JPH0464600B2 - - Google Patents

Info

Publication number
JPH0464600B2
JPH0464600B2 JP60231199A JP23119985A JPH0464600B2 JP H0464600 B2 JPH0464600 B2 JP H0464600B2 JP 60231199 A JP60231199 A JP 60231199A JP 23119985 A JP23119985 A JP 23119985A JP H0464600 B2 JPH0464600 B2 JP H0464600B2
Authority
JP
Japan
Prior art keywords
plug
shield
pipe
reactor
piping
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
JP60231199A
Other languages
Japanese (ja)
Other versions
JPS6291898A (en
Inventor
Tetsuo Matsuzaki
Masanori Suzuki
Koichi Saito
Tomojiro Sato
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.)
Hitachi Engineering Co Ltd
Hitachi Ltd
Original Assignee
Hitachi Engineering Co Ltd
Hitachi Ltd
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 Hitachi Engineering Co Ltd, Hitachi Ltd filed Critical Hitachi Engineering Co Ltd
Priority to JP60231199A priority Critical patent/JPS6291898A/en
Publication of JPS6291898A publication Critical patent/JPS6291898A/en
Publication of JPH0464600B2 publication Critical patent/JPH0464600B2/ja
Granted 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
    • 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

  • Manipulator (AREA)
  • Absorbent Articles And Supports Therefor (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Pressure Vessels And Lids Thereof (AREA)

Description

【発明の詳細な説明】 〔発明の利用分野〕 本発明は、原子炉生体しやへい壁の配管が貫通
するしやへいプラグ構造に係り、定検や改造時の
作業効率を大幅に向上できる原子炉しやへい体の
しやへいプラグ構造に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a shield plug structure through which piping penetrates through a nuclear reactor housing wall, and can greatly improve work efficiency during periodic inspections and modifications. Concerning the structure of the shield plug of the reactor shield body.

〔発明の背景〕[Background of the invention]

原子炉格納容器全体を表わす縦断面図を第3図
に、従来構造の原子炉しやへいプ体のしやへいラ
グ部の詳細を第4図に、しやへいプラグ組立て・
取外し手順を第5図に示す。
Figure 3 shows a longitudinal cross-sectional view of the entire reactor containment vessel, and Figure 4 shows details of the shield lug of the conventional reactor shield body, and Figure 4 shows the details of the shield plug assembly and shield plug assembly.
The removal procedure is shown in Figure 5.

原子炉格納容器1に内包され、原子炉圧力容器
2からの放射線をしやへいするため、原子炉生体
しやへい壁3が設けられている。この原子炉生体
しやへい壁3は、原子炉運転時及び定期検査時に
原子炉から各種の放射線が放出され、人体、機器
及び材料等への悪影響を防止するために設けられ
た一次しやへい壁である。
A reactor body shielding wall 3 is included in the reactor containment vessel 1 and is provided to shield radiation from the reactor pressure vessel 2. This reactor biological shield wall 3 is a primary shield installed to prevent various types of radiation from being emitted from the reactor during reactor operation and periodic inspections, and to prevent adverse effects on the human body, equipment, materials, etc. It's a wall.

また、原子炉圧力容器2には、各種ノズル4が
設けられ、このノズル4が配管5に接続されてい
る。さらに、配管5は原子炉生体しやへい壁3を
貫通し、原子炉格納容器1内の配管に接続されて
いる。
Further, the reactor pressure vessel 2 is provided with various nozzles 4, and these nozzles 4 are connected to piping 5. Furthermore, the piping 5 penetrates the reactor housing wall 3 and is connected to piping inside the reactor containment vessel 1.

この原子炉生体しやへい壁3の貫通口は、第4
図に示す様に鋼板6、及び鋼板とコンクリートと
の一体構造物のプラグ7で構成されている。この
プラグ6,7は、貫通口に配管貫通用の切欠き8
を設けた凹形ブロツクを重ね合わせた分割構造と
なつている。尚、第4図は片側のプラグが取り外
された状態を示している。
This through hole in the reactor bio-insulating wall 3 is the fourth
As shown in the figure, it consists of a steel plate 6 and a plug 7 that is an integral structure of the steel plate and concrete. These plugs 6 and 7 have a notch 8 in the through hole for passing through the pipe.
It has a divided structure of overlapping concave blocks with . Note that FIG. 4 shows a state in which one side of the plug is removed.

また、原子炉のノズル4と接続される配管5の
接合部は、供用期間中の検査、すなわちインサー
ビスインスペクシヨン(以下、ISIと称す。)を受
ける。このため、しやへいプラグ部は、貫通口8
を中心とした凹形ブロツク構造として、貫通口の
軸方向に複数列にし、貫通欠の左右2分口の縦型
凹形ブロツクを重ね合わせ、止め具9で固定され
た構造となつている。これは、各ブロツク状のプ
ラグ6,7を貫通口8の軸方向で、生体しやへい
の外側に取外し可能な構造としたものであり、
ISI時の検査口及び検査用スペース確保のための
構造である。
Further, the joint portion of the piping 5 connected to the nozzle 4 of the nuclear reactor undergoes an inspection during the service period, that is, an in-service inspection (hereinafter referred to as ISI). For this reason, the thin plug part is
As a concave block structure centered on the through hole, the vertical concave blocks of the right and left halves of the through hole are stacked in a plurality of rows in the axial direction of the through hole and fixed with a stopper 9. This has a structure in which each block-shaped plug 6, 7 can be removed from the outside of the living body shield in the axial direction of the through hole 8.
This structure is designed to secure an inspection port and space for inspection during ISI.

しかし、本構造に示すように、プラグ6,7の
貫通口8近傍には、多数の原子炉主要配管(主蒸
気配管10及びPLR配管11等)が近接して設
けられ、プラグ6,7の貫通口8を通る配管5
は、貫通口8近傍での迂回が必要である。
However, as shown in this structure, a large number of main reactor pipings (main steam piping 10, PLR piping 11, etc.) are installed close to each other near the through holes 8 of the plugs 6, 7. Piping 5 passing through through hole 8
requires a detour near the through hole 8.

また、本構造におけるISI検査時の作業手順は、
以下のようになる。
In addition, the work procedure for ISI inspection of this structure is as follows:
It will look like this:

() 原子炉生体しやへい壁3プラグ6,7上部
に吊り込み治具12の設置。
() Installation of the hanging jig 12 above the reactor housing wall 3 plugs 6 and 7.

()プラグの止め具9の取外し。()Remove the stopper 9 of the plug.

() 配管迂回なし側の鋼板プラグ、鋼板とコン
クリートのプラグ等の、原子炉生体しやへい壁
3の外側への吊り込み治具等による取外し。
() Removal of steel plate plugs on the side without piping detour, steel plate and concrete plugs, etc. using a hanging jig, etc. to the outside of the reactor bioshield wall 3.

() プラグ取外し部の空間からのISI作業員及
び作業工具の搬入。
() ISI workers and work tools are brought in through the space in the plug removal area.

() プラグ取外し部を足場として、原子炉生体
しやへい壁3と原子炉圧力容器2とのわずかの
空間でのISI作業。
() Using the plug removal area as a foothold, ISI work was carried out in the small space between the reactor biological wall 3 and the reactor pressure vessel 2.

() ISI作業終了後は、上気()〜()の
逆作業となる。
() After the ISI work is completed, the work will be the reverse of Joki () to ().

また、片側のプラグ取外し部の空間スペース
は、人間が背をまるめて通過できるぎりぎりのス
ペースとなつている。
Furthermore, the space in the plug removal section on one side is just enough for a person to pass through with their backs bent.

このような構造であるため、以下に示す問題点
がある。
This structure has the following problems.

(a) 原子炉生体しやへい壁3を貫通する配管5
が、生体しやへい壁3の外周の開口近傍で迂回
ルートとなるため、しやいイプラグ6,7の片
側ブロツクしか取外せず、十分な作業スペース
を確保できずISI時の作業員及び工具搬出入が
断続的となり、作業遅延の要因となつている。
(a) Piping 5 penetrating the reactor biological wall 3
However, since the detour route is near the opening on the outer periphery of the biological shielding wall 3, only one side block of the flexible plugs 6 and 7 can be removed, and sufficient work space cannot be secured for workers and tools during ISI. Loading and unloading is intermittent, causing work delays.

(b) ISI時の作業スペースとして、原子炉圧力容
器2と原子炉生体しやへい壁3との空間スペー
スは、わずかであり、圧力容器ノズル4と配管
5との検査時に、しやへいプラグ取外し部を足
場とするため、足場スペースに余裕がなく作業
がしずらい。
(b) As a working space during ISI, the space between the reactor pressure vessel 2 and the reactor bio-insulating wall 3 is small, and when inspecting the pressure vessel nozzle 4 and piping 5, Since the removed part is used as a scaffold, there is not enough scaffolding space, making it difficult to work.

以上の従来技術の問題点を解決すべく、原子炉
生体しやへい壁貫通口のしやへいプラグ構造の改
善が切に望まれている。
In order to solve the above-mentioned problems of the prior art, it is strongly desired to improve the structure of the shield plug of the nuclear reactor housing wall penetration port.

なお、このしやへいプラグ6,7は原子炉生体
しやへい壁3にはめ込まれ、配管5の貫通口8を
構成している独立の構造物であるため、既設、新
設プラントにかかわらず、しやへいプラグ6,7
自体の構造改善により、ISIあるいは修復作業の
率向上が身込まれる。
Note that the shielding plugs 6 and 7 are independent structures that are fitted into the reactor biological shielding wall 3 and constitute the through hole 8 of the piping 5, so regardless of whether the plant is an existing one or a new one, Shiyahei plug 6,7
Improving the structure itself will improve the rate of ISI or repair work.

この種従来技術を示すものとしては実開昭53−
95988号公報がある。
As a demonstration of this type of conventional technology,
There is a publication number 95988.

〔発明の目的〕[Purpose of the invention]

発明の目的は、原子炉圧力容器ノズルと配管の
接合部のISI作業及び修復作業の作業スペースを
確保し、作業の大幅な効率向上及び信頼性向上を
図り得る、原子炉生体しやへい壁の貫通口を構成
する原子炉しやへい体のしやへいプラグ構造を得
ることにある。
The purpose of the invention is to secure a working space for ISI work and repair work at the joint between the reactor pressure vessel nozzle and piping, and to improve the work efficiency and reliability. The object of the present invention is to obtain a flexible plug structure for a nuclear reactor shield body constituting a through hole.

〔発明の概要〕[Summary of the invention]

本発明は、構成要件として、原子炉のしやへい
壁を配管が貫通してその配管の延長が貫通直後の
位置から水平方向の一方へ曲げられている前記配
管と前記しやへい壁の貫通部貫通孔内壁面の間〓
間に分割自在なしやへいブロツクが配備されてい
るしやへいプラグ構造において、少なくとも前記
配管の前記曲げ方向の前記〓間に配備される前記
しやへいブロツクは、前記配管と前記〓間の上端
乃至は下端との間の〓間寸法を通過できる高さ寸
法以下の高さ寸法を有して上下三段に分割されて
いるとともに、前記上下三段の各しやへいブロツ
クは左右方向に無分割であり、且つ前記配管が貫
通する部分には前記しやへいブロツクの前記配管
方向への移動を阻止するストツパを設けられてい
ることを特徴とした原子炉しやへい体のしやへい
プラグ構造を有し、その構成要件により、貫通し
ている配管が或いはその配管に延長接続された配
管がしやへいブロツクの出入り正面に通されて、
全体として配管が曲げられている状態でも、配管
と前記〓間の上端或いは下端の間の〓間を利用し
て貫通部貫通孔内外に出し入れ出来、その回数が
しやへいブロツクを大型化しているから減少して
迅速に効率良い作業で広い作業スペース貫通部貫
通孔に得たり、或いはそのスペースを塞いだりす
る作用が得られ、しやへいブロツクを大型化でブ
ロツク間の合わせ目も少なくてしやへい信頼性も
良くなるという作用も得られる。
The present invention provides, as a structural feature, a pipe that penetrates a thin wall of a nuclear reactor, and an extension of the pipe that is bent in one direction in the horizontal direction from a position immediately after the penetration, and a penetration of the thin wall. Between the inner wall surfaces of the through hole〓
In the shrink plug structure in which a divisible shield block is provided between the pipes, at least the shrink block arranged between the pipes in the bending direction is arranged at the upper end between the pipe and the pipes. The block is divided into three upper and lower stages with a height that is less than or equal to the height that allows the block to pass through the distance between the block and the lower end, and each of the three upper and lower stages has no space in the left and right direction. A flexible plug for a nuclear reactor shield body, characterized in that the plug is divided, and a stopper is provided at a portion through which the piping passes through to prevent movement of the shield block in the direction of the piping. structure, and depending on its configuration requirements, the piping that passes through it or the piping that is extended and connected to the piping is passed through the entrance/exit front of the shield block,
Even when the pipe as a whole is bent, it is possible to insert and remove the pipe into and out of the through-hole by using the space between the pipe and the upper or lower end of the pipe, making the block larger and the number of times it must be removed is reduced. It is possible to quickly and efficiently work by reducing the amount of work required to create a wide work space through the through hole, or to block that space. It also has the effect of improving reliability.

〔発明の実施例〕[Embodiments of the invention]

本発明は、原子炉生体しやへい壁の配管の貫通
口を構成するしやへいプラグ構造において、生体
しやへい壁内側への機器の搬入、ISI及び修復作
業のスペース確保として、配管まわりのしやへい
プラグ全体を完全に取外し可能な分割ブロツク構
造としたことにある。
The present invention is aimed at securing space for carrying equipment inside the biological wall, ISI, and repair work in the shield plug structure that constitutes the piping penetration in the biological shield wall of a nuclear reactor. The reason is that the entire shield plug has a split block structure that is completely removable.

以下、本発明の実施例を具体的に説明する。 Examples of the present invention will be specifically described below.

第1図に本発明の実施例である原子炉しやへい
体のしやへいプラグ構造全体の鳥瞰図を示し、第
2図にそのプラグの取外し手順を示す。
FIG. 1 shows a bird's-eye view of the entire structure of a shield plug for a nuclear reactor shield according to an embodiment of the present invention, and FIG. 2 shows a procedure for removing the plug.

第1図において、しやへいプラグは分割ブロツ
ク状のプラグA,B,C,D,E,F、及びスト
ツパ13、止め具9で構成されている。分割ブロ
ツク状のプラグA〜Fは従来構造における縦型凹
形のブロツクとは異なり、水平方向分割とし、水
平方向の各ブロツク状のプログの移動を可能にし
た構造である。
In FIG. 1, the shield plug is composed of divided block-shaped plugs A, B, C, D, E, and F, a stopper 13, and a stopper 9. The divided block-shaped plugs A to F are different from the vertical concave blocks in the conventional structure, and have a structure in which they are divided horizontally and each block-shaped plug can be moved in the horizontal direction.

さらに、各分割プラグの中央の貫通口には、配
管5の貫通口を構成する〓型のストツパ13を設
け、各ブロツク状の分割プラグA〜Fを支持さ
せ、また、原子炉生体しやへい壁3の外側の原子
炉格納容器1側には、従来同様に取り外し可能な
止め具9にてプラグA〜F全体を固定している。
Furthermore, a square-shaped stopper 13, which constitutes a through-hole for the piping 5, is provided at the center through-hole of each split plug, supporting each of the block-shaped split plugs A to F, and also protecting the reactor's biological body. Plugs A to F are all fixed to the reactor containment vessel 1 side outside the wall 3 with removable fasteners 9 as in the conventional case.

次に、本実施例のしやへいプラグにおけるISI
時の作業手順は、第2図に示すように以下の手順
となる。
Next, the ISI in the Shiyahei plug of this example is
The work procedure at this time is as follows, as shown in Figure 2.

() 原子炉生体しやへい壁3のプラグA〜F上
部に吊り込み治具12の設置及びプラグの止め
具9の取外しを行う。
() Install the hanging jig 12 above the plugs A to F of the reactor housing wall 3 and remove the plug stopper 9.

() 吊り込み治具12を用いて、分割プラグ
A,Bを水平移動させ、原子炉生体しやへい壁
3の外側に外す。
() Using the lifting jig 12, move the split plugs A and B horizontally and remove them to the outside of the reactor housing shield wall 3.

() 次に、()同様の吊り込み治具12を用
いて、分割プラグC、ストツパ13、及びDを
上方の分割プラグA,Bの位置まで引き上げ、
同時に、水平移動させて生体しやへい壁3の外
側に外す。
() Next, using a lifting jig 12 similar to (), pull up the split plug C, stopper 13, and D to the position of the split plugs A and B above,
At the same time, it is moved horizontally and removed to the outside of the living body wall 3.

() 上記()同様に、分割プラグE,Fを水
平移動させ、生体しやへい壁の外側に外す。
() Similar to () above, move the split plugs E and F horizontally and remove them to the outside of the living body wall.

() 以下、従来技術同様のISI作業員及び工具
の搬入及び検査作業となる。
() Hereafter, the ISI workers and tools will be brought in and inspected as in the conventional technology.

すなわち、ISI検査時の分割プラグA〜Fの取
外し及び作業終了後の組立て手順は次のようにな
る。
That is, the procedure for removing the split plugs A to F during the ISI inspection and assembling them after completion of the work is as follows.

分割プラグの解体はA→B→C→ストツパ→D
→E→Fとなり組立はF→E→D→ストツパ→C
→B→Aの手順になる。
Disassembling the split plug is A → B → C → Stopper → D
→E → F and assembly is F → E → D → stopper → C
The procedure is →B→A.

本実施例では、鋼板による分割プラグAと鋼板
とコンクリートとの一体構造物による分割プラグ
B、同じく鋼板による分割プラグEと鋼板とコン
クリートとの一体構造物による分割プラグFとは
互いに分割されていて、分割プラグの組立て及び
解体が楽に出来るように配慮されているが、分割
せずとも良く、分割せずにすめば、組立て及び分
解作業対象分割プラグ個数が減るから、それにこ
したことは無い。
In this embodiment, a split plug A made of a steel plate, a split plug B made of an integral structure of a steel plate and concrete, and a split plug E made of a steel plate and a split plug F made of an integral structure of a steel plate and concrete are separated from each other. Although consideration has been given to making it easy to assemble and disassemble the split plugs, it is not necessary to split the plugs, and if the split plugs are not split, the number of split plugs to be assembled and disassembled will be reduced, so there is no harm in doing so.

本実施例では、以上のような構成と作業手順で
あるため、次のような効果を奏する。
In this embodiment, since the configuration and work procedure are as described above, the following effects are achieved.

(a) 生体しやへい壁3の貫通口を構成するしやへ
いプラグA〜F全体を取外すことができるた
め、ISI時の原子炉圧力容器ノズル4と配管5
の接合部までの作業員の操作スペースが十分確
保でき、作業員及び作業工具の搬出入の効率向
上ができる。
(a) Since the entire shield plugs A to F that constitute the penetration holes in the biological shield wall 3 can be removed, the reactor pressure vessel nozzle 4 and piping 5 during ISI can be removed.
Sufficient operating space for workers up to the joints can be secured, and the efficiency of carrying in and out of workers and work tools can be improved.

(b) 原子炉圧力容器ノズル4と配管5の接合部の
ISI時に足場として使用されるしやへいプラグ
A〜Fの取外し後部が、配管5まわり全周に空
間を確保できることとなるため、ISI作業及び
配管の修復作業スペースが十分確保できる。
(b) Joint between reactor pressure vessel nozzle 4 and piping 5
Since space can be secured all around the pipe 5 at the rear of the removal of the shield plugs A to F, which are used as scaffolding during ISI, sufficient space can be secured for ISI work and pipe repair work.

(c) 作業対象配管5まわりに、十分な空間スペー
スが確保できるため、複数の作業員による作業
が可能となる。
(c) Since sufficient space can be secured around the pipe 5 to be worked on, work can be carried out by multiple workers.

次に、本発明の他の実施例について説明する。 Next, other embodiments of the present invention will be described.

前述の実施例では、プラグの開放が片側だけで
支障がない作業の場合でも、全面開放、すなわち
すべてのプラグを解体しなければならない。この
ため無駄な作業が発生する。
In the above-mentioned embodiment, even if the plug is opened only on one side and there is no problem, the entire plug must be opened, that is, all the plugs must be dismantled. This results in wasted work.

例えば第4図に示す従来構造の様に配管がプラ
グ前面で迂回している側と相対する側のプラグは
従来構造でも解体が可能である。
For example, as in the conventional structure shown in FIG. 4, it is possible to dismantle the plug on the side opposite to the side where the piping detours in front of the plug.

本発明の他の実施例では上記の様に片側開放だ
けで作業が可能な場合は片側のみ従来構造とし配
管がプラグ前面で迂回している等で従来構造のプ
ラグでは開放不可能の場合においては該プラグの
みを本発明を採用する。すなわち、従来構造と本
発明の構造を組合せたものである。
In other embodiments of the present invention, as mentioned above, if work can be done by opening only one side, only one side has the conventional structure, and if the plug cannot be opened with the conventional structure because the piping is detoured in front of the plug, etc. The present invention is applied only to this plug. That is, it is a combination of the conventional structure and the structure of the present invention.

本発明の他の実施例によれば、上記条件の個所
のプラグの操作性においてより有利な効果が得ら
れる。
According to another embodiment of the present invention, more advantageous effects can be obtained in terms of the operability of the plug at the location where the above conditions are met.

次に、上記実施例によるプラグの開放操作を第
6図により説明する。
Next, the plug opening operation according to the above embodiment will be explained with reference to FIG.

図において、矢印はプラグの開放手順を示して
いる。
In the figure, arrows indicate the procedure for opening the plug.

すなわち、プラグを解体する方向に干渉物のな
い側のプラグにおいては、従来の構造のしやへい
プラグ6′,7′を採用し、従来の方法でプラグを
水平方向bからcの方向に引き出して片側の解放
dをする。片側解放のみで作業に支障をきたさな
い場合は本操作で作業が完了する。
That is, for the plug on the side where there is no interference in the direction of dismantling the plug, the flexible plugs 6' and 7' of the conventional structure are used, and the plug is pulled out in the horizontal direction from b to c using the conventional method. and release d on one side. If releasing only one side does not interfere with the work, complete the work with this operation.

更に、両側の解放が必要な場合は、残在するプ
ラグ中の上部プラグA′,B′が配管等に干渉しな
いため、水平方向eからfの方向に引き出すこと
が可能である。次に中間部プラグC′は上部に空間
ができるため、配管等の干渉物をさけるまで上部
に移動した後に水平方向に引き出す(gからhの
方向)。
Further, when it is necessary to release both sides, the upper plugs A' and B' of the remaining plugs do not interfere with the piping, etc., so that they can be pulled out in the horizontal direction from e to f. Next, since there is a space at the top of the intermediate plug C', move it to the top until it avoids interference such as piping, and then pull it out horizontally (in the direction from g to h).

以下ストツパ13′を解体し、下部プラグは干
渉物の形状により(i)方向又は(j)方向のいずれかで
解体し、プラグの両側開放を完了する。
Thereafter, the stopper 13' is disassembled, and the lower plug is disassembled in either the (i) direction or (j) direction depending on the shape of the interfering object, thereby completing the opening of both sides of the plug.

復旧作業は上記作業を逆にすることで可能であ
る。
Restoration work can be done by reversing the above work.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、配管がしやへいブロツクの出
入り正面に通されていても分割しやへいブロツク
の配管貫通部への出し入れ回数、言い替えれば個
数を少なくして迅速にしやへい体を組立て及び解
体できるから、ISIや修復作業のための広い作業
スペースが迅速かつ効率良く得られ、ISIや修復
作業の効率と信頼性とを向上できる。
According to the present invention, even if the pipe passes through the front of the flexible block, the flexible block can be assembled quickly by reducing the number of times, or in other words, the number of pieces, of the flexible block being moved in and out of the pipe penetration portion. Since it can be dismantled, a large working space for ISI and repair work can be quickly and efficiently obtained, improving the efficiency and reliability of ISI and repair work.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明の一実施例である原子炉しやへ
い体のしやへいプラグ構造を示す鳥瞰図、第2図
は第1図に示す実施例においてしやへいプラグの
取外し手順を示す図、第3図は原子炉格納容器全
体を示す縦断面図、第4図は従来の原子炉しやへ
い体のしやへいプラグ構造を示す鳥瞰図、第5図
は第4図に示すしやへいプラグの取外し手順を示
す図、第6図は本発明の他の実施例におけるしや
へいプラグの取外し手順を示す図である。 1……原子炉格納容器、2……原子炉圧力容
器、3……原子炉生体しやへい壁、4……原子炉
圧力容器ノズル、5……配管、6,6′……鋼板
プラグ、7,7′……プラグ、8……貫通口、9
……止め具、10……主蒸気配管、11……
PLR配管、12……吊り込み治具、13,1
3′……ストツパ、A,A′……プラグA、B,
B′……プラグB、C,C′……プラグC、D,
D′……プラグD、E,E′……プラグE、F……プ
ラグF。
Figure 1 is a bird's-eye view showing the shield plug structure of a nuclear reactor shield body which is an embodiment of the present invention, and Figure 2 is a diagram showing the procedure for removing the shield plug in the embodiment shown in Figure 1. , Figure 3 is a vertical cross-sectional view showing the entire reactor containment vessel, Figure 4 is a bird's-eye view showing the shield plug structure of a conventional reactor shield body, and Figure 5 is the shield shown in Figure 4. FIG. 6 is a diagram illustrating a procedure for removing a plug in another embodiment of the present invention. 1... Reactor containment vessel, 2... Reactor pressure vessel, 3... Reactor biological wall, 4... Reactor pressure vessel nozzle, 5... Piping, 6, 6'... Steel plate plug, 7, 7'...Plug, 8...Through hole, 9
... Stopper, 10 ... Main steam piping, 11 ...
PLR piping, 12...Hoisting jig, 13,1
3'...Stopper, A, A'...Plug A, B,
B'...Plug B, C, C'...Plug C, D,
D'...Plug D, E, E'...Plug E, F...Plug F.

Claims (1)

【特許請求の範囲】[Claims] 1 原子炉のしやへい壁を配管が貫通してその配
管の延長が貫通直後の位置から水平方向の一方へ
曲げられている前記配管と前記しやへい壁の貫通
部貫通孔内壁面の間の〓間に分割自在なしやへい
ブロツクが配備されているしやへいプラグ構造に
おいて、少なくとも前記配管の前記曲げ方向の前
記〓間に配備される前記しやへいブロツクは、前
記配管と前記〓間の上端乃至は下端との間の〓間
寸法を通過できる高さ寸法以下の高さ寸法を有し
て上下三段に分割されているとともに、前記上下
三段の各しやへいブロツクは左右方向に無分割で
あり、且つ前記配管が貫通する部分には前記しや
へいブロツクの前記配管方向への移動を阻止する
ストツパを設けられていることを特徴とした原子
炉しやへい体のしやへいプラグ構造。
1. Between the pipe that penetrates the shield wall of the reactor and the extension of the pipe is bent in one direction in the horizontal direction from the position immediately after the penetration, and the inner wall surface of the through hole of the penetration part of the shield wall. In the shield plug structure in which a divisible shield block is disposed between the pipe and the pipe, the shield block disposed at least between the pipe in the bending direction is arranged between the pipe and the pipe. It is divided into three upper and lower stages with a height that is less than the height that allows passage between the upper end and the lower end, and each of the upper and lower three stages is A shield for a nuclear reactor shield, characterized in that the shield is undivided, and a stopper is provided at a portion through which the pipe penetrates to prevent the shield block from moving in the direction of the pipe. Hei plug structure.
JP60231199A 1985-10-18 1985-10-18 Shielding plug structure of nuclear reactor shielding body Granted JPS6291898A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60231199A JPS6291898A (en) 1985-10-18 1985-10-18 Shielding plug structure of nuclear reactor shielding body

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60231199A JPS6291898A (en) 1985-10-18 1985-10-18 Shielding plug structure of nuclear reactor shielding body

Publications (2)

Publication Number Publication Date
JPS6291898A JPS6291898A (en) 1987-04-27
JPH0464600B2 true JPH0464600B2 (en) 1992-10-15

Family

ID=16919893

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60231199A Granted JPS6291898A (en) 1985-10-18 1985-10-18 Shielding plug structure of nuclear reactor shielding body

Country Status (1)

Country Link
JP (1) JPS6291898A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5750098B2 (en) * 1978-08-10 1982-10-26
JPS59180496A (en) * 1983-03-31 1984-10-13 株式会社日立製作所 Pipe penetration structure of reactor biologcal shielding wall

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6222876Y2 (en) * 1980-09-09 1987-06-10

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5750098B2 (en) * 1978-08-10 1982-10-26
JPS59180496A (en) * 1983-03-31 1984-10-13 株式会社日立製作所 Pipe penetration structure of reactor biologcal shielding wall

Also Published As

Publication number Publication date
JPS6291898A (en) 1987-04-27

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