JPH10123278A - Repairing device and method for reactor - Google Patents

Repairing device and method for reactor

Info

Publication number
JPH10123278A
JPH10123278A JP8281014A JP28101496A JPH10123278A JP H10123278 A JPH10123278 A JP H10123278A JP 8281014 A JP8281014 A JP 8281014A JP 28101496 A JP28101496 A JP 28101496A JP H10123278 A JPH10123278 A JP H10123278A
Authority
JP
Japan
Prior art keywords
reactor
storage pit
equipment storage
water
well
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.)
Pending
Application number
JP8281014A
Other languages
Japanese (ja)
Inventor
Tomoyuki Ito
藤 智 之 伊
Motohiko Kimura
村 元比古 木
Arata Ito
藤 新 伊
Katsuhiko Sato
藤 勝 彦 佐
Yutaka Togasawa
裕 戸賀沢
Etsuro Igarashi
越 郎 五十嵐
Mitsuaki Shimamura
村 光 明 島
Yasuhiro Yuguchi
口 康 弘 湯
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba 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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP8281014A priority Critical patent/JPH10123278A/en
Publication of JPH10123278A publication Critical patent/JPH10123278A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PROBLEM TO BE SOLVED: To provide a repairing device and method for reactor capable of conducting the repairing work for reactor in vapor phase space by storing in core structure with high radioactivity in water. SOLUTION: Provided are an isolating wall 1 built on the boundary between a component storage pit 102 and a reactor well 101 for damming up water in the component storage pit 102 and an isolating wall support means 2 having a part touching the isolation wall 1 and a part touching the inner wall of the reactor well. By receiving the hydraulic pressure added on the isolating wall 1 by the water in the component storage pit 102 with the inner wall 106 of the reactor well 101 by way of the isolating wall support means 2, the isolating wall 1 is supported.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は、原子炉の補修装置
及び方法に係わり、特に、気相空間において原子炉の補
修作業を行うための原子炉の補修装置及び方法に関す
る。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an apparatus and method for repairing a nuclear reactor, and more particularly to an apparatus and method for repairing a nuclear reactor for repairing a reactor in a gas phase space.

【0002】[0002]

【従来の技術】沸騰水型原子炉(BWR)の定期検査等
において原子炉圧力容器(原子炉容器)の内部の検査や
補修等を行う場合には、原子炉圧力容器の上蓋を開放
し、炉内構造物を原子炉容器の外部に取り出す必要があ
る。その際、炉心、炉内構造物、原子炉圧力容器等は放
射能が非常に高いため、原子炉圧力容器の上部に形成さ
れた原子炉ウェル及びこれに隣接して形成された機器貯
蔵ピット(ドライヤ・セパレータピット)に水を注入し
て放射線を遮蔽するようにしている。
2. Description of the Related Art In the case of inspecting or repairing the inside of a reactor pressure vessel (reactor vessel) during a periodic inspection or the like of a boiling water reactor (BWR), an upper lid of the reactor pressure vessel is opened, The reactor internals need to be taken out of the reactor vessel. At this time, the reactor core, reactor internals, reactor pressure vessel, etc. have extremely high radioactivity, so the reactor well formed on the upper part of the reactor pressure vessel and the equipment storage pit ( Water is injected into the dryer / separator pit) to shield radiation.

【0003】そして、原子炉圧力容器の内部から取り出
された蒸気乾燥器(ドライヤ)、気水分離器(セパレー
タ)等の炉内構造物は、機器貯蔵ピットにおいて水中で
保管される。また、原子炉圧力容器の内部から取り出さ
れた使用済燃料は、原子炉ウェルに連通している燃料プ
ールにおいて水中で保管され、一定期間冷却される。こ
こで、燃料プールは使用済燃料を一定期間にわたって冷
却するために使用されるものであるため、原子炉ウェル
と燃料プールとの間は隔離手段によって適宜水密に隔離
できるようになっており、原子炉の運転を再開した後に
おいても燃料プール内を水で満たしておくことができ
る。一方、原子炉ウェルと機器貯蔵ピットとの間を水密
に隔離するための手段は設けられていない。
[0003] Furnace structures such as a steam dryer (dryer) and a steam separator (separator) taken out of the reactor pressure vessel are stored underwater in an equipment storage pit. The spent fuel removed from the reactor pressure vessel is stored in water in a fuel pool communicating with the reactor well and cooled for a certain period. Here, since the fuel pool is used to cool the spent fuel for a certain period of time, the separation between the reactor well and the fuel pool can be appropriately water-tightly separated by a separating means. The fuel pool can be filled with water even after restarting the operation of the furnace. On the other hand, no means is provided for watertight isolation between the reactor well and the equipment storage pit.

【0004】[0004]

【発明が解決しようとする課題】上述したように、原子
炉ウェルと機器貯蔵ピットとの間を水密に隔離するため
の手段がないので、原子炉ウェル及び原子炉圧力容器の
内部を気相空間にして炉内の点検、補修作業等を実施す
るためには、原子炉ウェルのみならず、機器貯蔵ピット
をも気相空間にする必要がある。
As described above, since there is no means for providing watertight isolation between the reactor well and the equipment storage pit, the inside of the reactor well and the reactor pressure vessel are in a gas phase space. In order to perform inspection and repair work inside the reactor, it is necessary to make not only the reactor well but also the equipment storage pit into a gas phase space.

【0005】ところが、機器貯蔵ピット内には蒸気乾燥
器、気水分離器等の放射能の高い炉内構造物が保管され
ているので、機器貯蔵ピット内の水を排出して気相空間
にしてしまうと操作床(オペレーション・フロア)にお
ける放射線の線量が非常に高くなってしまうという問題
がある。
[0005] However, since high-activity internal structures such as a steam dryer and a steam separator are stored in the equipment storage pit, the water in the equipment storage pit is discharged to form a gas phase space. In such a case, there is a problem that the radiation dose on the operation floor becomes extremely high.

【0006】そこで、本発明の目的は、上述した問題点
を解消し、放射能の高い炉内構造物を水中で保管しつ
つ、気相空間において原子炉の補修作業を行うことがで
きる原子炉の補修装置及び方法を提供することにある。
Accordingly, an object of the present invention is to solve the above-mentioned problems and to provide a reactor capable of repairing a reactor in a gas phase space while storing a highly radioactive internal structure in water. To provide a repair device and method.

【0007】[0007]

【課題を解決するための手段】請求項1記載の発明によ
る原子炉の補修装置は、原子炉容器の上方に形成された
原子炉ウェルと、この原子炉ウェルに隣接して形成され
た機器貯蔵ピットとを備えた原子炉を補修するための原
子炉の補修装置において、前記機器貯蔵ピット内の水を
堰き止めるために前記機器貯蔵ピットと前記原子炉ウェ
ルとの境界に立設される隔離壁と、前記隔離壁に当接さ
れる部分及び前記原子炉ウェルの内壁面に当接される部
分を有する隔離壁支持手段と、を備え、前記機器貯蔵ピ
ット内の水によって前記隔離壁に加えられる水圧を前記
隔離壁支持手段を介して前記原子炉ウェルの内壁面で受
けることによって前記隔離壁を支持するようにしたこと
を特徴とする。
According to the first aspect of the present invention, there is provided a repair apparatus for a nuclear reactor, comprising: a reactor well formed above a reactor vessel; and an equipment storage formed adjacent to the reactor well. A reactor repairing apparatus for repairing a reactor having a pit, wherein an isolation wall erected at a boundary between the equipment storage pit and the reactor well to block water in the equipment storage pit. And isolation wall support means having a portion abutting against the isolation wall and a portion abutting against the inner wall surface of the reactor well, wherein the isolation wall is added to the isolation wall by water in the equipment storage pit. The isolation wall is supported by receiving a water pressure on the inner wall surface of the reactor well via the isolation wall support means.

【0008】請求項2記載の発明による原子炉の補修装
置は、前記隔離壁の縁部に水密シール部材を設けたこと
を特徴とする。
A repair apparatus for a nuclear reactor according to a second aspect of the present invention is characterized in that a watertight seal member is provided at an edge of the isolation wall.

【0009】請求項3記載の発明による原子炉の補修装
置は、原子炉容器の上方に形成された原子炉ウェルと、
この原子炉ウェルに隣接して形成された機器貯蔵ピット
とを備えた原子炉を補修するための原子炉の補修装置に
おいて、前記原子炉容器のフランジ部の外径よりも大き
な内径を有し、前記原子炉容器の真上の空間を周囲から
隔離するために前記原子炉ウェル内に配置される筒状隔
離体と、前記筒状隔離体の下端部に周設された水密シー
ル部材と、を備えたことを特徴とする。
A repair apparatus for a nuclear reactor according to the invention according to claim 3 comprises a reactor well formed above a reactor vessel;
In a reactor repair device for repairing a reactor having an equipment storage pit formed adjacent to the reactor well, the repair device has an inner diameter larger than an outer diameter of a flange portion of the reactor vessel, A cylindrical separator disposed in the reactor well to isolate a space directly above the reactor vessel from the surroundings, and a watertight seal member provided around a lower end of the cylindrical separator. It is characterized by having.

【0010】請求項4記載の発明による原子炉の補修装
置は、原子炉容器の上方に形成された原子炉ウェルと、
この原子炉ウェルに隣接して形成された機器貯蔵ピット
とを備えた原子炉を補修するための原子炉の補修装置に
おいて、前記機器貯蔵ピットに移送された炉内構造物の
全体を上方から覆うようにして配置され、前記炉内構造
物全体を内部に収納して周囲から隔離する遮蔽カバー部
材と、前記遮蔽カバー部材の下部に形成され、前記遮蔽
カバー部材の内部と外部との間に流体流路を形成する開
口部と、前記遮蔽カバー部材の上部に設けられ、前記遮
蔽カバー部材の内部と外部との間に必要に応じて流体流
路を形成するための弁手段と、を備えたことを特徴とす
る。
[0010] According to a fourth aspect of the present invention, there is provided a repair apparatus for a nuclear reactor, comprising: a reactor well formed above a reactor vessel;
In a repair apparatus for a reactor for repairing a reactor having an equipment storage pit formed adjacent to the reactor well, the entire reactor internal structure transferred to the equipment storage pit is covered from above. A shielding cover member that is arranged in such a manner as to house the entire furnace internal structure therein and isolate it from the surroundings, and a fluid cover formed between the inside and the outside of the shielding cover member formed below the shielding cover member. An opening for forming a flow path, and valve means provided at an upper portion of the shielding cover member for forming a fluid flow path between the inside and the outside of the shielding cover member as necessary. It is characterized by the following.

【0011】請求項5記載の発明による原子炉の補修装
置は、前記弁手段に前記遮蔽カバー部材の内部を減圧す
るためのポンプ手段を接続したことを特徴とする。
According to a fifth aspect of the present invention, in the repair apparatus for a nuclear reactor, a pump means for reducing the pressure inside the shielding cover member is connected to the valve means.

【0012】請求項6記載の発明による原子炉の補修装
置は、前記遮蔽カバー部材の高さは、前記機器貯蔵ピッ
トに前記遮蔽カバー部材を配置した場合に前記遮蔽カバ
ー部材の上端が操作床のレベルよりも高い位置にあるよ
うに設定されていることを特徴とする。
According to a sixth aspect of the present invention, in the repair device for a nuclear reactor, the height of the shield cover member is such that when the shield cover member is disposed in the equipment storage pit, the upper end of the shield cover member is located on the operating floor. It is characterized in that it is set to be at a position higher than the level.

【0013】請求項7記載の発明による原子炉の補修装
置は、原子炉容器の上方に形成された原子炉ウェルと、
この原子炉ウェルに隣接して形成された機器貯蔵ピット
とを備えた原子炉を補修するための原子炉の補修装置に
おいて、炉内構造物を内部に収納するために前記機器貯
蔵ピットに配置される、上面が開放された遮蔽容器と、
前記遮蔽容器の下部に設けられ、前記遮蔽容器の内部と
外部との間に必要に応じて流体流路を形成するための弁
手段と、を備えたことを特徴とする。
[0013] A repair apparatus for a nuclear reactor according to the invention according to claim 7 comprises: a reactor well formed above a reactor vessel;
In a repair apparatus for a reactor for repairing a reactor having an equipment storage pit formed adjacent to the reactor well, the equipment storage pit is disposed in the equipment storage pit to house a reactor internal structure therein. A shielding container with an open top,
Valve means for providing a fluid flow path between the inside and the outside of the shielding container as needed, provided at a lower portion of the shielding container.

【0014】請求項8記載の発明による原子炉の補修装
置は、前記遮蔽容器の上端に前記遮蔽容器と同径の筒状
部材を取り外し可能且つ水密に連接したことを特徴とす
る。
According to an eighth aspect of the present invention, there is provided the repair apparatus for a nuclear reactor, wherein a cylindrical member having the same diameter as the shielding container is detachably and watertightly connected to the upper end of the shielding container.

【0015】請求項9記載の発明による原子炉の補修装
置は、前記遮蔽容器及び前記筒状部材の高さは、前記機
器貯蔵ピットに前記遮蔽容器及び前記筒状部材を設置し
た場合に前記筒状部材の上端が操作床のレベルよりも高
い位置にあるように設定されており、前記弁手段に、前
記遮蔽容器の内部に水を注入するためのポンプ手段を接
続したことを特徴とする。
According to a ninth aspect of the present invention, in the repair apparatus for a nuclear reactor, the height of the shielding container and the cylindrical member may be reduced when the shielding container and the cylindrical member are installed in the equipment storage pit. The upper end of the shaped member is set at a position higher than the level of the operation floor, and a pump means for injecting water into the shielding container is connected to the valve means.

【0016】請求項10記載の発明による原子炉の補修
方法は、請求項1乃至請求項3のいずれか一項に記載の
原子炉の補修装置を用いた原子炉の補修方法であって、
原子炉ウェル及び機器貯蔵ピット内に水を注入した後、
原子炉容器内の炉内構造物を機器貯蔵ピットに移送し、
請求項1乃至請求項3のいずれか一項に記載の原子炉の
補修装置を所定の位置に配置し、少なくとも前記原子炉
容器の真上にある水を排出して気相空間とした後に原子
炉の補修作業を行うことを特徴とする。
According to a tenth aspect of the present invention, there is provided a method for repairing a nuclear reactor using the repair apparatus for a nuclear reactor according to any one of the first to third aspects.
After injecting water into the reactor well and equipment storage pit,
Transfer the internal structure of the reactor vessel to the equipment storage pit,
The reactor repair device according to any one of claims 1 to 3, wherein the repair device is disposed at a predetermined position, and at least water immediately above the reactor vessel is discharged to form a gas phase space. It is characterized by performing furnace repair work.

【0017】請求項11記載の発明による原子炉の補修
方法は、請求項4記載の原子炉の補修装置を用いた原子
炉の補修方法であって、原子炉ウェル及び機器貯蔵ピッ
ト内に水を注入した後、原子炉容器内の炉内構造物を機
器貯蔵ピットに移送し、前記弁手段を開放した状態で前
記遮蔽カバー部材によって前記炉内構造物を上方から覆
い、前記弁手段を開放状態から閉鎖状態に切り換え、少
なくとも前記原子炉ウェル及び前記機器貯蔵ピットの水
を排出して気相空間とした後に原子炉の補修作業を行う
ことを特徴とする。
A repair method for a nuclear reactor according to the invention according to claim 11 is a method for repairing a nuclear reactor using the repair apparatus for a nuclear reactor according to claim 4, wherein water is supplied to the reactor well and the equipment storage pit. After the injection, the reactor internal structure in the reactor vessel is transferred to the equipment storage pit, and the reactor internal structure is covered by the shielding cover member from above with the valve means opened, and the valve means is opened. From the closed state to the closed state, and at least water in the reactor well and the equipment storage pit is discharged to form a gaseous space, and then repair work of the reactor is performed.

【0018】請求項12記載の発明による原子炉の補修
方法は、請求項5又は請求項6に記載の原子炉の補修装
置を用いた原子炉の補修方法であって、原子炉ウェル及
び機器貯蔵ピット内に水を注入した後、原子炉容器内の
炉内構造物を機器貯蔵ピットに移送し、前記弁手段を開
放した状態で前記遮蔽カバー部材によって前記炉内構造
物を上方から覆い、前記ポンプ手段によって前記遮蔽カ
バー部材の内部を減圧し、前記弁手段を開放状態から閉
鎖状態に切り換え、少なくとも前記原子炉ウェル及び前
記機器貯蔵ピットの水を排出して気相空間とした後に原
子炉の補修作業を行うことを特徴とする。
According to a twelfth aspect of the present invention, there is provided a method for repairing a nuclear reactor using the reactor repair apparatus according to the fifth or sixth aspect, wherein the method comprises the steps of: After injecting water into the pit, the reactor internal structure in the reactor vessel is transferred to an equipment storage pit, and the reactor internal structure is covered from above by the shielding cover member with the valve means open, The inside of the shielding cover member is depressurized by pump means, the valve means is switched from an open state to a closed state, and at least water of the reactor well and the equipment storage pit is discharged to form a gas phase space, and then the reactor is closed. It is characterized by performing repair work.

【0019】請求項13記載の発明による原子炉の補修
方法は、請求項7又は請求項8に記載の原子炉の補修装
置を用いた原子炉の補修方法であって、原子炉ウェル及
び機器貯蔵ピット内に水を注入した後、前記弁手段を開
放した状態で前記遮蔽容器を前記機器貯蔵ピットに配置
し、前記弁手段を開放状態から閉鎖状態に切り換え、原
子炉容器内の炉内構造物を前記遮蔽容器の内部に移送
し、少なくとも前記原子炉ウェル及び前記機器貯蔵ピッ
トの水を排出して気相空間とした後に原子炉の補修作業
を行うことを特徴とする。
According to a thirteenth aspect of the present invention, there is provided a method for repairing a nuclear reactor using the reactor repair apparatus according to the seventh or eighth aspect, wherein the reactor well and the equipment storage are provided. After injecting water into the pit, the shielding container is disposed in the equipment storage pit with the valve means opened, and the valve means is switched from the open state to the closed state, and the reactor internal structure in the reactor vessel Is transported to the inside of the shielded vessel, and at least water in the reactor well and the equipment storage pit is discharged to form a gaseous space, and then a repair operation of the reactor is performed.

【0020】請求項14記載の発明による原子炉の補修
方法は、請求項9記載の原子炉の補修装置を用いた原子
炉の補修方法であって、水がない状態の前記機器貯蔵ピ
ットに前記遮蔽容器を配置し、原子炉容器内の炉内構造
物を前記遮蔽容器の内部に移送し、前記ポンプ手段によ
って開放状態の前記弁手段を介して前記遮蔽容器の内部
に水を注入し、前記弁手段を開放状態から閉鎖状態に切
り換え、少なくとも前記原子炉ウェル及び前記機器貯蔵
ピットを気相空間として原子炉の補修作業を行うことを
特徴とする。
According to a fourteenth aspect of the present invention, there is provided a method for repairing a nuclear reactor using the repair apparatus for a nuclear reactor according to the ninth aspect, wherein the repairing pit is provided in the equipment storage pit without water. Arranging a shielding vessel, transferring the reactor internals in the reactor vessel into the shielding vessel, injecting water into the shielding vessel through the valve means in an open state by the pump means, The valve means is switched from an open state to a closed state, and repair work of the reactor is performed using at least the reactor well and the equipment storage pit as a gas phase space.

【0021】[0021]

【発明の実施の形態】第1実施形態 以下、本発明による原子炉の補修装置及び方法の第1実
施形態について図1乃至図4を参照して説明する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS First Embodiment Hereinafter, a first embodiment of a reactor repair apparatus and method according to the present invention will be described with reference to FIGS.

【0022】図1は、本実施形態による原子炉の補修装
置を所定の位置に設置した状態を示した平面図であり、
図2は、図1の2−2線に沿った縦断面図である。図1
及び図2において符号100は原子炉圧力容器を示し、
この原子炉圧力容器100は上蓋(図示せず)が取り外
された状態にある。原子炉圧力容器100の上方には原
子炉ウェル101が形成されており、この原子炉ウェル
101に隣接して機器貯蔵ピット(ドライヤ・セパレー
タピット)102が形成されている。また、原子炉ウェ
ル101の傍らには燃料プール103が形成されてお
り、この燃料プール103は連絡通路部104を介して
原子炉ウェル101と連通している。この連絡通路部1
04は、隔離手段(図示せず)によって適宜水密に閉鎖
することが可能であり、これによって燃料プール103
を原子炉ウェル101から水密に隔離することができ
る。
FIG. 1 is a plan view showing a state in which the reactor repair apparatus according to the present embodiment is installed at a predetermined position.
FIG. 2 is a longitudinal sectional view taken along line 2-2 of FIG. FIG.
And in FIG. 2, reference numeral 100 indicates a reactor pressure vessel,
The reactor pressure vessel 100 is in a state where an upper lid (not shown) has been removed. A reactor well 101 is formed above the reactor pressure vessel 100, and an equipment storage pit (dryer / separator pit) 102 is formed adjacent to the reactor well 101. A fuel pool 103 is formed beside the reactor well 101, and the fuel pool 103 communicates with the reactor well 101 via a communication passage 104. This communication passage 1
The fuel pool 103 can be closed in a watertight manner by an isolation means (not shown).
From the reactor well 101 in a watertight manner.

【0023】そして、本実施形態による原子炉の補修装
置は、原子炉ウェル101と機器貯蔵ピット102との
境界に立設された方形状の隔離壁1と、この隔離壁1を
支持する隔離壁支持手段2とを備えている。方形状の隔
離壁1の両側端縁及び下端縁には、図3に示したように
水密シール3が付設されており、この水密シール部材3
は機器貯蔵ピット102の床面105及び側面に圧接さ
れて水密シールが形成されている。
The repair apparatus for a nuclear reactor according to the present embodiment has a rectangular isolation wall 1 erected at the boundary between the reactor well 101 and the equipment storage pit 102, and an isolation wall supporting the isolation wall 1. And support means 2. As shown in FIG. 3, watertight seals 3 are attached to both side edges and a lower end edge of the rectangular isolation wall 1.
Is pressed against the floor surface 105 and the side surface of the equipment storage pit 102 to form a watertight seal.

【0024】また、隔離壁支持手段2は、図2に示した
ように原子炉ウェル101の内壁面106に沿って立設
された複数の垂直支持部材4を備えており、これらの垂
直支持部材4によって複数の水平支持部材5が水平方向
に支持されている。これらの水平支持部材5は上下二段
に設けられており、各段は図1に示したように全体とし
て六角形の平面形状をなしている。ここで、各水平支持
部材5は原子炉圧力容器100の真上に位置しないよう
に配設されており、複数の水平支持部材5によって形成
される六角形の内側を原子炉圧力容器100が通り抜け
ることができるように構成されている。また、隔離壁1
と水平支持部材5との間は水平連結部材6によって連結
されており、機器貯蔵ピット102内の水によって隔離
壁1に加えられる水圧は水平連結部材6を介して水平支
持部材5に伝達されるように構成されている。
The separating wall supporting means 2 includes a plurality of vertical supporting members 4 erected along the inner wall surface 106 of the reactor well 101 as shown in FIG. 4 support a plurality of horizontal support members 5 in the horizontal direction. These horizontal support members 5 are provided in upper and lower stages, and each stage has a hexagonal planar shape as a whole as shown in FIG. Here, each horizontal support member 5 is disposed so as not to be located directly above the reactor pressure vessel 100, and the reactor pressure vessel 100 passes through a hexagon formed by the plurality of horizontal support members 5. It is configured to be able to. Also, isolation wall 1
Is connected to the horizontal support member 5 by a horizontal connection member 6, and the water pressure applied to the isolation wall 1 by the water in the equipment storage pit 102 is transmitted to the horizontal support member 5 via the horizontal connection member 6. It is configured as follows.

【0025】図4(a)、(b)は、図2のB部を拡大
した平面図及び側面図であり、垂直支持部材4と水平支
持部材5との連結構造を示している。図4(a)、
(b)に示したように、垂直支持部材4には取付部7が
突設されており、この取付部7には水平支持部材5の端
部を載置するための受け部8が二カ所に形成されてい
る。また、取付部7には金具取付孔8が形成されてお
り、一方、水平支持部材5にも金具取付孔9が形成され
ている。そして、これらの金具取付孔8、9には、垂直
支持部材4の取付部7と水平支持部材の端部とを連結す
るようにして逆U字状の取付金具10が挿入されてい
る。
FIGS. 4 (a) and 4 (b) are an enlarged plan view and a side view of a portion B in FIG. 2, and show a connection structure between the vertical support member 4 and the horizontal support member 5. FIG. FIG. 4 (a),
As shown in (b), the vertical support member 4 has a mounting portion 7 projecting therefrom. The mounting portion 7 has two receiving portions 8 on which the ends of the horizontal support member 5 are placed. Is formed. The mounting portion 7 is formed with a metal fitting hole 8, while the horizontal support member 5 is also formed with a metal fitting hole 9. An inverted U-shaped mounting bracket 10 is inserted into these mounting holes 8 and 9 so as to connect the mounting portion 7 of the vertical support member 4 and the end of the horizontal support member.

【0026】次に、本実施形態による原子炉の補修装置
を用いて原子炉の補修作業を行う場合の手順について説
明する。まず、原子炉圧力容器100の上蓋(図示せ
ず)を開放し、原子炉ウェル101及び機器貯蔵ピット
102に水を注入する。しかる後、原子炉圧力容器10
0の内部にある気水分離器(図示せず)等の炉内構造物
を機器貯蔵ピット102に移送する。そして、原子炉ウ
ェル101と機器貯蔵ピット102との境界部に隔離壁
1を立設し、また、原子炉ウェル101の内壁面106
に沿って複数の垂直支持部材4を配設する。ここで、垂
直支持部材4は、図4(a)に示したように原子炉ウェ
ル101の内壁面106に当接されている。次に、垂直
支持部材4の取付部7に形成された受け部8に下段の水
平支持部材5の各端部を載置し、取付部7の金具取付孔
8と水平支持部材5の金具取付孔9に逆U字状の取付金
具10を上方から挿入する。このようにして垂直支持部
材4と下段の水平支持部材5とを連結したら、同様の手
順によって上段の水平支持部材5と垂直支持部材4とを
連結する。このようにして垂直支持部材4と上下段の水
平支持部材5とを連結したら、隔離壁1と水平支持部材
5との間を水平連結部材6によって連結する。
Next, a procedure for repairing a reactor using the reactor repair apparatus according to the present embodiment will be described. First, the upper lid (not shown) of the reactor pressure vessel 100 is opened, and water is injected into the reactor well 101 and the equipment storage pit 102. Thereafter, the reactor pressure vessel 10
The inside of the furnace, such as a steam separator (not shown), is transferred to the equipment storage pit 102. Then, the isolation wall 1 is erected at the boundary between the reactor well 101 and the equipment storage pit 102, and the inner wall 106 of the reactor well 101 is
A plurality of vertical support members 4 are arranged along. Here, the vertical support member 4 is in contact with the inner wall surface 106 of the reactor well 101 as shown in FIG. Next, each end of the lower horizontal support member 5 is placed on the receiving portion 8 formed on the mounting portion 7 of the vertical support member 4, and the metal mounting hole 8 of the mounting portion 7 and the metal mounting of the horizontal support member 5 are mounted. An inverted U-shaped mounting bracket 10 is inserted into the hole 9 from above. After the vertical support member 4 and the lower horizontal support member 5 are connected in this manner, the upper horizontal support member 5 and the vertical support member 4 are connected in the same procedure. After the vertical support member 4 and the upper and lower horizontal support members 5 are connected in this manner, the isolation wall 1 and the horizontal support member 5 are connected by the horizontal connection member 6.

【0027】上記の手順によって原子炉の補修装置の設
置作業が完了したら、原子炉ウェル101及び原子炉圧
力容器100の内部の水を排出する。なお、原子炉ウェ
ル101のみを排水し、原子炉圧力容器100内には水
がある状態にしておくこともできる。ここで、原子炉ウ
ェル101と機器貯蔵ピット102との間は水密シール
部材3を有する隔離壁1によって水密に隔離されている
ので、原子炉ウェル101内の水を排出しても、機器貯
蔵ピット102内の水は原子炉ウェル101側に流出す
ることなくそのまま維持される。原子炉ウェル101内
が気相空間となると、機器貯蔵ピット102内の水によ
る水圧が隔離壁1に加えられ、この水圧は水平連結部材
6を介して水平支持部材5に伝達される。さらに、水平
支持部材5に伝達された水圧は垂直支持部材4に伝達さ
れるが、垂直支持部材4は原子炉ウェル101の内壁面
106に当接されているので、結局、機器貯蔵ピット1
02内の水圧による力は原子炉ウェル101の内壁面1
06によって受け止められることになる。したがって、
機器貯蔵ピット102からの水圧によって隔離壁1が倒
れるようなことがない。
After the installation of the repair equipment for the nuclear reactor is completed by the above procedure, the water inside the reactor well 101 and the reactor pressure vessel 100 is drained. It is also possible to drain only the reactor well 101 and keep water in the reactor pressure vessel 100. Here, since the reactor well 101 and the equipment storage pit 102 are water-tightly isolated by the isolation wall 1 having the watertight seal member 3, even if the water in the reactor well 101 is discharged, the equipment storage pit is not affected. The water in 102 is maintained without flowing out to the reactor well 101 side. When the inside of the reactor well 101 becomes a gas phase space, water pressure due to water in the equipment storage pit 102 is applied to the isolation wall 1, and this water pressure is transmitted to the horizontal support member 5 via the horizontal connecting member 6. Further, the water pressure transmitted to the horizontal support member 5 is transmitted to the vertical support member 4, but since the vertical support member 4 is in contact with the inner wall surface 106 of the reactor well 101, the equipment storage pit 1
The force due to the water pressure inside 02 is the inner wall 1 of the reactor well 101.
06 will be accepted. Therefore,
The isolation wall 1 does not fall due to the water pressure from the equipment storage pit 102.

【0028】そして、上記の手順によって原子炉ウェル
101及び原子炉圧力容器100の内部を気相空間とし
た後、原子炉圧力容器100の内部での原子炉の補修作
業や、原子炉圧力容器100自体の交換作業等の原子炉
の補修作業を実施する。ここで、各水平支持部材5は原
子炉圧力容器100の真上に位置しないように六角形に
配設されているので、原子炉圧力容器100の交換作業
においては、水平支持部材5によって形成された六角形
の内側を介して原子炉圧力容器100を搬出し又は搬入
することができる。
After the interior of the reactor well 101 and the reactor pressure vessel 100 is made into a gas phase space by the above-described procedure, the repair work of the reactor inside the reactor pressure vessel 100 and the reactor pressure vessel 100 are performed. Carry out repair work for the reactor, such as replacement of the reactor itself. Here, since each horizontal support member 5 is arranged in a hexagon so as not to be located directly above the reactor pressure vessel 100, it is formed by the horizontal support member 5 in the replacement operation of the reactor pressure vessel 100. The reactor pressure vessel 100 can be unloaded or loaded via the inside of the hexagon.

【0029】所定の補修作業を全て終了したら原子炉の
補修装置の撤去作業を開始するが、この撤去作業は上述
した設置作業と逆の手順によって行われる。すなわち、
原子炉圧力容器100及び原子炉ウェル101の内部に
水を注入した後、隔離壁1と水平支持部材5との間を連
結している水平連結部材6を取り外す。次に、取付金具
10を抜いて垂直支持部材4から水平支持部材5を取り
外し、垂直支持部材4を原子炉ウェル101から引き上
げる。最後に、原子炉ウェル101と機器貯蔵ピット1
02との間に立設された隔離壁1を取り外して撤去作業
を終了する。
When all the predetermined repair work is completed, the removal work of the repair equipment of the nuclear reactor is started. This removal work is performed in the reverse order of the above-described installation work. That is,
After water is injected into the reactor pressure vessel 100 and the reactor well 101, the horizontal connecting member 6 connecting the isolation wall 1 and the horizontal support member 5 is removed. Next, the mounting bracket 10 is removed, the horizontal support member 5 is removed from the vertical support member 4, and the vertical support member 4 is pulled up from the reactor well 101. Finally, reactor well 101 and equipment storage pit 1
02, the separating wall 1 standing upright is removed, and the removing operation is completed.

【0030】以上述べたように本実施形態による原子炉
の補修装置及び方法によれば、機器貯蔵ピット102の
内部に水を保持しつつ原子炉ウェル101及び原子炉圧
力容器100の内部を気相空間とすることができるの
で、放射能の高い炉内構造物を機器貯蔵ピット102に
おいて水中で保管して放射線を遮蔽しながら、原子炉圧
力容器100の内部での補修作業や原子炉圧力容器10
0自体の交換作業等の原子炉の補修作業を気相空間にお
いて行うことが可能であり、したがって、これらの作業
の効率が大幅に向上する。
As described above, according to the apparatus and method for repairing a nuclear reactor according to the present embodiment, the interior of the reactor well 101 and the reactor pressure vessel 100 are vapor Since the internal structure of the reactor can be used as a space, the internal structure of the reactor having a high radioactivity can be stored underwater in the equipment storage pit 102 to shield radiation, while repair work inside the reactor pressure vessel 100 and the reactor pressure vessel 10 can be performed.
Repair work of the nuclear reactor such as replacement work of the reactor 0 itself can be performed in the gas phase space, so that the efficiency of these works is greatly improved.

【0031】第2実施形態 次に、本発明による原子炉の補修装置及び方法の第2実
施形態について図5乃至図7を参照して説明する。な
お、上記第1実施形態と同一部材には同一符号を付して
詳細な説明は省略する。
Second Embodiment Next, a second embodiment of the apparatus and method for repairing a nuclear reactor according to the present invention will be described with reference to FIGS. The same members as those in the first embodiment are denoted by the same reference numerals, and detailed description is omitted.

【0032】図5は、本実施形態による原子炉の補修装
置を所定の位置に設置した状態を示した平面図であり、
図6は、図5の6−6線に沿った縦断面図である。図5
及び図6に示したように、本実施形態による原子炉の補
修装置は筒状隔離体20を備えており、この筒状隔離体
20は、原子炉圧力容器100のフランジ部107の外
径よりも大きな内径を有している。この筒状隔離体20
の下端部には、図7に示したように水密シール部材21
が周設されており、この水密シール部材21は原子炉ウ
ェル101の床面108に当接されて水密シールを形成
している。
FIG. 5 is a plan view showing a state in which the reactor repair apparatus according to the present embodiment is installed at a predetermined position.
FIG. 6 is a longitudinal sectional view taken along line 6-6 in FIG. FIG.
As shown in FIG. 6 and FIG. 6, the repair apparatus for a nuclear reactor according to the present embodiment includes a cylindrical separator 20, which is larger than the outer diameter of the flange 107 of the reactor pressure vessel 100. Also have a large inner diameter. This cylindrical separator 20
As shown in FIG.
The watertight seal member 21 is in contact with the floor surface 108 of the reactor well 101 to form a watertight seal.

【0033】次に、本実施形態による原子炉の補修装置
を用いて原子炉の補修作業を行う場合の手順について説
明する。まず、原子炉圧力容器100の上蓋(図示せ
ず)を開放し、原子炉ウェル101及び機器貯蔵ピット
102に水を注入する。しかる後、原子炉圧力容器10
0の内部にある気水分離器(図示せず)等の炉内構造物
を機器貯蔵ピット102に移送する。そして、筒状隔離
体20を原子炉ウェル101内に設置し、この筒状隔離
体20の下端部にある水密シール部材21を原子炉ウェ
ル101の床面108に当接して水密シールを形成す
る。
Next, a procedure for repairing a nuclear reactor using the reactor repair apparatus according to the present embodiment will be described. First, the upper lid (not shown) of the reactor pressure vessel 100 is opened, and water is injected into the reactor well 101 and the equipment storage pit 102. Thereafter, the reactor pressure vessel 10
The inside of the furnace, such as a steam separator (not shown), is transferred to the equipment storage pit 102. Then, the tubular separator 20 is installed in the reactor well 101, and the watertight seal member 21 at the lower end of the tubular separator 20 contacts the floor surface 108 of the reactor well 101 to form a watertight seal. .

【0034】このようにして原子炉の補修装置を原子炉
ウェル101内に設置したら、原子炉圧力容器100及
び筒状隔離体20の内部の水を排出する。ここで、筒状
隔離体20の内部と機器貯蔵ピット102との間は、水
密シール部材21を有する隔離壁1によって水密に隔離
されているので、筒状隔離体20内の水を排出しても、
機器貯蔵ピット102内の水は排出されることなくその
まま維持される。
When the repair device for the reactor is installed in the reactor well 101 in this manner, the water inside the reactor pressure vessel 100 and the cylindrical separator 20 is discharged. Here, since the inside of the tubular separator 20 and the device storage pit 102 are watertightly separated by the partition wall 1 having the watertight seal member 21, the water in the tubular separator 20 is discharged. Also,
The water in the equipment storage pit 102 is maintained without being discharged.

【0035】そして、上記の手順によって筒状隔離体2
0の内部(すなわち原子炉圧力容器100の真上)及び
原子炉圧力容器100の内部を気相空間とし、一方、機
器貯蔵ピット102の内部及び筒状隔離体20の周囲の
水はそのままにして、原子炉圧力容器100の内部での
原子炉の補修作業や、原子炉圧力容器100自体の交換
作業等の原子炉の補修作業を実施する。ここで、筒状隔
離体20は原子炉圧力容器100のフランジ部107の
外径よりも大きな内径を有しているので、原子炉圧力容
器100の交換作業においては、筒状隔離体20の内側
を介して原子炉圧力容器100を搬出し又は搬入するこ
とができる。
Then, according to the above procedure, the cylindrical separator 2
0 (that is, just above the reactor pressure vessel 100) and the interior of the reactor pressure vessel 100 are gas-phase spaces, while the water inside the equipment storage pit 102 and around the cylindrical separator 20 is left as it is. In addition, repair work of the reactor inside the reactor pressure vessel 100 and replacement work of the reactor pressure vessel 100 itself are performed. Here, since the cylindrical separator 20 has an inner diameter larger than the outer diameter of the flange portion 107 of the reactor pressure vessel 100, the inside of the cylindrical separator 20 is The reactor pressure vessel 100 can be unloaded or loaded via the.

【0036】所定の補修作業を全て終了したら原子炉の
補修装置の撤去作業を開始するが、この撤去作業は上述
した設置作業と逆の手順によって行われる。すなわち、
原子炉圧力容器100及び筒状隔離体20の内部に水を
注入した後、筒状隔離体20を原子炉ウェル101から
引き上げて撤去する。
When all the predetermined repair work is completed, the removal work of the repair equipment of the nuclear reactor is started. This removal work is performed in the reverse order of the installation work described above. That is,
After water is injected into the reactor pressure vessel 100 and the cylindrical separator 20, the cylindrical separator 20 is pulled up from the reactor well 101 and removed.

【0037】以上述べたように本実施形態による原子炉
の補修装置及び方法によれば、機器貯蔵ピット102の
内部に水を保持しつつ、原子炉圧力容器100の内部及
び上方を気相空間にすることができるので、放射能の高
い炉内構造物を機器貯蔵ピット102において水中で保
管して放射線を遮蔽しながら、原子炉圧力容器100の
内部での補修作業や原子炉圧力容器100自体の交換作
業等の原子炉の補修作業を気相空間において行うことが
可能であり、したがって、これらの作業の効率が大幅に
向上する。
As described above, according to the apparatus and method for repairing a nuclear reactor according to the present embodiment, the inside and upper part of the reactor pressure vessel 100 are kept in the gas space while the water is held inside the equipment storage pit 102. Therefore, while the reactor internal structure having high radioactivity is stored in water in the equipment storage pit 102 to shield the radiation, repair work inside the reactor pressure vessel 100 and the reactor pressure vessel 100 itself can be performed. Repair work of the reactor such as replacement work can be performed in the gas phase space, and therefore, the efficiency of these works is greatly improved.

【0038】第3実施形態 次に、本発明による原子炉の補修装置及び方法の第3実
施形態について図8を参照して説明する。なお、上記第
1実施形態と同一部材には同一符号を付して詳細な説明
は省略する。
Third Embodiment Next, a third embodiment of the reactor repair apparatus and method according to the present invention will be described with reference to FIG. The same members as those in the first embodiment are denoted by the same reference numerals, and detailed description is omitted.

【0039】図8は、本実施形態による原子炉の補修装
置を所定の位置に設置した状態を示した縦断面図であ
る。図8に示したように本実施形態による原子炉の補修
装置は、機器貯蔵ピット102に移送された気水分離器
109及び蒸気乾燥器110の全体を上方から覆うよう
にして設置された遮蔽カバー部材30を備えている。こ
の遮蔽カバー部材30は、機器貯蔵ピット102の床面
105に設置された状態において、その上端が操作床
(オペレーションフロア)111のレベルよりも高い位
置にある。
FIG. 8 is a longitudinal sectional view showing a state where the repair apparatus for a nuclear reactor according to the present embodiment is installed at a predetermined position. As shown in FIG. 8, the repair apparatus for a nuclear reactor according to the present embodiment includes a shielding cover installed so as to cover the entire steam-water separator 109 and the steam dryer 110 transferred to the equipment storage pit 102 from above. A member 30 is provided. When the shielding cover member 30 is installed on the floor surface 105 of the equipment storage pit 102, its upper end is at a position higher than the level of the operation floor 111.

【0040】遮蔽カバー部材30の下端部には、遮蔽カ
バー部材30の内部と外部との間に流体流路を形成する
切欠部(開口部)31が設けられており、この切欠部3
1の高さは、機器貯蔵ピット102と原子炉ウェル10
1との境界部にある段差112の高さよりも低く設定さ
れている。また、遮蔽カバー部材30の上部には、この
遮蔽カバー部材30の内部と外部との間に必要に応じて
流体流路を形成するためのバルブ32が設けられてお
り、このバルブ32には、遮蔽カバー部材30の内部に
空気等の流体を注入し又は排出するためのポンプ33が
配管34を介して接続されている。
At the lower end of the shielding cover member 30, a notch (opening) 31 for forming a fluid flow path between the inside and the outside of the shielding cover member 30 is provided.
The height of 1 is between the equipment storage pit 102 and the reactor well 10.
The height is set to be lower than the height of the step 112 at the boundary portion with the first. In addition, a valve 32 for forming a fluid flow path between the inside and the outside of the shielding cover member 30 as necessary is provided above the shielding cover member 30. A pump 33 for injecting or discharging a fluid such as air into the shielding cover member 30 is connected via a pipe 34.

【0041】次に、本実施形態による原子炉の補修装置
を用いて原子炉の補修作業を行う場合の手順について説
明する。まず、原子炉圧力容器100の上蓋(図示せ
ず)を開放し、原子炉ウェル101及び機器貯蔵ピット
102に水を注入する。しかる後、原子炉圧力容器10
0の内部にある気水分離器109及び蒸気乾燥器110
を機器貯蔵ピット102に移送する。そして、気水分離
器109及び蒸気乾燥器110の上方から遮蔽カバー部
材30を被せ、機器貯蔵ピット102の床面105に遮
蔽カバー部材30を載置する。ここで、気水分離器10
9及び蒸気乾燥器110に遮蔽カバー部材30を被せる
際には、バルブ32を開放状態にすると共にポンプ33
によって遮蔽カバー部材30内部の空気を排気するよう
にする。このようにすれば、機器貯蔵ピット102内の
水の中に遮蔽カバー部材30を速やかに設置することが
できると共に、遮蔽カバー部材30内の水位を操作床1
11のレベルよりも高い位置にすることができる。
Next, a procedure for repairing a nuclear reactor using the reactor repair apparatus according to the present embodiment will be described. First, the upper lid (not shown) of the reactor pressure vessel 100 is opened, and water is injected into the reactor well 101 and the equipment storage pit 102. Thereafter, the reactor pressure vessel 10
0 steam-water separator 109 and steam dryer 110
Is transferred to the equipment storage pit 102. Then, the shield cover member 30 is put on the steam-water separator 109 and the steam dryer 110 from above, and the shield cover member 30 is placed on the floor surface 105 of the equipment storage pit 102. Here, the steam separator 10
When the shielding cover member 30 is put on the steam dryer 9 and the steam dryer 110, the valve 32 is opened and the pump 33
As a result, air inside the shielding cover member 30 is exhausted. In this manner, the shield cover member 30 can be quickly installed in the water in the equipment storage pit 102, and the water level in the shield cover member 30 can be controlled by the operation floor 1.
The position can be higher than the eleventh level.

【0042】このようにして遮蔽カバー部材30の内部
に気水分離器109及び蒸気乾燥器110の全体を収納
して周囲から隔離し、遮蔽カバー部材30内の水位が所
定の位置に達したら、バルブ32を開放状態から閉鎖状
態に切り換える。
As described above, the entire steam-water separator 109 and the steam dryer 110 are housed inside the shielding cover member 30 to be isolated from the surroundings, and when the water level in the shielding cover member 30 reaches a predetermined position, The valve 32 is switched from the open state to the closed state.

【0043】次に、機器貯蔵ピット102、原子炉ウェ
ル101及び原子炉圧力容器100の内部の水を排出
し、このとき、機器貯蔵ピット102内の水位が切欠部
31の高さよりも下がらないようにする。ここで、バル
ブ32は閉じられているので遮蔽カバー部材30の内部
は気密であり、しかも、遮蔽カバー部材30の内部の圧
力は外部の圧力よりも低くなっているので、この内外の
圧力差によって遮蔽カバー部材30内の水位は高い位置
に維持される。
Next, the water inside the equipment storage pit 102, the reactor well 101, and the reactor pressure vessel 100 is drained. At this time, the water level in the equipment storage pit 102 does not drop below the height of the notch 31. To Here, since the valve 32 is closed, the inside of the shielding cover member 30 is airtight, and the pressure inside the shielding cover member 30 is lower than the external pressure. The water level in the shielding cover member 30 is maintained at a high position.

【0044】そして、上記の手順によって原子炉ウェル
101及び原子炉圧力容器100の内部を気相空間と
し、一方、遮蔽カバー部材30の内部には水がある状態
として、原子炉圧力容器100の内部での原子炉の補修
作業や、原子炉圧力容器100自体の交換作業等の原子
炉の補修作業を実施する。
According to the above procedure, the inside of the reactor well 101 and the reactor pressure vessel 100 is made into a gas phase space. And repair work of the reactor such as replacement work of the reactor pressure vessel 100 itself.

【0045】所定の補修作業を全て終了したら、原子炉
圧力容器100、原子炉ウェル101及び機器貯蔵ピッ
ト102の内部に水を注入する。そして、遮蔽カバー部
材30の上部に設けられたバルブ32を開放し、このバ
ルブ32を介して遮蔽カバー部材30の内部に空気を導
入する。このようにして遮蔽カバー部材30の内部と外
部との間の圧力差をなくした後、遮蔽カバー部材30を
機器貯蔵ピット102から引き上げる。
When all the predetermined repair work is completed, water is injected into the reactor pressure vessel 100, the reactor well 101, and the equipment storage pit 102. Then, the valve 32 provided above the shielding cover member 30 is opened, and air is introduced into the shielding cover member 30 via the valve 32. After eliminating the pressure difference between the inside and the outside of the shielding cover member 30 in this way, the shielding cover member 30 is pulled up from the device storage pit 102.

【0046】以上述べたように本実施形態による原子炉
の補修装置及び方法によれば、遮蔽カバー部材30の内
部を水で満たした状態にしながら、原子炉圧力容器10
0の内部及び原子炉ウェル101を気相空間とすること
ができるので、放射能の高い炉内構造物を遮蔽カバー部
材30内において水中で保管して放射線を遮蔽しなが
ら、原子炉圧力容器100の内部での補修作業や原子炉
圧力容器100自体の交換作業等の原子炉の補修作業を
気相空間において行うことが可能であり、したがって、
これらの作業の効率が大幅に向上する。また、遮蔽カバ
ー部材30自身によって放射線を遮蔽することができる
ので、遮蔽カバー部材30内の水による遮蔽効果と相ま
って効果的に放射線を遮蔽することができる。
As described above, according to the reactor repairing apparatus and method according to the present embodiment, the reactor pressure vessel 10 is maintained while the inside of the shielding cover member 30 is filled with water.
0 and the reactor well 101 can be made into a gas phase space, so that the reactor internal structure having high radioactivity is stored in water in the shielding cover member 30 to shield radiation while the reactor pressure vessel 100 It is possible to perform repair work on the reactor, such as repair work inside the reactor and replacement work of the reactor pressure vessel 100 itself, in the gas phase space.
The efficiency of these operations is greatly improved. Further, since the radiation can be shielded by the shielding cover member 30 itself, the radiation can be effectively shielded in combination with the shielding effect of the water in the shielding cover member 30.

【0047】また、遮蔽カバー部材30の上端は操作床
111のレベルよりも高い位置にあり、しかも、ポンプ
33によって遮蔽カバー部材30内の水位を操作床11
1のレベルよりも高い位置にすることができるので、図
8に示したように気水分離器109と蒸気乾燥器110
とを段積みして保管することが可能である。このため、
保管のために使用する機器貯蔵ピット102の床面10
5の面積を小さくすることができ、機器貯蔵ピット10
2を有効に利用することができる。
The upper end of the shield cover member 30 is located at a position higher than the level of the operation floor 111, and the water level in the shield cover member 30 is controlled by the pump 33.
1, the steam-water separator 109 and the steam dryer 110 as shown in FIG.
Can be stored in a stack. For this reason,
Floor 10 of equipment storage pit 102 used for storage
5 can be reduced, and the equipment storage pit 10
2 can be used effectively.

【0048】変形例 本実施形態の一変形例として、遮蔽カバー部材30を機
器貯蔵ピット102の床面105以外の場所に設置する
ことができる。つまり、機器貯蔵ピット102の床面1
05以外の場所であっても、遮蔽カバー部材30下部の
切欠部31が露出しない水位を維持できる場所であれば
設置することができる。
Modification As a modification of the present embodiment, the shielding cover member 30 can be installed at a place other than the floor surface 105 of the equipment storage pit 102. That is, the floor 1 of the equipment storage pit 102
Even if it is a place other than 05, it can be installed as long as it can maintain a water level where the notch 31 below the shielding cover member 30 is not exposed.

【0049】このように遮蔽カバー部材30の設置場所
は機器貯蔵ピット102の床面105に限定されないの
で、炉内構造物の保管場所を増やすことができる。
As described above, the installation place of the shielding cover member 30 is not limited to the floor surface 105 of the equipment storage pit 102, so that the storage place of the furnace internal structure can be increased.

【0050】第4実施形態 次に、本発明による原子炉の補修装置及び方法の第4実
施形態について図9を参照して説明する。なお、上記第
1実施形態と同一部材には同一符号を付して詳細な説明
は省略する。
Fourth Embodiment Next, a fourth embodiment of the apparatus and method for repairing a nuclear reactor according to the present invention will be described with reference to FIG. The same members as those in the first embodiment are denoted by the same reference numerals, and detailed description is omitted.

【0051】図9は、本実施形態による原子炉の補修装
置を所定の位置に設置した状態を示した縦断面図であ
る。図9に示したように本実施形態による原子炉の補修
装置は、機器貯蔵ピット102の床面105に載置され
た遮蔽容器40を備えており、この遮蔽容器40の上面
は開放されている。遮蔽容器40の上端には同径の円筒
部材41が取り外し可能に連接されており、その連接部
分は水密シール部材42によって水密にシールされてい
る。ここで、円筒部材41の上端部は、図9に示したよ
うに操作床111のレベルよりも高い位置にある。
FIG. 9 is a longitudinal sectional view showing a state where the repair device for a nuclear reactor according to the present embodiment is installed at a predetermined position. As shown in FIG. 9, the repair apparatus for a nuclear reactor according to the present embodiment includes a shielding container 40 placed on the floor surface 105 of the equipment storage pit 102, and the upper surface of the shielding container 40 is open. . A cylindrical member 41 of the same diameter is detachably connected to the upper end of the shielding container 40, and the connected portion is water-tightly sealed by a water-tight seal member 42. Here, the upper end of the cylindrical member 41 is at a position higher than the level of the operation floor 111 as shown in FIG.

【0052】また、遮蔽容器40の下部には、遮蔽容器
40の内部と外部との間に必要に応じて流体流路を形成
するためのバルブ43が設けられており、このバルブ4
3は、遮蔽容器40の内部に水を注入し又は排出するた
めのポンプ44に配管45を介して接続されている。
Further, a valve 43 for forming a fluid flow path between the inside and the outside of the shielding container 40 as necessary is provided below the shielding container 40.
3 is connected via a pipe 45 to a pump 44 for injecting or discharging water inside the shielding container 40.

【0053】次に、本実施形態による原子炉の補修装置
を用いて原子炉の補修作業を行う場合の手順について説
明する。まず、原子炉圧力容器100の上蓋(図示せ
ず)を開放し、原子炉ウェル101及び機器貯蔵ピット
102に水を注入する。しかる後、機器貯蔵ピット10
2の床面に遮蔽容器40及び円筒部材41を設置する。
この際、遮蔽容器40の下部のバルブ43を開放状態と
して、ポンプ44を駆動して遮蔽容器40及び円筒部材
41の内部に水を注入する。このように遮蔽容器40及
び円筒部材41に注水しながら設置作業を行うことによ
って、機器貯蔵ピット102の水の中に遮蔽容器40及
び円筒部材41を速やかに設置することができる。
Next, a procedure for repairing a reactor using the reactor repair apparatus according to the present embodiment will be described. First, the upper lid (not shown) of the reactor pressure vessel 100 is opened, and water is injected into the reactor well 101 and the equipment storage pit 102. Then, the equipment storage pit 10
The shielding container 40 and the cylindrical member 41 are installed on the floor surface of No. 2.
At this time, the valve 43 below the shielding container 40 is opened, and the pump 44 is driven to inject water into the shielding container 40 and the cylindrical member 41. By performing the installation work while pouring water into the shielding container 40 and the cylindrical member 41 in this manner, the shielding container 40 and the cylindrical member 41 can be quickly installed in the water of the device storage pit 102.

【0054】遮蔽容器40及び円筒部材41を機器貯蔵
ピット102の床面105に設置したらバルブ43を閉
鎖する。そして、原子炉圧力容器100の内部にある気
水分離器109及び蒸気乾燥器110を遮蔽容器40及
び円筒部材41の内部に移送して水中で保管する。ここ
で、遮蔽容器40及び円筒部材41内に炉内構造物を収
納した際に、炉内構造物の上部が水面よりも上にでてし
まうときには、再びバルブ43を開放してポンプ44か
ら水を注入し、炉内構造物の全体が水没するようにす
る。次に、機器貯蔵ピット102、原子炉ウェル101
及び原子炉圧力容器100の内部の水を排出して気相空
間とする。
When the shielding container 40 and the cylindrical member 41 are set on the floor 105 of the equipment storage pit 102, the valve 43 is closed. Then, the steam-water separator 109 and the steam dryer 110 inside the reactor pressure vessel 100 are transferred to the inside of the shielding vessel 40 and the cylindrical member 41 and stored in water. Here, when the furnace internal structure is stored in the shielding container 40 and the cylindrical member 41 and the upper part of the furnace internal structure comes out above the water surface, the valve 43 is opened again and the water is supplied from the pump 44. So that the entire furnace internals are submerged. Next, the equipment storage pit 102, the reactor well 101
Then, water inside the reactor pressure vessel 100 is discharged to form a gas phase space.

【0055】このようにして気水分離器109及び蒸気
乾燥器110を遮蔽容器40及び円筒部材41において
水中で保管しつつ、原子炉ウェル101及び原子炉圧力
容器100の内部を気相空間として原子炉圧力容器10
0の内部での原子炉の補修作業や、原子炉圧力容器10
0自体の交換作業等の原子炉の補修作業を実施する。そ
して、所定の補修作業が終了したら、遮蔽容器40及び
円筒部材41に保管された気水分離器109及び蒸気乾
燥器110を原子炉圧力容器100内に移送し、遮蔽容
器40及び円筒部材41内の水を排出した後、機器貯蔵
ピット102から遮蔽容器40及び円筒部材41を引き
上げて撤去する。
In this manner, the steam-water separator 109 and the steam dryer 110 are stored in the shielding vessel 40 and the cylindrical member 41 in the water, and the inside of the reactor well 101 and the reactor pressure vessel 100 is used as a gas phase space. Furnace pressure vessel 10
0 repair work inside the reactor pressure vessel 10
Perform repair work on the nuclear reactor, such as replacement work of the 0 itself. When the predetermined repair work is completed, the steam-water separator 109 and the steam dryer 110 stored in the shielding vessel 40 and the cylindrical member 41 are transferred into the reactor pressure vessel 100, and the inside of the shielding vessel 40 and the cylindrical member 41 are transferred. Then, the shielding container 40 and the cylindrical member 41 are pulled up from the equipment storage pit 102 and removed.

【0056】以上述べたように本実施形態による原子炉
の補修装置及び方法によれば、放射能の高い気水分離器
109及び蒸気乾燥器110を遮蔽容器40及び円筒部
材41において水中で保管し、機器貯蔵ピット102、
原子炉ウェル101及び原子炉圧力容器100の内部を
気相空間としながら作業を行うことができるので、原子
炉圧力容器100の内部での補修作業や原子炉圧力容器
100自体の交換作業等の原子炉の補修作業を気相空間
において行うことが可能であり、したがって、これらの
作業の効率が大幅に向上する。また、遮蔽容器40及び
円筒部材41自身によって放射線を遮蔽することができ
るので、水による遮蔽効果と相まって効果的に放射線を
遮蔽することができる。
As described above, according to the apparatus and method for repairing a nuclear reactor according to the present embodiment, the steam-water separator 109 and the steam dryer 110 having high radioactivity are stored underwater in the shielding vessel 40 and the cylindrical member 41. , Equipment storage pit 102,
Since the work can be performed while the inside of the reactor well 101 and the reactor pressure vessel 100 is used as a gas phase space, the repair work inside the reactor pressure vessel 100 and the replacement work of the reactor pressure vessel 100 itself can be performed. Furnace repair operations can be performed in the gas space, thus greatly improving the efficiency of these operations. Further, since the radiation can be shielded by the shielding container 40 and the cylindrical member 41 itself, the radiation can be effectively shielded in combination with the shielding effect by water.

【0057】また、円筒部材41の上端は操作床111
のレベルよりも高い位置にあり、しかも、ポンプ44に
よって遮蔽容器40及び円筒部材41の水位を操作床1
11のレベルよりも高い位置にすることができるので、
図9に示したように気水分離器109と蒸気乾燥器11
0とを段積みして保管することが可能である。このた
め、保管のために使用する機器貯蔵ピット102の床面
105の面積を小さくすることができ、機器貯蔵ピット
102を有効に利用することができる。
The upper end of the cylindrical member 41 is connected to the operation floor 111.
And the pump 44 controls the water level of the shielding container 40 and the cylindrical member 41 by the operation floor 1.
Since it can be higher than the 11th level,
As shown in FIG. 9, steam-water separator 109 and steam dryer 11
0 can be stacked and stored. Therefore, the area of the floor surface 105 of the device storage pit 102 used for storage can be reduced, and the device storage pit 102 can be used effectively.

【0058】さらに、本実施形態による原子炉の補修装
置は、遮蔽容器40の上部に円筒部材41を水密に連接
するようにしたので、炉内構造物を保管するための水の
水位を必要に応じて高くすることができる。
Further, in the repair apparatus for a nuclear reactor according to the present embodiment, the cylindrical member 41 is connected to the upper part of the shielding vessel 40 in a watertight manner, so that the water level for storing the internal structure of the reactor is required. Can be raised accordingly.

【0059】第1変形例 本実施形態の第1変形例として、遮蔽容器40及び円筒
部材41を機器貯蔵ピット102の床面105に設置す
る際に機器貯蔵ピット102を気相空間にしておくこと
もできる。この場合には、遮蔽容器40及び円筒部材4
1を機器貯蔵ピット102の床面105に設置した後、
原子炉圧力容器100の内部にある気水分離器109及
び蒸気乾燥器110を遮蔽容器40及び円筒部材41の
内部に移送する。次に、開放状態のバルブ43を介して
ポンプ44によって遮蔽容器40及び円筒部材41の内
部に水を注入し、気水分離器109及び蒸気乾燥器11
0の全体が冠水するまで水位を上昇させる。気水分離器
109及び蒸気乾燥器110の全体が冠水したら、バル
ブ43を開放状態から閉鎖状態に切り換えて気水分離器
109及び蒸気乾燥器110を水中で保管し、所定の原
子炉の補修作業を実施する。
First Modification As a first modification of the present embodiment, when the shielding container 40 and the cylindrical member 41 are installed on the floor surface 105 of the equipment storage pit 102, the equipment storage pit 102 is in a gas phase space. Can also. In this case, the shielding container 40 and the cylindrical member 4
After installing 1 on the floor 105 of the equipment storage pit 102,
The steam separator 109 and the steam dryer 110 inside the reactor pressure vessel 100 are transferred into the shield vessel 40 and the cylindrical member 41. Next, water is injected into the shielding container 40 and the cylindrical member 41 by the pump 44 through the valve 43 in the open state, and the steam-water separator 109 and the steam dryer 11
Raise the water level until the entire zero is flooded. When the entire steam-water separator 109 and the steam dryer 110 are submerged, the valve 43 is switched from the open state to the closed state, the steam-water separator 109 and the steam dryer 110 are stored in water, and a predetermined repair work of the nuclear reactor is performed. Is carried out.

【0060】第2変形例 本実施形態の第2変形例として、バルブ43に切換弁を
使用し、この切換弁によって、ポンプ44に連通した状
態及び完全に閉鎖した状態の2つの状態に加えて、遮蔽
容器40の内部と外部とが連通した状態を達成できるよ
うにする。
Second Modification As a second modification of the present embodiment, a switching valve is used as the valve 43, and this switching valve is used in addition to the two states of the state of being connected to the pump 44 and the state of being completely closed. Thus, a state where the inside and the outside of the shielding container 40 communicate with each other can be achieved.

【0061】そして、水で満たされた状態にある機器貯
蔵ピット102に遮蔽容器40及び円筒部材41を設置
する際には、バルブ43によって遮蔽容器40の内部と
外部とが連通した状態としておく。このようにすれば、
機器貯蔵ピット102内の水がバルブ43を介して遮蔽
容器40内に流入するので、ポンプ44によって遮蔽容
器40内に強制的に水を注入する必要がない。また、遮
蔽容器40及び円筒部材41を機器貯蔵ピット102に
設置した後に、バルブ43を切り換えてポンプ44から
水を注入することによって、遮蔽容器40及び円筒部材
41内の水位を高くすることができる。
When the shielding container 40 and the cylindrical member 41 are installed in the equipment storage pit 102 filled with water, the inside and the outside of the shielding container 40 are communicated by the valve 43. If you do this,
Since the water in the equipment storage pit 102 flows into the shielding container 40 via the valve 43, it is not necessary to forcibly inject the water into the shielding container 40 by the pump 44. After the shield container 40 and the cylindrical member 41 are installed in the equipment storage pit 102, the valve 43 is switched to inject water from the pump 44, so that the water level in the shield container 40 and the cylindrical member 41 can be increased. .

【0062】第3変形例 本実施形態の第3変形例として、遮蔽容器40及び円筒
部材41を機器貯蔵ピット102の床面105以外の場
所に設置することができる。つまり、本実施形態による
原子炉の補修装置は、遮蔽容器40及び円筒部材41の
内部にポンプ44によって水を注入するようにしたの
で、機器貯蔵ピット102の床面105以外の場所に遮
蔽容器40及び円筒部材41を設置することができる。
Third Modification As a third modification of the present embodiment, the shielding container 40 and the cylindrical member 41 can be installed at a place other than the floor surface 105 of the equipment storage pit 102. That is, in the repair apparatus for a nuclear reactor according to the present embodiment, water is injected into the shield container 40 and the cylindrical member 41 by the pump 44. And the cylindrical member 41 can be installed.

【0063】このように遮蔽容器40及び円筒部材41
の設置場所は機器貯蔵ピット102の床面105に限定
されないので、炉内構造物の保管場所を増やすことがで
きる。
As described above, the shielding container 40 and the cylindrical member 41
Is not limited to the floor 105 of the equipment storage pit 102, so that the number of storage locations for the furnace internals can be increased.

【0064】[0064]

【発明の効果】以上述べたように本発明による原子炉の
補修装置及び方法によれば、放射能の高い炉内構造物を
水中に保管しつつ、原子炉ウェル及び原子炉容器の内部
を気相空間にすることができるので、原子炉容器の内部
での補修作業や原子炉容器自体の交換作業等の原子炉の
補修作業を気相空間において行うことによって作業の効
率を大幅に向上させることができる。
As described above, according to the apparatus and method for repairing a nuclear reactor according to the present invention, the inside of the reactor well and the interior of the nuclear reactor vessel are maintained while the reactor internal structure having high radioactivity is stored in water. Because it can be in a phase space, the work efficiency can be greatly improved by performing repair work inside the reactor vessel and replacing the reactor vessel itself, etc., in the gas phase space. Can be.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明の第1実施形態による原子炉の補修装置
を所定の位置に設置した状態を示した平面図。
FIG. 1 is a plan view showing a state where a repair apparatus for a nuclear reactor according to a first embodiment of the present invention is installed at a predetermined position.

【図2】図1の2−2線に沿った縦断面図。FIG. 2 is a longitudinal sectional view taken along line 2-2 of FIG.

【図3】図2のA部を拡大した縦断面図。FIG. 3 is an enlarged longitudinal sectional view of a portion A in FIG. 2;

【図4】(a)は図2のB部を拡大した平面図、(b)
は図2のB部を拡大した側面図。
4A is an enlarged plan view of a portion B in FIG. 2, FIG.
3 is an enlarged side view of a portion B in FIG. 2.

【図5】本発明の第2実施形態による原子炉の補修装置
を所定の位置に設置した状態を示した平面図。
FIG. 5 is a plan view showing a state where a repair device for a nuclear reactor according to a second embodiment of the present invention is installed at a predetermined position.

【図6】図5の6−6線に沿った縦断面図。FIG. 6 is a vertical sectional view taken along line 6-6 in FIG. 5;

【図7】図6のC部を拡大した縦断面図。FIG. 7 is an enlarged longitudinal sectional view of a portion C in FIG. 6;

【図8】本発明の第3実施形態による原子炉の補修装置
を所定の位置に設置した状態を示した縦断面図。
FIG. 8 is a longitudinal sectional view showing a state where a repair device for a nuclear reactor according to a third embodiment of the present invention is installed at a predetermined position.

【図9】本発明の第4実施形態による原子炉の補修装置
を所定の位置に設置した状態を示した縦断面図。
FIG. 9 is a longitudinal sectional view showing a state where a repair device for a nuclear reactor according to a fourth embodiment of the present invention is installed at a predetermined position.

【符号の説明】[Explanation of symbols]

1 隔離壁 2 隔離壁支持手段 3、21、42 水密シール部材 4 垂直支持部材 5 水平支持部材 6 水平連結部材 20 筒状隔離体 30 遮蔽カバー部材 31 切欠部 32、43 バルブ 33、44 ポンプ 40 遮蔽容器 41 円筒部材 100 原子炉圧力容器 101 原子炉ウェル 102 機器貯蔵ピット 103 燃料プール 106 原子炉ウェルの内壁面 109 気水分離器 110 蒸気乾燥器 111 操作床(オペレーションフロア) DESCRIPTION OF SYMBOLS 1 Isolation wall 2 Isolation wall support means 3, 21, 42 Watertight seal member 4 Vertical support member 5 Horizontal support member 6 Horizontal connection member 20 Cylindrical separator 30 Shield cover member 31 Notch 32, 43 Valve 33, 44 Pump 40 Shield Vessel 41 Cylindrical member 100 Reactor pressure vessel 101 Reactor well 102 Equipment storage pit 103 Fuel pool 106 Inner wall surface of reactor well 109 Steam separator 110 Steam dryer 111 Operation floor

───────────────────────────────────────────────────── フロントページの続き (72)発明者 佐 藤 勝 彦 神奈川県横浜市磯子区新杉田町8番地 株 式会社東芝横浜事業所内 (72)発明者 戸賀沢 裕 神奈川県横浜市磯子区新杉田町8番地 株 式会社東芝横浜事業所内 (72)発明者 五十嵐 越 郎 神奈川県横浜市磯子区新杉田町8番地 株 式会社東芝横浜事業所内 (72)発明者 島 村 光 明 神奈川県横浜市磯子区新杉田町8番地 株 式会社東芝横浜事業所内 (72)発明者 湯 口 康 弘 神奈川県横浜市磯子区新杉田町8番地 株 式会社東芝横浜事業所内 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Katsuhiko Sato, Inventor 8 at Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Inside the Toshiba Yokohama office (72) Inventor Yutaka Togasawa 8, Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Address Toshiba Yokohama Works (72) Inventor Koshio Igarashi 8 Shinsugita-cho, Isogo-ku, Yokohama, Kanagawa Prefecture 72 Toshiba Yokohama Works (72) Inventor Mitsuaki Shimamura Shinsugita-machi, Isogo-ku, Yokohama, Kanagawa No. 8 In the Toshiba Yokohama Office (72) Inventor Yasuhiro Yuguchi 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa In the Toshiba Yokohama Office

Claims (14)

【特許請求の範囲】[Claims] 【請求項1】原子炉容器の上方に形成された原子炉ウェ
ルと、この原子炉ウェルに隣接して形成された機器貯蔵
ピットとを備えた原子炉を補修するための原子炉の補修
装置において、 前記機器貯蔵ピット内の水を堰き止めるために前記機器
貯蔵ピットと前記原子炉ウェルとの境界に立設される隔
離壁と、 前記隔離壁に当接される部分及び前記原子炉ウェルの内
壁面に当接される部分を有する隔離壁支持手段と、を備
え、 前記機器貯蔵ピット内の水によって前記隔離壁に加えら
れる水圧を前記隔離壁支持手段を介して前記原子炉ウェ
ルの内壁面で受けることによって前記隔離壁を支持する
ようにしたことを特徴とする原子炉の補修装置。
A reactor repair apparatus for repairing a reactor having a reactor well formed above a reactor vessel and an equipment storage pit formed adjacent to the reactor well. An isolation wall erected at a boundary between the equipment storage pit and the reactor well for damping water in the equipment storage pit; and a portion abutting on the isolation wall and inside the reactor well. Isolation wall support means having a portion abutting against a wall surface, wherein water pressure applied to the isolation wall by water in the equipment storage pit is applied to the inner wall surface of the reactor well via the isolation wall support means. A repair device for a nuclear reactor, wherein the isolation wall is supported by receiving the same.
【請求項2】前記隔離壁の縁部に水密シール部材を設け
たことを特徴とする請求項1記載の原子炉の補修装置。
2. A repair apparatus for a nuclear reactor according to claim 1, wherein a watertight seal member is provided at an edge of said isolation wall.
【請求項3】原子炉容器の上方に形成された原子炉ウェ
ルと、この原子炉ウェルに隣接して形成された機器貯蔵
ピットとを備えた原子炉を補修するための原子炉の補修
装置において、 前記原子炉容器のフランジ部の外径よりも大きな内径を
有し、前記原子炉容器の真上の空間を周囲から隔離する
ために前記原子炉ウェル内に配置される筒状隔離体と、 前記筒状隔離体の下端部に周設された水密シール部材
と、を備えたことを特徴とする原子炉の補修装置。
3. A reactor repair apparatus for repairing a reactor having a reactor well formed above a reactor vessel and an equipment storage pit formed adjacent to the reactor well. A cylindrical isolator having an inner diameter larger than the outer diameter of the flange portion of the reactor vessel, and disposed in the reactor well to isolate a space directly above the reactor vessel from surroundings; A repair device for a nuclear reactor, comprising: a watertight seal member provided around a lower end portion of the cylindrical separator.
【請求項4】原子炉容器の上方に形成された原子炉ウェ
ルと、この原子炉ウェルに隣接して形成された機器貯蔵
ピットとを備えた原子炉を補修するための原子炉の補修
装置において、 前記機器貯蔵ピットに移送された炉内構造物の全体を上
方から覆うようにして配置され、前記炉内構造物全体を
内部に収納して周囲から隔離する遮蔽カバー部材と、 前記遮蔽カバー部材の下部に形成され、前記遮蔽カバー
部材の内部と外部との間に流体流路を形成する開口部
と、 前記遮蔽カバー部材の上部に設けられ、前記遮蔽カバー
部材の内部と外部との間に必要に応じて流体流路を形成
するための弁手段と、を備えたことを特徴とする原子炉
の補修装置。
4. A reactor repair apparatus for repairing a reactor having a reactor well formed above a reactor vessel and an equipment storage pit formed adjacent to the reactor well. A shielding cover member that is arranged so as to cover the entire furnace internal structure transferred to the equipment storage pit from above, and that houses the entire furnace internal structure therein to isolate it from the surroundings; An opening formed at a lower portion of the shield cover member to form a fluid flow path between the inside and the outside of the shield cover member, and provided at an upper portion of the shield cover member, between the inside and the outside of the shield cover member. A repair device for a nuclear reactor, comprising: valve means for forming a fluid flow path as required.
【請求項5】前記弁手段に前記遮蔽カバー部材の内部を
減圧するためのポンプ手段を接続したことを特徴とする
請求項4記載の原子炉の補修装置。
5. A repair apparatus for a nuclear reactor according to claim 4, wherein pump means for reducing the pressure inside said shielding cover member is connected to said valve means.
【請求項6】前記遮蔽カバー部材の高さは、前記機器貯
蔵ピットに前記遮蔽カバー部材を配置した場合に前記遮
蔽カバー部材の上端が操作床のレベルよりも高い位置に
あるように設定されていることを特徴とする請求項5記
載の原子炉の補修装置。
6. The height of the shielding cover member is set such that the upper end of the shielding cover member is located at a position higher than the level of the operation floor when the shielding cover member is disposed in the equipment storage pit. The repair device for a nuclear reactor according to claim 5, wherein
【請求項7】原子炉容器の上方に形成された原子炉ウェ
ルと、この原子炉ウェルに隣接して形成された機器貯蔵
ピットとを備えた原子炉を補修するための原子炉の補修
装置において、 炉内構造物を内部に収納するために前記機器貯蔵ピット
に配置される、上面が開放された遮蔽容器と、 前記遮蔽容器の下部に設けられ、前記遮蔽容器の内部と
外部との間に必要に応じて流体流路を形成するための弁
手段と、を備えたことを特徴とする原子炉の補修装置。
7. A reactor repair apparatus for repairing a reactor having a reactor well formed above a reactor vessel and an equipment storage pit formed adjacent to the reactor well. A shielding container having an open upper surface, which is disposed in the equipment storage pit for storing the furnace internals therein; provided at a lower portion of the shielding container, between the inside and the outside of the shielding container. A repair device for a nuclear reactor, comprising: valve means for forming a fluid flow path as required.
【請求項8】前記遮蔽容器の上端に前記遮蔽容器と同径
の筒状部材を取り外し可能且つ水密に連接したことを特
徴とする請求項7記載の原子炉の補修装置。
8. The repair apparatus for a nuclear reactor according to claim 7, wherein a cylindrical member having the same diameter as the shielding container is detachably and watertightly connected to an upper end of the shielding container.
【請求項9】前記遮蔽容器及び前記筒状部材の高さは、
前記機器貯蔵ピットに前記遮蔽容器及び前記筒状部材を
設置した場合に前記筒状部材の上端が操作床のレベルよ
りも高い位置にあるように設定されており、 前記弁手段に、前記遮蔽容器の内部に水を注入するため
のポンプ手段を接続したことを特徴とする請求項8記載
の原子炉の補修装置。
9. The height of the shielding container and the cylindrical member is as follows:
When the shielding container and the cylindrical member are installed in the equipment storage pit, the upper end of the cylindrical member is set at a position higher than the level of the operation floor, and the valve means includes the shielding container. 9. A repair apparatus for a nuclear reactor according to claim 8, wherein pump means for injecting water into the interior of the reactor are connected.
【請求項10】請求項1乃至請求項3のいずれか一項に
記載の原子炉の補修装置を用いた原子炉の補修方法であ
って、 原子炉ウェル及び機器貯蔵ピット内に水を注入した後、
原子炉容器内の炉内構造物を機器貯蔵ピットに移送し、
請求項1乃至請求項3のいずれか一項に記載の原子炉の
補修装置を所定の位置に配置し、少なくとも前記原子炉
容器の真上にある水を排出して気相空間とした後に原子
炉の補修作業を行うことを特徴とする原子炉の補修方
法。
10. A method for repairing a reactor using the repair apparatus for a reactor according to claim 1, wherein water is injected into the reactor well and the equipment storage pit. rear,
Transfer the internal structure of the reactor vessel to the equipment storage pit,
The reactor repair device according to any one of claims 1 to 3, wherein the repair device is disposed at a predetermined position, and at least water immediately above the reactor vessel is discharged to form a gas phase space. A method for repairing a nuclear reactor, comprising repairing the reactor.
【請求項11】請求項4記載の原子炉の補修装置を用い
た原子炉の補修方法であって、 原子炉ウェル及び機器貯蔵ピット内に水を注入した後、
原子炉容器内の炉内構造物を機器貯蔵ピットに移送し、
前記弁手段を開放した状態で前記遮蔽カバー部材によっ
て前記炉内構造物を上方から覆い、前記弁手段を開放状
態から閉鎖状態に切り換え、少なくとも前記原子炉ウェ
ル及び前記機器貯蔵ピットの水を排出して気相空間とし
た後に原子炉の補修作業を行うことを特徴とする原子炉
の補修方法。
11. A method for repairing a nuclear reactor using the repair apparatus for a nuclear reactor according to claim 4, wherein water is injected into the reactor well and the equipment storage pit.
Transfer the internal structure of the reactor vessel to the equipment storage pit,
With the valve means opened, the reactor internal structure is covered from above by the shielding cover member, the valve means is switched from the open state to the closed state, and at least the water in the reactor well and the equipment storage pit is discharged. A method for repairing a nuclear reactor, comprising performing repair work on the nuclear reactor after the space has been converted to a gas phase space.
【請求項12】請求項5又は請求項6に記載の原子炉の
補修装置を用いた原子炉の補修方法であって、 原子炉ウェル及び機器貯蔵ピット内に水を注入した後、
原子炉容器内の炉内構造物を機器貯蔵ピットに移送し、
前記弁手段を開放した状態で前記遮蔽カバー部材によっ
て前記炉内構造物を上方から覆い、前記ポンプ手段によ
って前記遮蔽カバー部材の内部を減圧し、前記弁手段を
開放状態から閉鎖状態に切り換え、少なくとも前記原子
炉ウェル及び前記機器貯蔵ピットの水を排出して気相空
間とした後に原子炉の補修作業を行うことを特徴とする
原子炉の補修方法。
12. A method for repairing a nuclear reactor using the repair equipment for a nuclear reactor according to claim 5 or 6, wherein water is injected into the reactor well and the equipment storage pit.
Transfer the internal structure of the reactor vessel to the equipment storage pit,
In the state in which the valve means is opened, the inside of the furnace is covered with the shielding cover member from above, the inside of the shielding cover member is depressurized by the pump means, and the valve means is switched from the open state to the closed state. A method for repairing a nuclear reactor, comprising performing a repair work on a nuclear reactor after draining water from the reactor well and the equipment storage pit to form a gas phase space.
【請求項13】請求項7又は請求項8に記載の原子炉の
補修装置を用いた原子炉の補修方法であって、 原子炉ウェル及び機器貯蔵ピット内に水を注入した後、
前記弁手段を開放した状態で前記遮蔽容器を前記機器貯
蔵ピットに配置し、前記弁手段を開放状態から閉鎖状態
に切り換え、原子炉容器内の炉内構造物を前記遮蔽容器
の内部に移送し、少なくとも前記原子炉ウェル及び前記
機器貯蔵ピットの水を排出して気相空間とした後に原子
炉の補修作業を行うことを特徴とする原子炉の補修方
法。
13. A method for repairing a nuclear reactor using the repair equipment for a nuclear reactor according to claim 7 or 8, wherein water is injected into the reactor well and the equipment storage pit.
With the valve means open, the shielding vessel is placed in the equipment storage pit, the valve means is switched from the open state to the closed state, and the internal structure in the reactor vessel is transferred to the inside of the shielding vessel. A method for repairing a nuclear reactor, wherein the repair work of the nuclear reactor is performed after at least water in the reactor well and the equipment storage pit is drained to form a gas space.
【請求項14】請求項9記載の原子炉の補修装置を用い
た原子炉の補修方法であって、 水がない状態の前記機器貯蔵ピットに前記遮蔽容器を配
置し、原子炉容器内の炉内構造物を前記遮蔽容器の内部
に移送し、前記ポンプ手段によって開放状態の前記弁手
段を介して前記遮蔽容器の内部に水を注入し、前記弁手
段を開放状態から閉鎖状態に切り換え、少なくとも前記
原子炉ウェル及び前記機器貯蔵ピットを気相空間として
原子炉の補修作業を行うことを特徴とする原子炉の補修
方法。
14. A method for repairing a nuclear reactor using the repair equipment for a nuclear reactor according to claim 9, wherein the shielding vessel is disposed in the equipment storage pit in a state where there is no water, and the reactor in the reactor vessel is provided. Transferring the internal structure into the shielding container, injecting water into the shielding container through the valve means in an open state by the pump means, switching the valve means from an open state to a closed state, A method for repairing a nuclear reactor, wherein repair work of the nuclear reactor is performed using the reactor well and the equipment storage pit as a gas space.
JP8281014A 1996-10-23 1996-10-23 Repairing device and method for reactor Pending JPH10123278A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP8281014A JPH10123278A (en) 1996-10-23 1996-10-23 Repairing device and method for reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP8281014A JPH10123278A (en) 1996-10-23 1996-10-23 Repairing device and method for reactor

Publications (1)

Publication Number Publication Date
JPH10123278A true JPH10123278A (en) 1998-05-15

Family

ID=17633088

Family Applications (1)

Application Number Title Priority Date Filing Date
JP8281014A Pending JPH10123278A (en) 1996-10-23 1996-10-23 Repairing device and method for reactor

Country Status (1)

Country Link
JP (1) JPH10123278A (en)

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