JP2015184176A - Water filling method in reactor pressure vessel in nuclear power plant - Google Patents

Water filling method in reactor pressure vessel in nuclear power plant Download PDF

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JP2015184176A
JP2015184176A JP2014061844A JP2014061844A JP2015184176A JP 2015184176 A JP2015184176 A JP 2015184176A JP 2014061844 A JP2014061844 A JP 2014061844A JP 2014061844 A JP2014061844 A JP 2014061844A JP 2015184176 A JP2015184176 A JP 2015184176A
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plug
pressure vessel
reactor pressure
water
filling
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JP6368513B2 (en
JP2015184176A5 (en
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孝一 黒澤
Koichi Kurosawa
孝一 黒澤
信哉 大森
Shinya Omori
信哉 大森
廉 守中
Tadashi Morinaka
廉 守中
千葉 昇
Noboru Chiba
昇 千葉
鈴木 貢
Mitsugi Suzuki
鈴木  貢
重男 大森
Shigeo Omori
重男 大森
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Hitachi GE Nuclear Energy Ltd
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Hitachi GE Nuclear Energy Ltd
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Abstract

PROBLEM TO BE SOLVED: To provide a water filling method in a reactor pressure vessel for improving the work environment of an operator, by suppressing the influence of radiation on the surroundings when a fuel debris is taken from the reactor pressure vessel.SOLUTION: In carrying out a structure disposed in a reactor core, a shared device in which a plug attaching device 38 or a debris takeout device can be installed is inserted into a reactor pressure vessel 11, and the clearance between them is sealed. Then, a nozzle part of the reactor pressure vessel is blocked with a plug using the plug attaching device installed in the shared device. Then, water is filled into an upper part of the shared device.

Description

本発明は原子力プラントにおける原子炉圧力容器内水張り工法に係り、特に、原子炉圧力容器(以下、RPVという)内から燃料デブリを取出す際の作業者の安全性を改善した原子力プラントにおける原子炉圧力容器内水張り工法に関する。   TECHNICAL FIELD The present invention relates to a method for filling a reactor pressure vessel in a nuclear power plant, and more particularly to a reactor pressure in a nuclear plant that improves the safety of an operator when taking out fuel debris from the reactor pressure vessel (hereinafter referred to as RPV). It relates to the water filling method in the container.

一般に、原子力プラント、特に沸騰水型原子力プラントにおいては、非常時においても常にRPV内の炉心の冷却がされるように、多重の緊急冷却設備が設けられ、炉心溶融事故を防ぐように対策が講じられている。しかし、極めて少ない確率ではあるが、過酷事故により緊急冷却設備の機能が喪失し炉心溶融に至る場合が想定される。   In general, in nuclear power plants, especially boiling water nuclear power plants, multiple emergency cooling facilities are provided so that the core in the RPV is always cooled even in an emergency, and measures are taken to prevent core melting accidents. It has been. However, although the probability is very small, it is assumed that the function of the emergency cooling facility is lost due to a severe accident and the core is melted.

このような場合には、既存の原子炉建屋に設置してある燃料搬出機器の使用が出来ない場合が考えられ、通常の燃料搬出作業が実施できない場合が想定され、炉心溶融により発生した燃料デブリをRPV内から取出すことが難しいものとなる。   In such a case, it is possible that the fuel delivery equipment installed in the existing reactor building cannot be used, and it is assumed that normal fuel delivery work cannot be performed. Is difficult to remove from the RPV.

特許文献1には、沸騰水型原子炉に過酷事故が発生した後でも炉心燃料を容易に取り出すことのできる原子炉内燃料取出し方法が記載されている。この特許文献1では、沸騰水型原子炉が設けられた既設の原子炉建屋を囲むように仮設建屋を設置して、この仮設建屋に吊上げ装置を取り付け、この吊上げ装置を用いて沸騰水型原子炉内の炉心燃料に対して上方に設置された複数の炉内構造物を順次取り外した後に、更に、この吊上げ装置を用いて炉心燃料を取り出す原子炉内燃料取出し方法が記載されている。   Patent Document 1 describes a nuclear fuel removal method in which core fuel can be easily removed even after a severe accident occurs in a boiling water reactor. In this Patent Document 1, a temporary building is installed so as to surround an existing reactor building provided with a boiling water reactor, a lifting device is attached to the temporary building, and a boiling water atom is used by using this lifting device. A nuclear fuel removal method is described in which a plurality of in-core structures installed above the core fuel in the reactor are sequentially removed and then the core fuel is taken out using the lifting device.

特開2013−156133号公報JP 2013-156133 A

しかしながら、上述した炉心溶融により発生した燃料デブリは、高放射化された燃料と炉内構造物等が溶融硬化したものであり、その搬出には、放射線対策、発生した二次生成物の汚染拡大防止等を考慮することが重要であり、万が一の燃料デブリの拡散は作業被ばくや周辺区域への汚染拡大につながる。   However, the fuel debris generated by the melting of the core described above is a product obtained by melting and hardening highly activated fuel and the internal structure of the reactor. It is important to consider prevention, etc. In the unlikely event that fuel debris is diffused, it will lead to work exposure and the spread of contamination to surrounding areas.

一方、特許文献1に記載の方法においては、原子炉格納容器の上蓋を取り外す前に、原子炉ウェル内の水張りを行なうことが記載されているが、原子炉ウェルが必ずしも水張りすることができない可能性もあり、RPV内から燃料デブリを取出す際の作業者の安全性の改善の余地がある。また、発生した二次生成物の汚染拡大防止についての記載は無く、この点に関しても更に改善の余地がある。   On the other hand, in the method described in Patent Document 1, it is described that the reactor well is filled with water before removing the upper cover of the reactor containment vessel. However, the reactor well may not necessarily be filled with water. Therefore, there is room for improvement in worker safety when removing fuel debris from the RPV. Moreover, there is no description about prevention of the expansion of contamination of the generated secondary product, and there is room for further improvement in this respect.

本発明は上述の点に鑑みなされたもので、その目的とするところは、原子炉圧力容器内から燃料デブリを取出す等の各種作業を行う際の放射線による周囲への影響を抑制し、作業者の作業環境を良好にする原子力プラントにおける原子炉圧力容器内水張り工法を提供することにある。   The present invention has been made in view of the above-described points, and the object of the present invention is to suppress the influence of radiation on the surroundings when performing various operations such as taking out fuel debris from the reactor pressure vessel, and It is intended to provide a method for filling a reactor pressure vessel in a nuclear power plant to improve the working environment.

本発明の原子力プラントにおける原子炉圧力容器内水張り工法は、上記目的を達成するために、原子力プラントにおける原子炉圧力容器内水張り工法であって、炉心上部に設けられている蒸気乾燥器、気水分離器を搬出した後、少なくともプラグ取付装置又はデブリ取出し装置が設置できる共用装置を原子炉圧力容器内に挿入して、前記共用装置に設置されているプラグ取付装置を用いて前記原子炉圧力容器のノズル部をプラグで塞ぎ、その後原子炉圧力容器内に設置されている解体対象機器の上方まで前記共用装置を下降し、前記共用装置の外周に位置する前記原子炉圧力容器間をシールした後前記共用装置の上方に水を張り、解体対象機器の取り出し(切断解体)を実施することを特徴とする。   In order to achieve the above object, a water pressure filling method for a reactor pressure vessel in a nuclear power plant according to the present invention is a water pressure filling method for a reactor pressure vessel in a nuclear power plant. After unloading the separator, insert at least a common device in which a plug attachment device or a debris removal device can be installed into the reactor pressure vessel, and use the plug attachment device installed in the common device to After the nozzle part of the reactor is closed with a plug, the shared device is lowered to above the dismantling target device installed in the reactor pressure vessel and the space between the reactor pressure vessels located on the outer periphery of the shared device is sealed Water is spread above the shared device, and the device to be dismantled is taken out (cutting and dismantling).

本発明によれば、原子炉圧力容器内から燃料デブリを取出す等の各種作業を行う際の放射線による周囲への影響を抑制し、作業者の作業環境を良好にすることが可能となる。   ADVANTAGE OF THE INVENTION According to this invention, it becomes possible to suppress the influence on the circumference | surroundings by the radiation at the time of performing various operations, such as taking out fuel debris from the inside of a reactor pressure vessel, and it becomes possible to improve an operator's working environment.

本発明の原子力プラントにおける原子炉圧力容器内水張り工法の実施例1が適用される沸騰水型原子力プラントの概略構成を示す図である。BRIEF DESCRIPTION OF THE DRAWINGS It is a figure which shows schematic structure of the boiling water nuclear power plant in which Example 1 of the water pressure filling method in a reactor pressure vessel in the nuclear power plant of this invention is applied. 図1の沸騰水型原子力プラントのRPV内の構造物及びノズルの配置を示す図である。It is a figure which shows the arrangement | positioning of the structure and nozzle in RPV of the boiling water nuclear power plant of FIG. 本発明の原子力プラントにおける原子炉圧力容器内水張り工法の作業フローチャートの一例である。It is an example of the work flowchart of the water pressure filling method in the reactor pressure vessel in the nuclear power plant of this invention. 図1の沸騰水型原子力プラントのRPV内、デブリ取出し装置が設置された共用装置を挿入し上部格子板を切断解体する状態を示す図である。It is a figure which shows the state which inserts the common apparatus with which the debris extraction apparatus was installed in RPV of the boiling water nuclear power plant of FIG. 1, and cuts and disassembles an upper lattice board. 図1の沸騰水型原子力プラントのRPV内に、プラグ取付装置が設置された共用装置を挿入した状態を示す図である。It is a figure which shows the state which inserted the common apparatus with which the plug attachment apparatus was installed in RPV of the boiling water nuclear power plant of FIG. 図5の実施例1におけるプラグ取付装置の詳細を示す図である。It is a figure which shows the detail of the plug attachment apparatus in Example 1 of FIG. 本発明の原子力プラントにおける原子炉圧力容器内水張り工法の実施例1を示し、共用装置をプラグ取付箇所まで搬入した状態を示す図である。It is a figure which shows Example 1 of the water filling method in the reactor pressure vessel in the nuclear power plant of this invention, and shows the state which carried in the common apparatus to the plug attachment location. 図7の状態からプラグ取付装置を共用装置内へ搬入した状態を示す図である。It is a figure which shows the state which carried the plug attachment apparatus into the shared apparatus from the state of FIG. 図8の状態からプラグ取付装置を副旋回テーブルシールへ挿入した状態を示す図である。It is a figure which shows the state which inserted the plug attachment apparatus into the sub turning table seal from the state of FIG. 図9の状態から遮へいポートを開状態にした状態を示す図である。It is a figure which shows the state which made the shielding port the open state from the state of FIG. 図10の状態からプラグ取付装置を副旋回テーブルへ着座した状態を示す図である。It is a figure which shows the state which seated the plug attachment apparatus in the sub turning table from the state of FIG. 図11の状態から主旋回テーブルを旋回してプラグ取付の位置決めを行う状態を示す図である。It is a figure which shows the state which turns a main turning table from the state of FIG. 11, and positions a plug attachment. 図12の状態から副旋回テーブルを旋回してプラグ取付装置の位置決めを行う状態を示す図である。It is a figure which shows the state which turns a sub turning table from the state of FIG. 12, and positions a plug attachment apparatus. 図13の状態からプラグ受取りの状態を示す図である。It is a figure which shows the state of plug reception from the state of FIG. 図14の状態から昇降機構によるRPV内へプラグを搬入する状態を示す図である。It is a figure which shows the state which carries in a plug in RPV by a raising / lowering mechanism from the state of FIG. 図15の状態から旋回機構による姿勢の変更状態を示す図である。It is a figure which shows the change state of the attitude | position by a turning mechanism from the state of FIG. 図16の状態から回転機構による180°旋回した状態を示す図である。It is a figure which shows the state rotated 180 degrees by the rotation mechanism from the state of FIG. 図17の状態からプラグ押付機構によるプラグ取付状態を示す図である。It is a figure which shows the plug attachment state by a plug pressing mechanism from the state of FIG. プラグでノズル部を塞いだ後、プラグ取付装置の各動作機構をプラグ取付装置内へ戻した状態を示す図である。It is a figure which shows the state which returned each operation | movement mechanism of the plug attachment apparatus into the plug attachment apparatus after plugging a nozzle part with a plug. 図19の状態からプラグ取付装置を上昇した状態を示す図である。It is a figure which shows the state which raised the plug attachment apparatus from the state of FIG. 図20の状態から遮へいポートを閉状態にした状態を示す図である。It is a figure which shows the state which made the shielding port the closed state from the state of FIG. 図21の状態からプラグ取付装置を共用装置から搬出した状態を示す図である。It is a figure which shows the state which carried out the plug attachment apparatus from the common apparatus from the state of FIG. 本発明の原子力プラントにおける原子炉圧力容器内水張り工法の実施例2が適用される沸騰水型原子力プラントのRPV内に、プラグ取付装置が設置された共用装置を挿入した状態を示す図である。It is a figure which shows the state which inserted the common apparatus with which the plug attachment apparatus was installed in RPV of the boiling water nuclear power plant to which Example 2 of the water pressure filling method in the reactor pressure vessel in the nuclear power plant of this invention is applied. 図23の実施例2におけるプラグ取付装置の詳細を示す図である。It is a figure which shows the detail of the plug attachment apparatus in Example 2 of FIG. 本発明の原子力プラントにおける原子炉圧力容器内水張り工法の実施例2を示し、共用装置をプラグ取付箇所まで搬入した状態を示す図である。It is a figure which shows Example 2 of the water filling method in the reactor pressure vessel in the nuclear power plant of this invention, and shows the state which carried in the common apparatus to the plug attachment location. 図25の状態からプラグ取付装置を共用装置内へ搬入した状態を示す図である。It is a figure which shows the state which carried the plug attachment apparatus into the shared apparatus from the state of FIG. 図26の状態からプラグ取付装置を副旋回テーブルシールへ挿入した状態を示す図である。It is a figure which shows the state which inserted the plug attachment apparatus into the sub turning table seal from the state of FIG. 図27の状態から遮へいポートを開状態にした状態を示す図である。It is a figure which shows the state which made the shielding port the open state from the state of FIG. 図28の状態からプラグ取付装置を副旋回テーブルへ着座した状態を示す図である。It is a figure which shows the state which seated the plug attachment apparatus to the sub turning table from the state of FIG. 図29の状態から主旋回テーブルを旋回してプラグ取付の位置決めを行う状態を示す図である。It is a figure which shows the state which turns the main turning table from the state of FIG. 29, and positions a plug attachment. 図30の状態からプラグ押付機構によるプラグ取付状態を示す図である。It is a figure which shows the plug attachment state by a plug pressing mechanism from the state of FIG. プラグでノズル部を塞いだ後、プラグ把持機構及びプラグ押付機構をプラグ取付装置内へ戻した状態を示す図である。It is a figure which shows the state which plugged the nozzle part with the plug and returned the plug holding mechanism and the plug pressing mechanism into the plug mounting device. 図32の状態からプラグ取付装置を上昇した状態を示す図である。It is a figure which shows the state which raised the plug attachment apparatus from the state of FIG. 図33の状態から遮へいポートを閉状態にした状態を示す図である。It is a figure which shows the state which made the shielding port the closed state from the state of FIG. 図34の状態からプラグ取付装置を共用装置から搬出した状態を示す図である。It is a figure which shows the state which carried out the plug attachment apparatus from the common apparatus from the state of FIG.

以下、図示した実施例に基づいて本発明の原子力プラントにおける原子炉圧力容器内水張り工法を説明する。なお、各図において、同一構成部品には同符号を使用する。   Hereinafter, a method for filling a reactor pressure vessel in a nuclear power plant according to the present invention will be described with reference to the illustrated embodiment. In each figure, the same symbols are used for the same components.

沸騰水型原子力プラントに適用した本発明の原子力プラントにおける原子炉圧力容器内水張り工法の実施例1について図1から図22を用いて説明する。   A first embodiment of the water pressure filling method in a reactor pressure vessel in a nuclear power plant of the present invention applied to a boiling water nuclear power plant will be described with reference to FIGS.

まず、本実施例の沸騰水型原子力プラントの概略構造を、図1を用いて説明する。該図に示す如く、沸騰水型原子力プラント1は、原子炉2及び原子炉格納容器(以下、PCVという)3を備えている。PCV3は、原子炉建屋4内に設置されて、上端部に上蓋5が取り付けられて密封されている。PCV3は、内部に形成されたドライウェル6及び冷却水が充填された圧力抑制プールが内部に形成された圧力抑制室7を有する。ドライウェル6に連絡されるベント通路8の一端が、圧力抑制室7内の圧力抑制プールの冷却水中に浸漬されている。PCV3の上蓋5の真上に複数に分割された放射線遮へい体であるシールドプラグ9が配置され、これらのシールドプラグ9が、原子炉建屋4の運転床(以下、オペフロ29という)に設置されている。   First, the schematic structure of the boiling water nuclear power plant of the present embodiment will be described with reference to FIG. As shown in the figure, the boiling water nuclear power plant 1 includes a nuclear reactor 2 and a reactor containment vessel (hereinafter referred to as PCV) 3. The PCV 3 is installed in the reactor building 4 and is sealed with an upper lid 5 attached to the upper end. The PCV 3 has a dry well 6 formed inside and a pressure suppression chamber 7 in which a pressure suppression pool filled with cooling water is formed. One end of the vent passage 8 connected to the dry well 6 is immersed in the cooling water of the pressure suppression pool in the pressure suppression chamber 7. A shield plug 9, which is a radiation shielding body divided into a plurality of parts, is disposed directly above the upper lid 5 of the PCV 3, and these shield plugs 9 are installed on the operation floor of the reactor building 4 (hereinafter referred to as “operation floor 29”). Yes.

原子炉2は、上蓋10が取り付けられて構成される原子炉圧力容器(以下、RPVという)11、核燃料物質を含む複数の燃料集合体が装荷された炉心12、蒸気乾燥器13及び気水分離器14を備えている。炉心12、気水分離器14及び蒸気乾燥器13は、RPV11内に配置されている。   The nuclear reactor 2 includes a reactor pressure vessel (hereinafter referred to as RPV) 11 having a top cover 10 attached thereto, a core 12 loaded with a plurality of fuel assemblies containing nuclear fuel materials, a steam dryer 13 and a steam / water separator. A container 14 is provided. The core 12, the steam / water separator 14, and the steam dryer 13 are disposed in the RPV 11.

図2を用いて原子炉2の詳細を説明する。図2は蒸気乾燥器13及び気水分離器14を取外した状態を示す。   Details of the nuclear reactor 2 will be described with reference to FIG. FIG. 2 shows a state where the steam dryer 13 and the steam separator 14 are removed.

該図に示す如く、RPV11内に設置された炉心シュラウド15が、炉心12を取り囲んでいる。炉心12内に装荷された各燃料集合体16は、下端部が炉心支持板17によって支持され、上端部が上部格子板18によって保持される。気水分離器14は、炉心12の上端部に位置する上部格子板18よりも上方に配置され、蒸気乾燥器13が気水分離器14の上方に配置されている。   As shown in the figure, a core shroud 15 installed in the RPV 11 surrounds the core 12. Each fuel assembly 16 loaded in the core 12 has a lower end supported by the core support plate 17 and an upper end held by the upper lattice plate 18. The steam / water separator 14 is disposed above the upper lattice plate 18 located at the upper end of the core 12, and the steam dryer 13 is disposed above the steam / water separator 14.

複数の制御棒案内管19が炉心12の下方に配置され、複数の制御棒案内管19を含むサポートシリンダが形成されている。炉心12内の燃料集合体16間に出し入れされて原子炉出力を制御する制御棒(図示せず)が、各制御棒案内管19内に配置されている。複数の制御棒駆動機構ハウジング21が、RPV11の下鏡22に取り付けられている。制御棒駆動機構(図示せず)が、それぞれの制御棒駆動機構ハウジング21内に設置され、制御棒案内管19内の制御棒と連結されている。また、サポートシリンダの外周にはジェットポンプ57が円周上に複数配置されている。   A plurality of control rod guide tubes 19 are arranged below the core 12, and a support cylinder including the plurality of control rod guide tubes 19 is formed. Control rods (not shown) that are put into and out of the fuel assemblies 16 in the core 12 to control the reactor power are disposed in the control rod guide tubes 19. A plurality of control rod drive mechanism housings 21 are attached to the lower mirror 22 of the RPV 11. A control rod drive mechanism (not shown) is installed in each control rod drive mechanism housing 21 and connected to the control rod in the control rod guide tube 19. A plurality of jet pumps 57 are arranged on the circumference of the support cylinder.

RPV11は、その内壁面から多数のノズル配管が接続されている。RPV11の上方から一例として、主蒸気用ノズル41C、非常用復水器ノズル41D、給水ノズル41F、CSノズル41G、再循環入口ノズル41B、再循環出口ノズル41A、計測ノズル41E等が異なる高さレベルにあり、かつ、各ノズル41A−41Gは、RPV11の円周上に複数存在する。   The RPV 11 is connected to a number of nozzle pipes from the inner wall surface. As an example from above the RPV 11, the main steam nozzle 41C, the emergency condenser nozzle 41D, the water supply nozzle 41F, the CS nozzle 41G, the recirculation inlet nozzle 41B, the recirculation outlet nozzle 41A, the measurement nozzle 41E, etc. have different height levels. In addition, there are a plurality of nozzles 41A-41G on the circumference of the RPV 11.

また、RPV11は、PCV3内の底部に設けられたコンクリートマット23上に設けられた筒状のペデスタル24上に据え付けられている。筒状のγ線遮蔽体25が、ペデスタル24の上端に設置され、RPV11を取り囲んでいる。   Moreover, RPV11 is installed on the cylindrical pedestal 24 provided on the concrete mat 23 provided in the bottom part in PCV3. A cylindrical γ-ray shield 25 is installed at the upper end of the pedestal 24 and surrounds the RPV 11.

原子炉建屋4には、原子炉ウェルを挟み込むように、ドライヤ・セパレータプール(以下、DSPという)26及び使用済みの燃料を一時的に保管する使用済燃料貯蔵プール(以下、SFPという)27が設けられている。DSP26は、定期検査時に蒸気乾燥器13や気水分離器14といった炉内構造物を仮置きする場所として使われる。   The reactor building 4 has a dryer / separator pool (hereinafter referred to as DSP) 26 and a spent fuel storage pool (hereinafter referred to as SFP) 27 for temporarily storing used fuel so as to sandwich the reactor well. Is provided. The DSP 26 is used as a place for temporarily placing in-furnace structures such as the steam dryer 13 and the steam separator 14 during periodic inspection.

次に、沸騰水型原子力プラント1において、炉心溶融が生じた場合に発生する燃料デブリ28の形態の概要について説明する。   Next, an outline of the form of the fuel debris 28 generated when the core melts in the boiling water nuclear power plant 1 will be described.

例えば、沸騰水型原子力プラント1において、冷却設備の機能が喪失しRPV11内に冷却水が注入されない場合は、核燃料の崩壊熱により、燃料集合体16内の燃料ペレット及び被覆管等が溶融する。この場合、溶融した核燃料はもともと存在していた位置、RPV11の炉底部、又はPCV3の底部であるコンクリートマット23上に存在すると推定される。本実施例の原子力プラントにおける原子炉圧力容器内水張り工法は、このような状態の燃料デブリ28を搬出する際等に適用される。   For example, in the boiling water nuclear power plant 1, when the function of the cooling facility is lost and the cooling water is not injected into the RPV 11, the fuel pellets and the cladding tube in the fuel assembly 16 are melted by the decay heat of the nuclear fuel. In this case, it is estimated that the molten nuclear fuel exists on the concrete mat 23 which is the position where it originally existed, the furnace bottom of the RPV 11, or the bottom of the PCV 3. The water pressure filling method in the reactor pressure vessel in the nuclear power plant of this embodiment is applied when carrying out the fuel debris 28 in such a state.

本実施例の原子炉圧力容器内水張り工法の手順について、図2及び図3を用いて説明する。   The procedure of the water pressure filling method in the reactor pressure vessel of the present embodiment will be described with reference to FIGS.

本実施例では、RPV11に後述するプラグ取付装置38又はデブリ取出し装置58(図4参照)が設置できる共用装置39をRPV11内に挿入し、共用装置39の外周に有する上部外周シール30A及び下部外周シール30BによりRPV11の内壁面との隙間をシールすることで、シール面から上方に水張りが可能となる。本工法は、燃料デブリ28の取出しを主体とした炉内構造物の切断解体作業において、共用装置39の上方に水張りして遮へい水深を確保した状態で作業を行うことで、オペフロ29における線量当量率の低減、及び切断解体時に発生するダストの拡散防止を図ることを目的とする。その際、RPV11の内壁面の各高さレベルには、上述した各種ノズル41A−41Gが存在し、水張りを阻害する。そのため炉内構造物を順次上からデブリ取出し装置58により取り出しながら、共用装置39を下降し、該当高さレベルのノズルをプラグ取付装置38によりプラグで閉止して注水を繰り返す手順となる。   In this embodiment, a common device 39 in which a plug mounting device 38 or a debris extraction device 58 (see FIG. 4), which will be described later, can be installed in the RPV 11 is inserted into the RPV 11, and an upper outer peripheral seal 30A and a lower outer periphery on the outer periphery of the common device 39. By sealing the gap with the inner wall surface of the RPV 11 with the seal 30B, water filling can be performed upward from the seal surface. In this construction method, in the operation of cutting and dismantling the internal structure of the reactor mainly taking out the fuel debris 28, the work is carried out in a state where water is filled above the common device 39 and the shielding water depth is secured. The purpose is to reduce the rate and prevent the diffusion of dust generated during cutting and dismantling. In that case, the various nozzles 41A-41G mentioned above exist in each height level of the inner wall surface of RPV11, and water filling is inhibited. Therefore, while the reactor internals are sequentially taken out from above by the debris take-out device 58, the common device 39 is lowered, and the nozzle at the corresponding height level is closed by the plug by the plug mounting device 38 and water injection is repeated.

図3に、作業フローの一例を示す。   FIG. 3 shows an example of the work flow.

該図に示す本実施例の作業フローは、最初に共用装置39をRPV11内に吊り降ろし(ステップ59A)、主蒸気用ノズル41Cの近傍位置に設置する。プラグ取付装置38にて主蒸気用ノズル41Cにプラグを取付け後(ステップ59B)に、下方に移動し、非常用復水器ノズル41Dに同様にプラグを取り付ける(ステップ59B)。次に共用装置39を下降(ステップ59C)し、しかるべき位置で共用装置39の上部外周シール30Aから上に注水し、水張りを行う(ステップ59D)。プラグ取付装置38をデブリ取出し装置58に交換(ステップ59E)し、近傍の構造物である給水スパージャ55及びCS配管56を切断解体して撤去後(ステップ59F)、再度プラグ取付装置38に交換し(ステップ59G)、給水ノズル41F、CSノズル41Gをプラグで閉止する(ステップ59H)。次に、再度デブリ取出し装置58に交換し(ステップ59I)、共通装置39を下降して(ステップ59J)上部格子板18の取り出し(切断解体)(ステップ59K)を実施する。以下、同様のノズルプラグ閉止、注水、構造物を含めたデブリ取出しを順次繰り返して実施する。   In the work flow of this embodiment shown in the figure, the shared device 39 is first suspended in the RPV 11 (step 59A) and installed near the main steam nozzle 41C. After the plug is attached to the main steam nozzle 41C by the plug attachment device 38 (step 59B), it moves downward and the plug is similarly attached to the emergency condenser nozzle 41D (step 59B). Next, the shared device 39 is lowered (step 59C), and water is poured from the upper outer peripheral seal 30A of the shared device 39 at an appropriate position, and water filling is performed (step 59D). The plug attachment device 38 is replaced with the debris removal device 58 (step 59E), the water supply sparger 55 and the CS pipe 56, which are neighboring structures, are cut and disassembled and removed (step 59F), and then replaced with the plug attachment device 38 again. (Step 59G), the water supply nozzle 41F and the CS nozzle 41G are closed with plugs (Step 59H). Next, the debris take-out device 58 is replaced again (step 59I), the common device 39 is lowered (step 59J), and the upper lattice plate 18 is taken out (cut and disassembled) (step 59K). Thereafter, the same nozzle plug closing, water injection, and debris retrieval including the structure are sequentially repeated.

図4に、上部格子板18の取外しの状態図を示す。   FIG. 4 shows a state diagram of the removal of the upper lattice plate 18.

該図に示す如く、RPV11内に設置した共用装置39には、上部外周シール30Aから上方に注水により水が張られている。外周シールは上部外周シール30Aと下部外周シール30Bの上下2箇所に有しており、これは順次デブリ取出しの進捗により共用装置39をRPV11の内壁面を水張り状態で下降させるため、そのときに水のリークによる急激な水位低下を防止するため2重のシール構造としている。共用装置39の内側には、デブリ取出し装置58が配置されている。デブリ取出し装置58は、アブレッシブウオータージェット又はファイバーレーザ等の切断機能を有し、上部格子板18の切断解体を行う。   As shown in the figure, the common device 39 installed in the RPV 11 is filled with water by pouring water upward from the upper outer peripheral seal 30A. The outer peripheral seals are provided at two locations, the upper outer peripheral seal 30A and the lower outer peripheral seal 30B. This is because the common device 39 is lowered in a water-filled state on the inner wall surface of the RPV 11 in accordance with the progress of the debris extraction. In order to prevent a sudden drop in water level due to the leakage of water, a double seal structure is adopted. A debris retrieval device 58 is disposed inside the shared device 39. The debris extraction device 58 has a cutting function such as an abrasive water jet or a fiber laser, and cuts and disassembles the upper lattice plate 18.

次に図5乃至図35を用いてプラグ取付け装置及びその手順を説明する。   Next, the plug mounting apparatus and its procedure will be described with reference to FIGS.

図5に、プラグ取付装置38が設置された共用装置39をRPV11内に挿入した状態を示し、図6に、そのプラグ取付装置38の詳細を示す。該図に示す本実施例は、プラグ取付装置38内に同一高さレベルにある複数のノズルに対してプラグ45を準備しておき、一度のプラグ取付装置38のセットにて対象箇所のノズル部、例えば給水ノズル41F(円周上4箇所)を全て塞ぐ(閉止)ものである。   FIG. 5 shows a state in which the shared device 39 in which the plug attachment device 38 is installed is inserted into the RPV 11, and FIG. 6 shows details of the plug attachment device 38. In this embodiment shown in the figure, the plug 45 is prepared for a plurality of nozzles at the same height level in the plug mounting device 38, and the nozzle portion of the target portion is set by one set of the plug mounting device 38. For example, all the water supply nozzles 41F (four on the circumference) are closed (closed).

図5に示す如く、複数のノズル部41A−41Gを有するRPV11内に、プラグ取付装置38が設置された共用装置39が昇降装置42により降下されて挿入される。その際、共用装置39とRPV11の内壁間は、上部外周シール30A及び下部外周シール30Bでシールされている。また、共用装置39は、主旋回テーブル31と副旋回テーブル33を有し、それぞれは主旋回テーブルシール32及び副旋回テーブルシール34を介してプラグ取付装置38に対してシールされており、主旋回テーブル31と副旋回テーブル33を操作し、プラグ45を設置する位置を決めるものである。なお、43は、ケーブル・ホース送り機構である。   As shown in FIG. 5, the shared device 39 in which the plug mounting device 38 is installed is lowered and inserted into the RPV 11 having the plurality of nozzle portions 41 </ b> A- 41 </ b> G. At that time, the space between the shared device 39 and the inner wall of the RPV 11 is sealed by the upper outer peripheral seal 30A and the lower outer peripheral seal 30B. The common device 39 includes a main turning table 31 and a sub turning table 33, which are sealed to the plug mounting device 38 via a main turning table seal 32 and a sub turning table seal 34, respectively. The position where the plug 45 is installed is determined by operating the table 31 and the auxiliary turning table 33. Reference numeral 43 denotes a cable / hose feed mechanism.

一方、プラグ取付装置38は、図6に示す如く、容器54と、この容器54内に配置された複数のプラグ45を収納しているプラグボックス46と、プラグボックス46の下部に設置されているプラグ取出機構47と、プラグ把持機構50を先端に有するプラグ押付機構51と、プラグ把持機構50とプラグ押付機構51の姿勢を変更する旋回機構49と、プラグ把持機構50とプラグ押付機構51を回転させる回転機構48と、プラグ把持機構50とプラグ押付機構51を昇降させる昇降装置52とから概略構成されている。   On the other hand, as shown in FIG. 6, the plug attachment device 38 is installed in a container 54, a plug box 46 storing a plurality of plugs 45 disposed in the container 54, and a lower part of the plug box 46. The plug take-out mechanism 47, the plug pressing mechanism 51 having the plug holding mechanism 50 at the tip, the turning mechanism 49 for changing the attitude of the plug holding mechanism 50 and the plug pressing mechanism 51, the plug holding mechanism 50, and the plug pressing mechanism 51 are rotated. The rotating mechanism 48 is configured to include a plug holding mechanism 50 and a lifting device 52 that lifts and lowers the plug pressing mechanism 51.

そして、プラグボックス46の下部に設置されていうプラグ取出機構47でプラグ45の落下を防止し、更に、プラグ押付機構51をプラグボックス46内に挿入し、プラグ把持機構50にてプラグ45を掴み、プラグ取出機構47の落下防止を解除するようになっている。また、詳細説明は後述するが、プラグボックス46内からプラグ45を取出した後、プラグ取付装置38の昇降装置52にて下降させてプラグ45をRPV11内へ搬出し、RPV11内へ搬出したプラグ45を、ノズル部41A−41Gへ押込むために、旋回機構49及び回転機構48を用いて姿勢変更する。姿勢変更されたプラグ45を、プラグ押付機構51を用いてノズル部41A−41Gへ挿入し、ノズル部41A−41Gを塞ぐものである。   Then, the plug 45 is prevented from dropping by the plug take-out mechanism 47 installed at the lower part of the plug box 46, and the plug pressing mechanism 51 is inserted into the plug box 46, and the plug 45 is grasped by the plug gripping mechanism 50, The fall prevention of the plug take-out mechanism 47 is released. As will be described in detail later, after the plug 45 is taken out from the plug box 46, the plug 45 is lowered by the elevating device 52 of the plug mounting device 38 to carry out the plug 45 into the RPV 11, and the plug 45 carried into the RPV 11 is discharged. Is pushed into the nozzle portions 41A-41G using the turning mechanism 49 and the rotation mechanism 48. The plug 45 whose posture has been changed is inserted into the nozzle portion 41A-41G using the plug pressing mechanism 51, and the nozzle portion 41A-41G is closed.

次に、本発明の原子力プラントにおける原子炉圧力容器内水張り工法の実施例1におけるプラグ取付け作業に関するステップを、図7−図22を用いて説明する。   Next, steps related to the plug mounting operation in the first embodiment of the water pressure filling method in a reactor pressure vessel in the nuclear power plant of the present invention will be described with reference to FIGS.

該図に示す本実施例の原子力プラントにおける原子炉圧力容器内水張り工法は、特に図示しないが、炉心12の上部に設けられている構造物(シールドプラグ9、上蓋5及び10、蒸気乾燥器13、気水分離器14、上部格子板18、炉心シュラウド15等)を搬出するステップと、プラグ取付装置38又はデブリ取出し装置58が設置できる共用装置39をRPV11内のプラグ取付箇所まで搬入し、両者(共用装置39とRPV11の内壁)間を上部外周シール30A及び下部外周シール30Bでシールするステップ(図7参照)と、共用装置39内へプラグ取付装置38を搬入するステップ(図8参照)と、プラグ取付装置38を副旋回テーブルシール34へ挿入するステップ(図9参照)と、遮へいポート35を開状態とするステップ(図10参照)と、共用装置39内に搬入されたプラグ取付装置38を共用装置39の副旋回テーブル33へ着座するステップ(図11参照)と、副旋回テーブル33へ着座したプラグ取付装置38を主旋回テーブル31を旋回してプラグ取付装置38の位置決めを行うステップ(図12参照)と、副旋回テーブル33を旋回してプラグ取付装置38の位置決めを行うステップ(図13参照)と、主旋回テーブル31と副旋回テーブル33を旋回して位置決めされたプラグ取付装置38のプラグ把持機構50でプラグボックス46内の1個のプラグ45を受取るステップ(図14参照)と、プラグ取付装置38の昇降装置52によるRPV11内へプラグ45を搬入するステップ(図15参照)と、プラグ把持機構50で受取ったプラグ45をプラグ取付装置38の旋回機構49により再循環出口ノズル41Aと同等の位置に姿勢変更するステップ(図16参照)と、姿勢変更されたプラグ45をプラグ取付装置38の回転機構48を用いて再循環出口ノズル41Aの方向に向きを変えるために180°旋回するステップ(図17参照)と、再循環出口ノズル41Aの方向に向きを変えたプラグ45をプラグ取付装置38のプラグ押付機構51を用いて再循環出口ノズル41Aに押付け、再循環出口ノズル41Aを塞ぐステップ(図18参照)とからなる。なお、他のノズル部41B−41Gも上記ステップと同様の手順にてノズルの閉止を可能とする。   The reactor pressure vessel water filling method in the nuclear power plant of the present embodiment shown in the figure is not particularly shown, but structures (shield plug 9, upper lids 5 and 10, steam dryer 13) provided above the core 12. , The steam separator 14, the upper grid plate 18, the core shroud 15, etc.), and the common device 39 on which the plug mounting device 38 or the debris removal device 58 can be installed is transported to the plug mounting location in the RPV 11. A step (see FIG. 7) for sealing between the common device 39 and the inner wall of the RPV 11 with the upper outer peripheral seal 30A and the lower outer peripheral seal 30B (see FIG. 7), and a step for carrying the plug mounting device 38 into the common device 39 (see FIG. 8). , A step of inserting the plug attachment device 38 into the auxiliary turning table seal 34 (see FIG. 9), and a step of opening the shielding port 35. (See FIG. 10), a step (see FIG. 11) of seating the plug attachment device 38 carried into the common device 39 on the auxiliary turning table 33 of the common device 39, and a plug attachment device 38 seated on the auxiliary turning table 33. Turning the main turning table 31 to position the plug mounting device 38 (see FIG. 12), turning the auxiliary turning table 33 to position the plug mounting device 38 (see FIG. 13), A step of receiving one plug 45 in the plug box 46 by the plug gripping mechanism 50 of the plug mounting device 38 positioned by turning the turning table 31 and the auxiliary turning table 33 (see FIG. 14); The step of carrying the plug 45 into the RPV 11 by the lifting device 52 (see FIG. 15) and the plug 4 received by the plug gripping mechanism 50 Is changed to a position equivalent to the recirculation outlet nozzle 41A by the swiveling mechanism 49 of the plug mounting device 38 (see FIG. 16), and the plug 45 whose posture has been changed is re-used using the rotating mechanism 48 of the plug mounting device 38. The step of turning 180 ° to change the direction in the direction of the circulation outlet nozzle 41A (see FIG. 17), and the plug 45 having the direction changed in the direction of the recirculation outlet nozzle 41A is used by the plug pressing mechanism 51 of the plug mounting device 38. And pressing the recirculation outlet nozzle 41A to block the recirculation outlet nozzle 41A (see FIG. 18). The other nozzle portions 41B-41G can also close the nozzles in the same procedure as the above step.

プラグ取付装置38の搬出は、次のようにして行う。即ち、プラグ把持機構50によるプラグ45の把持を解除すると共に、プラグ取付装置38のプラグ把持機構50、旋回機構49、回転機構48及びプラグ押付機構51をプラグ取付装置38内に戻し(図19参照)、その後に、プラグ取付装置38の昇降装置52を用いてプラグ取付装置38を上昇(図20参照)させ、遮へいポート35を閉状態にし(図21参照)、共用装置39からプラグ取付装置38を搬出する(図22参照)。   The plug mounting device 38 is carried out as follows. That is, the gripping of the plug 45 by the plug gripping mechanism 50 is released, and the plug gripping mechanism 50, the turning mechanism 49, the rotating mechanism 48, and the plug pressing mechanism 51 of the plug mounting device 38 are returned into the plug mounting device 38 (see FIG. 19). Thereafter, the plug mounting device 38 is raised (see FIG. 20) using the lifting device 52 of the plug mounting device 38 (see FIG. 20), the shielding port 35 is closed (see FIG. 21), and the common device 39 to the plug mounting device 38 are closed. Is carried out (see FIG. 22).

プラグ取付装置38が搬出されたら、次の作業であるRPV11内のデブリを取出すためのデブリ取出し装置58と交換し、その後、共用装置39の上方に水を張り、デブリ取出し装置58による燃料デブリ28の取出しが行われるものである。   When the plug mounting device 38 is carried out, it is replaced with a debris take-out device 58 for taking out the debris in the RPV 11 which is the next operation, and then water is filled above the common device 39 so that the fuel debris 28 by the debris take-out device 58 is filled. Is taken out.

このような本実施例の原子力プラントにおける原子炉圧力容器内水張り工法とすることにより、RPV11内から燃料デブリ28を取出す等の各種作業を行う際に、共用装置39の上方に水が張られていることにから、オペフロ29上での放射線による周囲への影響を抑制して作業者の作業環境を良好にすると共に、切断解体等で発生するダストの拡散も防止することが可能となり、更には、原子炉建屋4内の遮へい体の削減も可能となり、原子炉建屋4に加わる荷重の軽量化が図れる効果もある。   By adopting the water filling method in the reactor pressure vessel in the nuclear power plant of this embodiment, when performing various operations such as taking out the fuel debris 28 from the RPV 11, water is stretched above the common device 39. Therefore, it is possible to improve the working environment of the operator by suppressing the influence on the surroundings by radiation on the operation floor 29, and to prevent the diffusion of dust generated by cutting and dismantling, etc. Further, the shielding body in the reactor building 4 can be reduced, and the load applied to the reactor building 4 can be reduced.

図23−35に、本発明の原子力プラントにおける原子炉圧力容器内水張り工法のプラグ取付け作業の実施例2を示す。図23は、プラグ取付装置38Aが設置された共用装置39をRPV11内に挿入した状態を、図24は、そのプラグ取付装置38Aの詳細を、原子力プラントにおける原子炉圧力容器内水張り工法のプラグ取付け作業の実施例2のステップを図25−図35にそれぞれ示す。該図に示す本実施例は、プラグ45を一度に設置するノズル部の数は1個とし、その都度、プラグ取付装置38Aを交換するものである。   FIG. 23-35 shows a second embodiment of the plug installation work of the water pressure filling method in the reactor pressure vessel in the nuclear power plant of the present invention. FIG. 23 shows a state in which the common device 39 in which the plug attachment device 38A is installed is inserted into the RPV 11, and FIG. 24 shows the details of the plug attachment device 38A, with the plug attachment of the reactor pressure vessel water filling method in a nuclear power plant. The steps of Working Example 2 are shown in FIGS. 25 to 35, respectively. In the present embodiment shown in the figure, the number of nozzle portions for installing the plug 45 at one time is one, and the plug mounting device 38A is replaced each time.

図23に示す如く、上述した複数のノズル部41A−41Gを有するRPV11内に、プラグ取付装置38Aが設置された共用装置39が昇降機構42により降下されて挿入される。その際、共用装置39とRPV11の内壁間は、上部外周シール30A及び下部外周シール30Bでシールされている。また、共用装置39は、主旋回テーブル31と副旋回テーブル33を有し、それぞれは主旋回テーブルシール32及び副旋回テーブルシール34を介してプラグ取付装置38Aに対してシールされており、主旋回テーブル31と副旋回テーブル33を操作し、プラグ45を設置する位置を決めるものである。なお、43は、ケーブル・ホース送り機構である。   As shown in FIG. 23, the shared device 39 in which the plug mounting device 38A is installed is lowered and inserted into the RPV 11 having the plurality of nozzle portions 41A-41G described above. At that time, the space between the shared device 39 and the inner wall of the RPV 11 is sealed by the upper outer peripheral seal 30A and the lower outer peripheral seal 30B. The common device 39 includes a main turning table 31 and a sub turning table 33, which are sealed to the plug mounting device 38A via a main turning table seal 32 and a sub turning table seal 34, respectively. The position where the plug 45 is installed is determined by operating the table 31 and the auxiliary turning table 33. Reference numeral 43 denotes a cable / hose feed mechanism.

一方、プラグ取付装置38Aは、図24に示す如く、容器54と、この容器54内に配置された1個のプラグ45を把持するプラグ把持機構50を先端に有するプラグ押付機構51とから概略構成されている。   On the other hand, as shown in FIG. 24, the plug attachment device 38A is schematically configured from a container 54 and a plug pressing mechanism 51 having a plug gripping mechanism 50 for gripping one plug 45 disposed in the container 54 at the tip. Has been.

そして、主旋回テーブル31と副旋回テーブル33を操作し、プラグ45を設置する位置を決め、プラグ押付機構51を用いてプラグ45を各ノズル部41A−41Gへ挿入し、それぞれのノズル部41A−41Gを塞ぐものである。   Then, the main turning table 31 and the sub turning table 33 are operated, the position where the plug 45 is installed is determined, the plug 45 is inserted into each nozzle part 41A-41G using the plug pressing mechanism 51, and each nozzle part 41A- 41G is blocked.

次に、本発明の原子力プラントにおける原子炉圧力容器内水張り工法の実施例2におけるプラグ取付け作業のステップを、図25−図35を用いて説明する。   Next, the steps of the plug mounting work in the second embodiment of the water pressure filling method in the reactor pressure vessel in the nuclear power plant of the present invention will be described with reference to FIGS.

該図に示す本実施例の原子力プラントにおける原子炉圧力容器内水張り工法は、特に図示しないが、炉心12の上部に設けられている構造物(シールドプラグ9、上蓋5及び10、蒸気乾燥器13、気水分離器14、上部格子板18、炉心シュラウド15等)を搬出するステップと、プラグ取付装置38A又はデブリ取出し装置(図示せず)が設置できる共用装置39をRPV11内のプラグ取付箇所まで搬入し、両者(共用装置39とRPV11の内壁)間を上部外周シール30A及び下部外周シール30Bでシールするステップ(図25参照)と、プラグ取付装置38Aのプラグ把持機構50で1つのプラグ45を把持しているプラグ取付装置38Aを共用装置39内へ搬入するステップ(図26参照)と、プラグ取付装置38Aを副旋回テーブルシール34へ挿入するステップ(図27参照)と、遮へいポート35を開状態とするステップ(図28参照)と、共用装置39内に搬入されたプラグ取付装置38Aを共用装置39の副旋回テーブル33へ着座するステップ(図29参照)と、副旋回テーブル33へ着座したプラグ取付装置38Aを主旋回テーブル31を旋回してプラグ取付装置38Aの位置決めを行うステップ(図30参照)と、位置決めされたプラグ把持機構50で把持されている1つのプラグ45を、プラグ取付装置38Aのプラグ押付機構51を用いて再循環出口ノズル41Aに押付け塞ぐステップ(図31参照)とからなる。そして、プラグ取付装置38Aを次のプラグ取付装置38Aと交換し、交換したプラグ取付装置38Aのプラグ押付機構51を用いて再循環入口ノズル41Bに押付けて塞ぐ。同一円周上にある残りのノズル部は、本手順と同手順を繰り返し行い、共用装置39の上方に水を張るものである。   The reactor pressure vessel water filling method in the nuclear power plant of the present embodiment shown in the figure is not particularly shown, but structures (shield plug 9, upper lids 5 and 10, steam dryer 13) provided above the core 12. , A steam separator 14, an upper lattice plate 18, a core shroud 15, etc.) and a common device 39 on which a plug mounting device 38 A or a debris extraction device (not shown) can be installed up to the plug mounting location in the RPV 11. A step (see FIG. 25) of carrying in and sealing between the two (the common device 39 and the inner wall of the RPV 11) with the upper outer peripheral seal 30A and the lower outer peripheral seal 30B (see FIG. 25), and one plug 45 with the plug gripping mechanism 50 of the plug mounting device 38A A step (see FIG. 26) for carrying the grasped plug attachment device 38A into the common device 39, and the auxiliary attachment of the plug attachment device 38A. The step of inserting into the table seal 34 (see FIG. 27), the step of opening the shielding port 35 (see FIG. 28), and the plug mounting device 38A carried into the shared device 39 are connected to the auxiliary turning table of the shared device 39. A step (see FIG. 29) for seating on 33, a step (see FIG. 30) for positioning the plug mounting device 38A by turning the plug mounting device 38A seated on the auxiliary turning table 33 on the main turning table 31. This step comprises the step of pressing and closing one plug 45 held by the plug holding mechanism 50 against the recirculation outlet nozzle 41A using the plug pressing mechanism 51 of the plug mounting device 38A (see FIG. 31). Then, the plug mounting device 38A is replaced with the next plug mounting device 38A, and the plug mounting device 38A is pressed against the recirculation inlet nozzle 41B using the plug pressing mechanism 51 of the replaced plug mounting device 38A. The remaining nozzles on the same circumference repeat the same procedure as this procedure, and water is placed above the shared device 39.

1つの再循環出口ノズル41Aをプラグ45で塞いだ後のプラグ取付装置38Aの搬出は、次のようにして行う(他のノズル部41B−41Gをプラグ45で塞いだ後も同様である)。即ち、1つのプラグ45で再循環出口ノズル41Aを塞いだ後にプラグ把持機構50によるプラグ45の把持を解除し、プラグ取付装置38Aのプラグ把持機構50及びプラグ押付機構51をプラグ取付装置38A内に戻し(図32参照)、その後、共用装置39の昇降機構42を用いてプラグ取付装置38Aを上昇(図33参照)させ、遮へいポート35を閉状態にし(図34参照)、共用装置39からプラグ取付装置38Aを搬出する(図35参照)。これをノズル部の数だけ繰り返し行った後に、デブリ取出し装置と交換し、その後、共用装置39の上方に水を張り、デブリ取出し装置58による燃料デブリ28の取出しが行われるものである。   The plug attachment device 38A is unloaded after one recirculation outlet nozzle 41A is plugged with the plug 45 (the same applies after the other nozzle portions 41B-41G are plugged with the plug 45). That is, after plugging the recirculation outlet nozzle 41A with a single plug 45, the plug 45 is released from the plug holding mechanism 50, and the plug holding mechanism 50 and the plug pressing mechanism 51 of the plug mounting device 38A are placed in the plug mounting device 38A. Then, the plug mounting device 38A is raised (see FIG. 33) by using the lifting mechanism 42 of the common device 39, and the shielding port 35 is closed (see FIG. 34). The attachment device 38A is carried out (see FIG. 35). After this is repeated for the number of nozzles, it is replaced with a debris take-out device, and then water is filled above the shared device 39, and the fuel debris 28 is taken out by the debris take-out device 58.

このような本実施例の原子力プラントにおける原子炉圧力容器内水張り工法とすることにより、実施例1と同様な効果を得ることができる。   By adopting the water filling method in the reactor pressure vessel in the nuclear power plant of this embodiment, the same effect as that of Embodiment 1 can be obtained.

なお、本発明は上記した実施例に限定されるものではなく、様々な変形例が含まれる。例えば、上記した実施例は本発明を分かりやすく説明するために詳細に説明したものであり、必ずしも説明した全ての構成を備えるものに限定されるものではない。また、ある実施例の構成の一部を他の実施例の構成に置き換えることが可能であり、また、ある実施例の構成に他の実施例の構成を加えることも可能である。また、各実施例の構成の一部について、他の構成の追加・削除・置換をすることが可能である。   In addition, this invention is not limited to an above-described Example, Various modifications are included. For example, the above-described embodiments have been described in detail for easy understanding of the present invention, and are not necessarily limited to those having all the configurations described. Further, a part of the configuration of one embodiment can be replaced with the configuration of another embodiment, and the configuration of another embodiment can be added to the configuration of one embodiment. Further, it is possible to add, delete, and replace other configurations for a part of the configuration of each embodiment.

1…沸騰水型原子力プラント、2…原子炉、3…原子炉格納容器(PCV)、4…原子炉建屋、5、10…上蓋、6…ドライウェル、7…圧力抑制室、8…ベント通路、9…シールドプラグ、11…原子炉圧力容器(RPV)、12…炉心、13…蒸気乾燥器、14…気水分離器、15…炉心シュラウド、16…燃料集合体、17…炉心支持板、18…上部格子板、19…制御棒案内管、21…制御棒駆動機構ハウジング、22…下鏡、23…コンクリートマット、24…ペデスタル、25…γ線遮蔽体、26…ドライヤ・セパレータプール(DSP)、27…使用済燃料貯蔵プール(SFP)、28…燃料デブリ、29…オペフロ、30A…上部外周シール、30B…下部外周シール、31…主旋回テーブル、32…主旋回テーブルシール、33…副旋回テーブル、34…副旋回テーブルシール、35…遮へいポート、38、38A…プラグ取付装置、39…共用装置、41A…再循環出口ノズル、41B…再循環入口ノズル、41C…主蒸気用ノズル、41D…非常用復水器ノズル、41E…計測ノズル、41F…給水ノズル、41G…CSノズル、42…共用装置の昇降機構、43…ケーブル・ホース送り機構、45…プラグ、46…プラグボックス、47…プラグ取出機構、48…回転機構、49…旋回機構、50…プラグ把持機構、51…プラグ押付機構、52…プラグ取付装置の昇降装置、54…容器、55…給水スパージャ、56…CS配管、57…ジェットポンプ、58…デブリ取出し装置。   DESCRIPTION OF SYMBOLS 1 ... Boiling water type nuclear power plant, 2 ... Reactor, 3 ... Reactor containment vessel (PCV), 4 ... Reactor building, 5, 10 ... Upper lid, 6 ... Dry well, 7 ... Pressure suppression chamber, 8 ... Vent passage , 9 ... Shield plug, 11 ... Reactor pressure vessel (RPV), 12 ... Core, 13 ... Steam dryer, 14 ... Steam separator, 15 ... Core shroud, 16 ... Fuel assembly, 17 ... Core support plate, 18 ... Upper lattice plate, 19 ... Control rod guide tube, 21 ... Control rod drive mechanism housing, 22 ... Lower mirror, 23 ... Concrete mat, 24 ... Pedestal, 25 ... Gamma ray shield, 26 ... Dryer separator pool (DSP) ), 27 ... spent fuel storage pool (SFP), 28 ... fuel debris, 29 ... operation floor, 30A ... upper outer periphery seal, 30B ... lower outer periphery seal, 31 ... main turning table, 32 ... main turning table seal 33 ... Sub-turn table, 34 ... Sub-turn table seal, 35 ... Shield port, 38, 38A ... Plug mounting device, 39 ... Shared device, 41A ... Recirculation outlet nozzle, 41B ... Recirculation inlet nozzle, 41C ... For main steam Nozzle, 41D ... Emergency condenser nozzle, 41E ... Measurement nozzle, 41F ... Water supply nozzle, 41G ... CS nozzle, 42 ... Elevating mechanism of common device, 43 ... Cable / hose feed mechanism, 45 ... Plug, 46 ... Plug box , 47 ... Plug extraction mechanism, 48 ... Rotation mechanism, 49 ... Swing mechanism, 50 ... Plug gripping mechanism, 51 ... Plug pressing mechanism, 52 ... Elevating device for plug mounting device, 54 ... Container, 55 ... Water supply sparger, 56 ... CS Piping, 57 ... jet pump, 58 ... debris removal device.

Claims (7)

原子力プラントにおける原子炉圧力容器内水張り工法であって、
少なくともプラグ取付装置又はデブリ取出し装置が設置できる共用装置を原子炉圧力容器内に挿入して両者間をシールし、前記共用装置の上方に水を張ることを特徴とする原子力プラントにおける原子炉圧力容器内水張り工法。
A water pressure filling method in a reactor pressure vessel in a nuclear power plant,
A reactor pressure vessel in a nuclear power plant characterized in that at least a common device on which a plug mounting device or a debris extraction device can be installed is inserted into the reactor pressure vessel, the space between both is sealed, and water is filled above the common device. Inland water filling method.
請求項1に記載の原子力プラントにおける原子炉圧力容器内水張り工法において、
前記原子炉圧力容器内の構造物搬出に伴ない前記原子炉圧力容器内のノズルの高さ位置が水張り位置に相当する場合に、プラグ取付け装置を用いて前記原子炉圧力容器のノズル部をあらかじめプラグで塞ぎ、しかる後に、前記共用装置の上方に水を張ることを特徴とする原子力プラントにおける原子炉圧力容器内水張り工法。
In the method of filling a reactor pressure vessel in a nuclear power plant according to claim 1,
When the height position of the nozzle in the reactor pressure vessel corresponds to the water filling position when the structure in the reactor pressure vessel is carried out, the nozzle portion of the reactor pressure vessel is previously set using a plug attachment device. A method for filling a reactor pressure vessel in a nuclear power plant, comprising plugging with a plug and then filling water above the shared device.
請求項1又は2に記載の原子力プラントにおける原子炉圧力容器内水張り工法において、
前記原子炉圧力容器内水張り工法は、前記共用装置を前記原子炉圧力容器内のプラグ取付箇所まで搬入して両者間をシールするステップと、前記共用装置内へ前記プラグ取付装置を搬入するステップと、前記共用装置内に注水し水張りするステップと、水張り後に原子炉圧力容器内の構造物を取り出すステップを有し、順次当該ステップを繰り返すことで、前記原子炉圧力容器内の構造物を炉心下部まで撤去することを特徴とする原子力プラントにおける原子炉圧力容器内水張り工法。
In the method of filling a reactor pressure vessel in a nuclear power plant according to claim 1 or 2,
The water pressure filling method in the reactor pressure vessel includes a step of bringing the common device into a plug attachment location in the reactor pressure vessel and sealing between the two, and a step of carrying the plug attachment device into the common device; A step of pouring water into the shared device and filling it with water, and a step of taking out the structure in the reactor pressure vessel after filling with water, and repeating the steps in order to remove the structure in the reactor pressure vessel at the lower part of the core Water reactor construction method in a nuclear reactor pressure vessel in a nuclear power plant
請求項1乃至3のいずれか1項に記載の原子力プラントにおける原子炉圧力容器内水張り工法において、
前記原子炉圧力容器内水張り工法は、前記炉心上部に設けられている構造物を搬出するステップと、前記プラグ取付装置又は前記デブリ取出し装置が設置できる前記共用装置を前記原子炉圧力容器内のプラグ取付箇所まで搬入して両者間をシールするステップと、前記共用装置内へ前記プラグ取付装置を搬入するステップと、前記共用装置内に搬入された前記プラグ取付装置を前記共用装置の副旋回テーブルへ着座するステップと、前記副旋回テーブルへ着座した前記プラグ取付装置を主旋回テーブルを旋回して前記プラグ取付装置の位置決めを行い前記プラグ取付装置のプラグ把持機構でプラグを受取るステップと、前記プラグ把持機構で受取った前記プラグを前記プラグ取付装置の旋回機構により前記ノズル部と同等の位置に姿勢変更するステップと、姿勢変更された前記プラグを前記プラグ取付装置の回転機構を用いて前記ノズル部の方向に向きを変えるステップと、前記ノズル部の方向に向きを変えた前記プラグを前記プラグ取付装置のプラグ押付機構を用いて前記ノズル部に押付け該ノズル部を塞ぐステップと、前記ノズル部を前記プラグで塞いだ後、前記共用装置の上方に水を張るステップとからなることを特徴とする原子力プラントにおける原子炉圧力容器内水張り工法。
In the method of filling a reactor pressure vessel in a nuclear power plant according to any one of claims 1 to 3,
The water pressure filling method in the reactor pressure vessel includes a step of unloading the structure provided in the upper part of the core, and the common device in which the plug mounting device or the debris extraction device can be installed as a plug in the reactor pressure vessel. A step of carrying in to the attachment point and sealing between the two, a step of carrying in the plug attachment device into the common device, and the plug attachment device carried into the common device to the auxiliary turning table of the common device A step of seating, a step of positioning the plug attachment device by turning the plug attachment device seated on the auxiliary turning table on a main turning table, and receiving a plug by a plug grasping mechanism of the plug attachment device; The posture of the plug received by the mechanism is changed to a position equivalent to the nozzle by the turning mechanism of the plug mounting device. A step of changing the orientation of the plug whose posture has been changed in the direction of the nozzle portion using a rotation mechanism of the plug attachment device, and the direction of the plug changed in the direction of the nozzle portion of the plug attachment device A nuclear power plant comprising: a step of pressing against the nozzle portion using a plug pressing mechanism; and a step of filling water above the common device after the nozzle portion is closed with the plug. In-reactor pressure vessel water filling method.
請求項4に記載の原子力プラントにおける原子炉圧力容器内水張り工法において、
前記プラグで前記ノズル部を塞いだ後に前記プラグ把持機構による前記プラグの把持を解除すると共に、前記プラグ取付装置の前記プラグ把持機構、前記旋回機構、前記回転機構及び前記プラグ押付機構を前記プラグ取付装置内に戻した後に、前記プラグ取付装置の昇降機構を用いて前記プラグ取付装置を上昇させて前記共用装置から前記プラグ取付装置を搬出して前記デブリ取出し装置と交換し、その後、前記共用装置の上方に水を張ることを特徴とする原子力プラントにおける原子炉圧力容器内水張り工法。
In the method of filling a reactor pressure vessel in a nuclear power plant according to claim 4,
After plugging the nozzle portion with the plug, the plug gripping mechanism releases the plug, and the plug gripping mechanism, the turning mechanism, the rotating mechanism, and the plug pressing mechanism of the plug mounting device are plug-attached. After returning to the inside of the apparatus, the plug mounting apparatus is lifted by using a lifting mechanism of the plug mounting apparatus, the plug mounting apparatus is taken out from the shared apparatus and replaced with the debris retrieval apparatus, and then the shared apparatus Water filling method in a reactor pressure vessel in a nuclear power plant characterized by filling water above
請求項1乃至3のいずれか1項に記載の原子力プラントにおける原子炉圧力容器内水張り工法において、
前記原子炉圧力容器内水張り工法は、前記炉心上部に設けられている構造物を搬出するステップと、前記プラグ取付装置又は前記デブリ取出し装置が設置できる前記共用装置を前記原子炉圧力容器内のプラグ取付箇所まで搬入して両者間をシールするステップと、前記プラグ取付装置のプラグ把持機構で1つの前記プラグを把持している前記プラグ取付装置を前記共用装置内へ搬入するステップと、前記共用装置内に搬入された前記プラグ取付装置を前記共用装置の副旋回テーブルへ着座するステップと、前記副旋回テーブルへ着座した前記プラグ取付装置を主旋回テーブルを旋回して前記プラグ取付装置の位置決めを行うステップと、位置決めされた前記プラグ把持機構で把持されている1つの前記プラグを、前記プラグ取付装置のプラグ押付機構を用いて前記ノズル部に押付け塞ぐステップと、前記プラグ取付装置を次のプラグ取付装置と交換し、交換した前記プラグ取付装置のプラグ押付機構を用いて前記ノズル部に押付け塞ぐステップを前記ノズル部の数だけ繰り返し行うステップと、全ての前記ノズル部を前記プラグで塞いだ後、前記共用装置の上方に水を張るステップとからなることを特徴とする原子力プラントにおける原子炉圧力容器内水張り工法。
In the method of filling a reactor pressure vessel in a nuclear power plant according to any one of claims 1 to 3,
The water pressure filling method in the reactor pressure vessel includes a step of unloading the structure provided in the upper part of the core, and the common device in which the plug mounting device or the debris extraction device can be installed as a plug in the reactor pressure vessel. A step of carrying in to a mounting location and sealing between the two, a step of carrying in the plug mounting device holding one plug by a plug gripping mechanism of the plug mounting device into the shared device, and the shared device A step of seating the plug mounting device carried into the sub-turning table of the shared device, and a step of turning the plug mounting device seated on the sub-turning table on the main turning table to position the plug mounting device. One plug held by the plug holding mechanism positioned and the plug of the plug mounting device A step of pressing and closing the nozzle portion using an attaching mechanism, a step of replacing the plug attaching device with the next plug attaching device, and a step of pushing and closing the nozzle portion using the plug pushing mechanism of the replaced plug attaching device. Water filling in a nuclear reactor pressure vessel in a nuclear power plant, comprising: repeatedly performing as many as the number of nozzle portions; and filling all the nozzle portions with the plug and then filling water above the shared device. Construction method.
請求項6に記載の原子力プラントにおける原子炉圧力容器内水張り工法において、
1つの前記プラグで前記ノズル部を塞いだ後に前記プラグ把持機構による前記プラグの把持を解除し、前記プラグ取付装置の前記プラグ把持機構及び前記プラグ押付機構を前記プラグ取付装置内に戻した後、前記共用装置の昇降機構を用いて前記プラグ取付装置を上昇させて前記共用装置から前記プラグ取付装置を搬出し、これを前記ノズル部の数だけ繰り返した後に、前記デブリ取出し装置と交換し、その後、前記共用装置の上方に水を張ることを特徴とする原子力プラントにおける原子炉圧力容器内水張り工法。
In the method of filling a reactor pressure vessel in a nuclear power plant according to claim 6,
After closing the nozzle portion with one of the plugs, releasing the plug by the plug gripping mechanism, and returning the plug gripping mechanism and the plug pressing mechanism of the plug mounting device into the plug mounting device; The plug mounting device is lifted by using the lifting mechanism of the shared device to carry out the plug mounting device from the shared device, and after repeating this by the number of the nozzle portions, the debris removing device is replaced. Water filling method in a nuclear reactor pressure vessel in a nuclear power plant, wherein water is filled above the common device.
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