, and the dismantling status was confirmed from within this radiation shielding area. it can.

本発明の一実施形態に係る原子炉建屋解体システムの縦断面図である。It is a longitudinal cross-sectional view of the reactor building dismantling system which concerns on one Embodiment of this invention. 前記実施形態に係る原子炉建屋解体システムのA−A断面図である。It is AA sectional drawing of the reactor building dismantling system which concerns on the said embodiment. 前記実施形態に係る原子炉建屋解体システムを構築する手順を説明するための図(その1)である。It is FIG. (1) for demonstrating the procedure which builds the reactor building dismantling system which concerns on the said embodiment. 前記実施形態に係る原子炉建屋解体システムを構築する手順を説明するための図(その2)である。It is FIG. (2) for demonstrating the procedure which builds the reactor building dismantling system which concerns on the said embodiment. 前記実施形態に係る原子炉建屋解体システムを構築する手順を説明するための図(その3)である。It is FIG. (3) for demonstrating the procedure which builds the reactor building dismantling system which concerns on the said embodiment.

以下、本発明の一実施形態について、図面を参照しながら説明する。
図1は、本発明の一実施形態に係る原子炉建屋解体システム1の縦断面図である。図2は、原子炉建屋解体システム1のA−A断面図である。
Hereinafter, an embodiment of the present invention will be described with reference to the drawings.
FIG. 1 is a longitudinal sectional view of a reactor building dismantling system 1 according to an embodiment of the present invention. FIG. 2 is a cross-sectional view of the reactor building dismantling system 1 taken along the line AA.

原子炉建屋解体システム1は、核燃料を反応させる原子炉10が収容された鉄筋コンクリ−ト構造の原子炉建屋11を解体する。
原子炉10は、核燃料が収納された鋼製の圧力容器と、この圧力容器を格納する鋼製の格納容器と、この格納容器を囲む厚い鉄筋コンクリート製の主隔壁と、を備え、圧力容器内で核燃料を核分裂反応させて、核分裂反応に伴う熱エネルギーを取り出すものである。
The reactor building dismantling system 1 dismantles a reactor building 11 having a reinforced concrete structure in which a nuclear reactor 10 that reacts with nuclear fuel is accommodated.
The nuclear reactor 10 includes a steel pressure vessel in which nuclear fuel is stored, a steel containment vessel that houses the pressure vessel, and a thick reinforced concrete bulkhead that surrounds the containment vessel. The nuclear fuel undergoes a fission reaction to extract the thermal energy associated with the fission reaction.

原子炉建屋解体システム1は、原子炉建屋11を覆う防護建屋20と、この防護建屋20の内側に設けられたアクセス構台30と、防護建屋20の外側に設けられた出入管理設備40および換気設備としての換気・機械設備50と、を備える。   The reactor building dismantling system 1 includes a protection building 20 that covers the reactor building 11, an access gantry 30 provided inside the protection building 20, an access control facility 40 and a ventilation facility provided outside the protection building 20. As a ventilation / mechanical facility 50.

防護建屋20は、高い気密性を有しており、原子炉建屋11の周囲を地盤改良して形成された基礎21と、基礎21の上に設置されて原子炉建屋11の側面を覆う壁部22と、この壁部22の上に設けられ原子炉建屋11の上面を覆う屋根部23と、を備える。   The protective building 20 has high airtightness, a base 21 formed by improving the ground around the reactor building 11, and a wall portion that is installed on the base 21 and covers the side surface of the reactor building 11. 22 and a roof portion 23 provided on the wall portion 22 and covering the upper surface of the reactor building 11.

防護建屋20の壁部22および屋根部23は、3つのモジュール20A、20B、20Cが積層されて構成される。
具体的には、モジュール20A、20B、20Cは、矩形枠状のベースモジュール20A、このベースモジュール20Aの上に積層された矩形枠状の中間モジュール20B、中間モジュール20Bの上に積層された平板状のトップモジュール20Cからなる。
The wall portion 22 and the roof portion 23 of the protective building 20 are configured by stacking three modules 20A, 20B, and 20C.
Specifically, the modules 20A, 20B, and 20C include a rectangular frame-shaped base module 20A, a rectangular frame-shaped intermediate module 20B stacked on the base module 20A, and a flat plate stacked on the intermediate module 20B. The top module 20C.

ベースモジュール20Aは、防護建屋20の壁部22を上下に三分割したうちの最下段に相当する。
中間モジュール20Bは、防護建屋20の壁部22を上下に三分割したうちの中間部分に相当する。
トップモジュール20Cは、防護建屋20の壁部22を上下に三分割したうちの最上段と屋根部23とからなる。
これらモジュール20A、20B、20C同士の接合部分の隙間は、図示しないエアタイトチューブで密閉されている。
The base module 20 </ b> A corresponds to the lowermost step among the upper and lower walls 22 of the protective building 20.
The intermediate module 20 </ b> B corresponds to an intermediate portion of the wall portion 22 of the protective building 20 divided into three parts in the vertical direction.
The top module 20 </ b> C includes an uppermost step of the wall portion 22 of the protective building 20 divided into three parts in the vertical direction and a roof portion 23.
The gaps at the joints between these modules 20A, 20B, and 20C are sealed with an air tight tube (not shown).

防護建屋20の内部には、大型の解体材を解体するための解体エリア24が設けられている。この解体エリア24の外周には、放射線を遮蔽する遮蔽部材としての遮蔽壁25が設けられており、この遮蔽壁25により、解体材からの放射線が外部に漏れないようになっている。   A dismantling area 24 for dismantling a large dismantling material is provided inside the protective building 20. On the outer periphery of the dismantling area 24, a shielding wall 25 is provided as a shielding member for shielding radiation, and the shielding wall 25 prevents radiation from the dismantling material from leaking outside.

屋根部23の内部には、天井走行式の解体用機械26と、天井走行式の搬送クレーン27と、が設けられる。   Inside the roof portion 23, an overhead traveling type dismantling machine 26 and an overhead traveling type transport crane 27 are provided.

解体用機械26は、原子炉建屋11を解体するためのものであり、遠隔操作可能な構造である。解体用機械26は、防護建屋20の屋根部23に架設されて略水平に延びる走行レール261と、この走行レール261に沿って走行可能で遠隔操作可能な機械本体262と、を備える。この機械本体262の先端には、種々のアタッチメントが装着可能となっている。
解体用機械26は、アタッチメントを適宜装着することにより、コンクリートの圧砕や切断、金属の切断、解体材の把持などの種々の作業が可能となっている。
The dismantling machine 26 is for dismantling the reactor building 11 and has a structure that can be remotely operated. The dismantling machine 26 includes a traveling rail 261 that is installed on the roof 23 of the protective building 20 and extends substantially horizontally, and a machine body 262 that can travel along the traveling rail 261 and can be remotely operated. Various attachments can be attached to the tip of the machine body 262.
The dismantling machine 26 can perform various operations such as crushing and cutting of concrete, cutting of metal, and gripping of a dismantling material by appropriately attaching an attachment.

搬送クレーン27は、原子炉建屋11を解体した解体材を解体フロア内で水平方向に運搬したり、解体材を解体フロアから地上レベルまで荷下ろししたりするためのものであり、遠隔操作可能な構造である。搬送クレーン27は、それぞれ、防護建屋20の屋根部23に架設されて略水平に延びる走行レール271と、この走行レール271に沿って走行可能なクレーン本体272と、を備える。   The transport crane 27 is for carrying the dismantling material dismantled from the reactor building 11 in the horizontal direction within the dismantling floor, or for unloading the dismantling material from the dismantling floor to the ground level, and can be remotely operated. Structure. Each of the transport cranes 27 includes a traveling rail 271 that is installed on the roof portion 23 of the protective building 20 and extends substantially horizontally, and a crane body 272 that can travel along the traveling rail 271.

アクセス構台30は、トラス部材で構築され、原子炉建屋11の側面に沿って上方に延びている。このアクセス構台30の屋上には、放射線を遮蔽する遮蔽部材としての遮蔽壁32で囲まれた放射線遮蔽エリア31が設けられている。
この放射線遮蔽エリア31内では、遮蔽壁32により、放射線の被曝量が低減するようになっている。
The access gantry 30 is constructed of a truss member and extends upward along the side surface of the reactor building 11. On the roof of the access gantry 30, a radiation shielding area 31 surrounded by a shielding wall 32 as a shielding member for shielding radiation is provided.
In the radiation shielding area 31, the radiation exposure amount is reduced by the shielding wall 32.

アクセス構台30の内部には、エレベータや階段などの昇降設備が設けられており、この昇降設備により、地上レベルから放射線遮蔽エリア31にアクセス可能となっている。   The access gantry 30 is provided with elevating equipment such as elevators and stairs, and the elevating equipment allows access to the radiation shielding area 31 from the ground level.

出入管理設備40は、作業員や搬出車両43が防護建屋20内に出入りするための設備である。すなわち、出入管理設備40には、作業員が通行可能な作業員通路41と、搬出車両43が通行可能な車両通路42が設けられる。出入管理設備40には除染設備が設けられており、この除染設備を用いて作業員や搬出車両43を除染して、防護建屋20内の放射性物質が作業員や搬出車両43付着して外部に流出しないようにする。   The entry / exit management facility 40 is a facility for allowing workers and carry-out vehicles 43 to enter and exit the protection building 20. That is, the entrance / exit management facility 40 is provided with a worker passage 41 through which a worker can pass and a vehicle passage 42 through which the unloading vehicle 43 can pass. The entry / exit management facility 40 is provided with a decontamination facility. The decontamination facility is used to decontaminate workers and carry-out vehicles 43, and radioactive substances in the protective building 20 adhere to the workers and carry-out vehicles 43. To prevent it from leaking outside.

換気・機械設備50は、フィルタを通して防護建屋20内の空気を換気しつつ、防護建屋20内を負圧に維持する。これにより、防護建屋20内の放射性物質が外部に流出するのを防止する。
また、この換気・機械設備50は、緊急時に防護建屋20の内部空間を外部に開放する緊急ベント機能を有している。
The ventilation / mechanical facility 50 maintains the inside of the protective building 20 at a negative pressure while ventilating the air in the protective building 20 through a filter. Thereby, the radioactive substance in the protective building 20 is prevented from flowing out.
Further, the ventilation / mechanical facility 50 has an emergency vent function for opening the internal space of the protective building 20 to the outside in an emergency.

以上の原子炉建屋解体システム1の構築方法は、以下のようになる。
まず、原子炉建屋11の周囲に基礎21を形成し、また、アクセス構台30を構築する。
次に、原子炉建屋11の近傍で、ベースモジュール20A、中間モジュール20B、トップモジュール20Cを地上で組み立てる。トップモジュール20Cには、天井走行式の解体用機械26および天井走行式の搬送クレーン27を組み込んでおく。
The construction method of the above reactor building dismantling system 1 is as follows.
First, the foundation 21 is formed around the reactor building 11 and the access gantry 30 is constructed.
Next, in the vicinity of the reactor building 11, the base module 20A, the intermediate module 20B, and the top module 20C are assembled on the ground. An overhead traveling type dismantling machine 26 and an overhead traveling type transport crane 27 are incorporated in the top module 20C.

次に、図3〜図5に示すように、超大型クレーン60により、吊り治具61を用いて、基礎21の上にベースモジュール20A、中間モジュール20B、トップモジュール20Cの順に揚重して積層し、防護建屋20を構築する。このとき、吊り治具61のモジュール20A〜20Cの開放や、モジュール20A〜20C同士の接続は、全て遠隔操作で行う。
次に、出入管理設備40および換気・機械設備50を設置し、図示しない床走行式の解体用機械を原子炉建屋11の屋上に配置する。
Next, as shown in FIGS. 3 to 5, the base module 20 </ b> A, the intermediate module 20 </ b> B, and the top module 20 </ b> C are lifted and stacked in this order on the foundation 21 using the suspension jig 61 by the super large crane 60. Then, the protective building 20 is constructed. At this time, the modules 20A to 20C of the hanging jig 61 are opened and the modules 20A to 20C are all connected by remote control.
Next, the access control facility 40 and the ventilation / mechanical facility 50 are installed, and a floor traveling type dismantling machine (not shown) is arranged on the roof of the reactor building 11.

以上の原子炉建屋解体システム1では、作業員は、アクセス構台30の放射線遮蔽エリア31から解体状況を適宜確認しながら、天井走行式の解体用機械26および天井走行式の搬送クレーン27のほか、図示しない床走行式の解体用機械などを遠隔操作し、原子炉建屋11を上から解体する。
このとき、大型の解体材は、搬送クレーン27で解体エリア24に荷下ろしし、この解体エリア24にて細かく解体する。
そして、解体材を放射性廃棄物容器に収納して密封して、この放射性廃棄物容器を搬出車両43で搬出する。
In the reactor building dismantling system 1 described above, an operator confirms the dismantling status from the radiation shielding area 31 of the access gantry 30 as well as the overhead traveling dismantling machine 26 and the overhead traveling transport crane 27, The reactor building 11 is disassembled from above by remotely operating a floor traveling type dismantling machine (not shown).
At this time, the large dismantling material is unloaded into the dismantling area 24 by the transport crane 27, and is dismantled finely in the dismantling area 24.
Then, the dismantling material is accommodated in a radioactive waste container and sealed, and the radioactive waste container is carried out by the carry-out vehicle 43.

本実施形態によれば、以下のような効果がある。
(1)原子炉建屋11を防護建屋20で覆ったので、放射性物質が外部に飛散するのを防止できる。また、アクセス構台30に遮蔽壁32で囲まれた放射線遮蔽エリア31を設け、この放射線遮蔽エリア31内から解体状況を確認するようにしたので、作業員の被曝量を低減して、原子炉建屋11を迅速に解体できる。
According to this embodiment, there are the following effects.
(1) Since the reactor building 11 is covered with the protection building 20, it is possible to prevent radioactive materials from being scattered outside. In addition, since the radiation shield area 31 surrounded by the shield wall 32 is provided on the access gantry 30 and the dismantling status is confirmed from within the radiation shield area 31, the exposure amount of the worker is reduced and the reactor building is reduced. 11 can be dismantled quickly.

(2)防護建屋20を3つのモジュール20A〜20Cに分割しておき、超大型クレーン60によりこれらモジュール20A〜20Cを揚重して積層して、防護建屋20を構築する。よって、防護建屋20を構築する際、作業員が原子炉建屋11に長時間接近する必要がなく、作業員の被曝量をさらに低減できる。   (2) The protection building 20 is divided into three modules 20 </ b> A to 20 </ b> C, and these modules 20 </ b> A to 20 </ b> C are lifted and stacked by the super large crane 60 to construct the protection building 20. Therefore, when constructing the protective building 20, it is not necessary for the worker to approach the reactor building 11 for a long time, and the exposure amount of the worker can be further reduced.

(3)防護建屋20の内部を負圧に維持したので、作業員や搬出車両43が防護建屋20に出入りする際、放射性物質が外部に飛散するのを防止でき、周辺環境の安全性を向上できる。   (3) Since the inside of the protective building 20 is maintained at a negative pressure, it is possible to prevent radioactive materials from being scattered outside when workers and carry-out vehicles 43 enter and leave the protective building 20 and improve the safety of the surrounding environment. it can.

なお、本発明は前記実施形態に限定されるものではなく、本発明の目的を達成できる範囲での変形、改良等は本発明に含まれるものである。   It should be noted that the present invention is not limited to the above-described embodiment, and modifications, improvements, etc. within a scope that can achieve the object of the present invention are included in the present invention.

1…原子炉建屋解体システム
10…原子炉
11…原子炉建屋
20…防護建屋
20A…ベースモジュール
20B…中間モジュール
20C…トップモジュール
21…基礎
22…壁部
23…屋根部
24…解体エリア
25…遮蔽壁
26…解体用機械
27…搬送クレーン
30…アクセス構台
31…放射線遮蔽エリア
32…遮蔽壁(遮蔽部材)
40…出入管理設備
41…作業員通路
42…車両通路
43…搬出車両
50…換気・機械設備(換気設備)
60…超大型クレーン
61…吊り治具
261…走行レール
262…機械本体
271…走行レール
272…クレーン本体
DESCRIPTION OF SYMBOLS 1 ... Reactor building dismantling system 10 ... Reactor 11 ... Reactor building 20 ... Protection building 20A ... Base module 20B ... Intermediate module 20C ... Top module 21 ... Base 22 ... Wall part 23 ... Roof part 24 ... Dismantling area 25 ... Shielding Wall 26 ... Demolition machine 27 ... Transport crane 30 ... Access gantry 31 ... Radiation shielding area 32 ... Shielding wall (shielding member)
40 ... Entrance / exit management equipment 41 ... Worker passage 42 ... Vehicle passage 43 ... Unloading vehicle 50 ... Ventilation / mechanical equipment (ventilation equipment)
DESCRIPTION OF SYMBOLS 60 ... Super-large crane 61 ... Hanging jig 261 ... Traveling rail 262 ... Machine main body 271 ... Traveling rail 272 ... Crane main body

Claims (3)

核燃料を反応させる原子炉が収容された原子炉建屋を解体するための原子炉建屋解体システムであって、
前記原子炉建屋を覆う防護建屋と、当該防護建屋の内部に設けられたアクセス構台と、前記防護建屋の天井面に設けられた天井走行式の解体用機械および搬送クレーンと、を備え、
前記アクセス構台には、放射線を遮蔽する遮蔽部材で囲まれた放射線遮蔽エリアが設けられることを特徴とする原子炉建屋解体システム。
A reactor building dismantling system for dismantling a reactor building containing a nuclear fuel reacting reactor,
A protection building covering the reactor building, an access gantry provided inside the protection building, an overhead traveling dismantling machine and a transport crane provided on the ceiling surface of the protection building,
The reactor building dismantling system, wherein the access gantry is provided with a radiation shielding area surrounded by a shielding member for shielding radiation.
前記防護建屋は、複数のモジュールが上下に積層されて構成されることを特徴とする請求項1に記載の原子炉建屋解体システム。   The reactor building demolition system according to claim 1, wherein the protection building is configured by stacking a plurality of modules vertically. 前記防護建屋の内部を負圧に維持する換気設備を備えることを特徴とする請求項1または2に記載の原子炉建屋解体システム。   The reactor building dismantling system according to claim 1 or 2, further comprising a ventilation facility for maintaining the inside of the protective building at a negative pressure.
JP2011163822A 2011-07-27 2011-07-27 Reactor building dismantling system Active JP5627117B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2011163822A JP5627117B2 (en) 2011-07-27 2011-07-27 Reactor building dismantling system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2011163822A JP5627117B2 (en) 2011-07-27 2011-07-27 Reactor building dismantling system

Publications (2)

Publication Number Publication Date
JP2013029334A true JP2013029334A (en) 2013-02-07
JP5627117B2 JP5627117B2 (en) 2014-11-19

Family

ID=47786517

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2011163822A Active JP5627117B2 (en) 2011-07-27 2011-07-27 Reactor building dismantling system

Country Status (1)

Country Link
JP (1) JP5627117B2 (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2017067754A (en) * 2015-09-29 2017-04-06 日立Geニュークリア・エナジー株式会社 Demolition method of reactor building
JP6991625B1 (en) 2021-05-25 2022-01-12 株式会社ナベカヰ Anti-scattering curing system and structure dismantling method using it
KR20220092107A (en) * 2020-12-24 2022-07-01 주식회사 오리온이엔씨 Temporary multi-stage safety-shelter for preventing scattering dust from dissolving nuclear power plants

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6466599A (en) * 1987-09-07 1989-03-13 Kajima Corp Method for disassembling reactor building
JPH01302200A (en) * 1988-05-31 1989-12-06 Shimizu Corp Decommissioning of nuclear reactor
JPH1077742A (en) * 1996-07-11 1998-03-24 Hitachi Ltd Constructing method for plant
JP2002341089A (en) * 2001-05-22 2002-11-27 Shimizu Corp Dismantling method and dismantling device of shielding wall
JP2003034981A (en) * 2001-07-25 2003-02-07 Kajima Corp Method for constructing steel plate concrete structure
JP2007303970A (en) * 2006-05-11 2007-11-22 Taisei Corp Safety facility

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6466599A (en) * 1987-09-07 1989-03-13 Kajima Corp Method for disassembling reactor building
JPH01302200A (en) * 1988-05-31 1989-12-06 Shimizu Corp Decommissioning of nuclear reactor
JPH1077742A (en) * 1996-07-11 1998-03-24 Hitachi Ltd Constructing method for plant
JP2002341089A (en) * 2001-05-22 2002-11-27 Shimizu Corp Dismantling method and dismantling device of shielding wall
JP2003034981A (en) * 2001-07-25 2003-02-07 Kajima Corp Method for constructing steel plate concrete structure
JP2007303970A (en) * 2006-05-11 2007-11-22 Taisei Corp Safety facility

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2017067754A (en) * 2015-09-29 2017-04-06 日立Geニュークリア・エナジー株式会社 Demolition method of reactor building
KR20220092107A (en) * 2020-12-24 2022-07-01 주식회사 오리온이엔씨 Temporary multi-stage safety-shelter for preventing scattering dust from dissolving nuclear power plants
KR102559068B1 (en) * 2020-12-24 2023-07-24 주식회사 오리온이엔씨 Temporary multi-stage safety-shelter for preventing scattering dust from dissolving nuclear power plants
JP6991625B1 (en) 2021-05-25 2022-01-12 株式会社ナベカヰ Anti-scattering curing system and structure dismantling method using it
JP2022180878A (en) * 2021-05-25 2022-12-07 株式会社ナベカヰ Splash prevention cure system and structure demolition method using the same

Also Published As

Publication number Publication date
JP5627117B2 (en) 2014-11-19

Similar Documents

Publication Publication Date Title
KR100944404B1 (en) System and method of storing high level waste
JP5627117B2 (en) Reactor building dismantling system
JP6571982B2 (en) Operating floor containment compartment and nuclear plant
JP6349059B2 (en) Radioactive material treatment facility
JP6916239B2 (en) Reactor building overall cover device and reactor building preparation work method
CN110010257B (en) Device and method for assembling and disassembling strong radioactive core components of reactor of floating nuclear power station
JP2013002924A (en) Bridge type crane and method of disassembling nuclear power plant
EP2515310B1 (en) Shielded protective tent assembly
JP6129656B2 (en) Method for carrying out fuel debris and working house system in boiling water nuclear power plant
JP5681318B1 (en) Method for dismantling a damaged reactor core
CN104934088A (en) Anti-radiation cab
JP2015049060A (en) Fuel debris carry-out apparatus and carry-out method in boiling water nuclear power plant
JP4055157B2 (en) Reactor pressure vessel replacement method
US11984233B2 (en) Method for decommissioning heavy water reactor facility
JP6480365B2 (en) Reactor building demolition method
JP5905790B2 (en) Spent fuel storage facility
JP2013238545A (en) Radioactive material treatment facility
RU66841U1 (en) BIOLOGICAL PROTECTION MODULE
JP6729209B2 (en) Shield port installation method and shield port
CN201163545Y (en) Shielding device used for once neutron source component suspension
JP2005308624A (en) Nuclear reactor facility
JP4096911B2 (en) Reactor pressure vessel replacement method
JP6301764B2 (en) Method of unloading nuclear equipment, unloading device thereof, and method of retrieving fuel debris
Wall et al. Retrieval of Intermediate Level Waste at Trawsfyndd Nuclear Power Station
JP2015214866A (en) Safety protection equipment and installation method for the same

Legal Events

Date Code Title Description
A621 Written request for application examination

Free format text: JAPANESE INTERMEDIATE CODE: A621

Effective date: 20131113

A977 Report on retrieval

Free format text: JAPANESE INTERMEDIATE CODE: A971007

Effective date: 20140718

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20140725

A521 Request for written amendment filed

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20140909

TRDD Decision of grant or rejection written
A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

Effective date: 20140926

A61 First payment of annual fees (during grant procedure)

Free format text: JAPANESE INTERMEDIATE CODE: A61

Effective date: 20140929

R150 Certificate of patent or registration of utility model

Ref document number: 5627117

Country of ref document: JP

Free format text: JAPANESE INTERMEDIATE CODE: R150

R250 Receipt of annual fees

Free format text: JAPANESE INTERMEDIATE CODE: R250