JPS61192986A - Piping penetrating section structure of reactor container - Google Patents

Piping penetrating section structure of reactor container

Info

Publication number
JPS61192986A
JPS61192986A JP60030431A JP3043185A JPS61192986A JP S61192986 A JPS61192986 A JP S61192986A JP 60030431 A JP60030431 A JP 60030431A JP 3043185 A JP3043185 A JP 3043185A JP S61192986 A JPS61192986 A JP S61192986A
Authority
JP
Japan
Prior art keywords
penetration
containment vessel
reactor containment
piping
reactor
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP60030431A
Other languages
Japanese (ja)
Inventor
益田 淳一
根矢 武雄
正範 鈴木
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 Ltd
Original Assignee
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 Ltd filed Critical Hitachi Ltd
Priority to JP60030431A priority Critical patent/JPS61192986A/en
Publication of JPS61192986A publication Critical patent/JPS61192986A/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

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  • Devices For Medical Bathing And Washing (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の利用分野〕 原子カプラントの生体じゃへい体配筋と原子炉格納容器
のペネトレーションの関係において、生体じゃへい体配
筋の大組施工を可能とするペネトレーションの構造に係
わる。
[Detailed Description of the Invention] [Field of Application of the Invention] Penetration structure that enables large-scale assembly construction of living body reinforcement in the relationship between the biological reinforcement of an atomic couplant and the penetration of a nuclear reactor containment vessel. related to.

〔発明の背景〕[Background of the invention]

現在一般に実施されている原子炉格納容器のペネトレー
ションの取り付けは、生体じゃへい体配筋施工前となっ
ており、この手順のまま、鉄筋を別の場所で大組し、こ
れを一括吊込みするとき。
Currently, the installation of penetration in the reactor containment vessel that is generally carried out is done before constructing the living body reinforcements, and following this procedure, the reinforcing bars are assembled in a separate location and then suspended all at once. When.

−基の原子炉格納容器に取り付けられている100本以
上のペネトレーションの長さが、約3000m厘もあり
、大半が放射状に配置されているため、上記大組した鉄
筋を水平でかつ求心方向にアクセスしても、ペネトレー
ションの求心方向の開きのため、鉄筋と干渉し、大組鉄
筋工法は、実際上、非常に困難である。
-The length of the more than 100 penetration bars attached to the primary reactor containment vessel is approximately 3,000 meters, and most of them are arranged radially, so the large-scale assembly of reinforcing bars mentioned above can be aligned horizontally and centripetally. Even if it is accessed, the centripetal opening of the penetration interferes with the reinforcing bars, making the large-assembly reinforcing bar construction method extremely difficult in practice.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、原子カプラントの建設工程のクリティ
カルパスである生体じゃへい体の施工工期の大半を占め
る配筋施工工期を短縮する一方策としての鉄筋大組工法
の障害となる原子炉格納容器のペネトレーションを、上
記鉄筋施工後とすることで、鉄筋大組工法の適用を可能
とし、プラント建設工期を大幅に短縮することにある。
The purpose of the present invention is to shorten the reinforcing structure construction period, which accounts for most of the construction period for biomechanical structures, which is a critical path in the construction process of nuclear power plants. By performing the penetration after the above-mentioned reinforcing bars are constructed, it is possible to apply the reinforcing bar large-assembly construction method, and the plant construction period can be significantly shortened.

〔発明の概要〕[Summary of the invention]

本発明は、生体じゃへい体の配筋施工工期の短縮のため
、鉄筋大組工法適用の障害となる原子炉格納容器のペネ
トレーションを、生体じゃへい体配筋施工後とすること
により、上記障害を除くことにより発生する原子炉格納
容器の耐圧、漏洩テスト後のペネトレーションの原子炉
格納容器への取付け、ならびに、取付は場所の健全性の
確認を可能とする方式の提供に係わるものである。
In order to shorten the construction period for arranging living body reinforcement, the present invention eliminates the penetration of the reactor containment vessel, which is an obstacle to the application of the reinforcing bar large assembly method, after the construction of reinforcement for living body reinforcement. It is related to the pressure resistance of the reactor containment vessel generated by removing the leakage, the installation of the penetration into the reactor containment vessel after the leakage test, and the provision of a method that makes it possible to confirm the integrity of the location.

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

第1図は、本発明の実施例を示すもので、ペネトレーシ
ョン座7を原子炉格納容器の所定位置に予め取り付け、
仮設キャップ8を取り付けておく。
FIG. 1 shows an embodiment of the present invention, in which a penetration seat 7 is installed in a predetermined position in the reactor containment vessel,
Attach the temporary cap 8.

生体じゃへい体配筋施工後、ペネトレーションスリーブ
4、プロセス配管等5、プロセス配管保温材6を仮設キ
ャップ8を撤去後、挿入して、ペネトレーション座7と
9において溶接取付けることで、所定の原子炉格納容器
配管等貫通部構造を構成させる。
After constructing the biological body reinforcement, the penetration sleeve 4, process piping, etc. 5, and process piping heat insulating material 6 are inserted after removing the temporary cap 8, and welded and attached at the penetration seats 7 and 9 to secure the specified reactor. Configure the structure of the containment vessel piping and other penetrating parts.

第2図は、原子炉建屋構造の断面の一例を示すもので、
原子炉格納容器1に取り付けられた配管等貫通ペネトレ
ーション3と生体じゃへい体2との関係を示す。
Figure 2 shows an example of a cross section of the reactor building structure.
The relationship between the penetration 3 of piping etc. attached to the reactor containment vessel 1 and the biological barrier 2 is shown.

生体じゃへい体3は、格子状に設定された配筋を主要な
る構造体とした鉄筋コンクリートである。
The living body 3 is made of reinforced concrete whose main structure is reinforcement arranged in a grid pattern.

第3図は、従来一般に提供されている配管等貫通ペネト
レーションを示すもので、ペネトレ−ションスリーブ4
が、直接原子炉格納容器に取り付けられており、プロセ
ス配管等5.プロセス配管保温材6が取り付けられてい
る構造を示す6本構造にて、ペネトレーションスリーブ
を、原子炉格納容器の耐圧、漏洩テストおよび生体じゃ
へい体配筋施工後、取り付けた場合、原子炉格納容器と
の溶接点の健全性を確認するための、例えば、第6図に
示すようなテストチャンネル10の取り付け゛は、原子
炉格納容器自体の損傷の危険性が高く、又又線検査を行
う作業空間が確保できない。
Figure 3 shows the penetration through piping etc. that has been generally provided in the past, and shows the penetration sleeve 4.
is directly attached to the reactor containment vessel, and process piping, etc. 5. In the six-piece structure showing the structure in which the process piping insulation material 6 is attached, when the penetration sleeve is installed after the pressure resistance and leakage tests of the reactor containment vessel and the biological body reinforcement construction, the reactor containment vessel For example, installing a test channel 10 as shown in Figure 6 to confirm the integrity of the welding point with the reactor has a high risk of damage to the reactor containment vessel itself, and it is necessary to perform a line inspection. Unable to secure work space.

原子炉格納容器に取り付けられるペネトレーションの大
半を1本容器の耐圧漏洩試験前より、耐圧漏洩試験及び
生体じゃへい体配筋施工後とすることにより、生体じゃ
へい体配筋のブロック積み施工を可能とする方式の提案
である。
By making most of the penetrations installed in the reactor containment vessel after the pressure leakage test and the living body reinforcement construction, rather than before the single vessel pressure leakage test, it is possible to construct the living body body reinforcement in blocks. This is a proposed method.

上記のため、原子炉格納容器の耐圧漏洩試験時には、第
4図に示すよう、ペネトレーション座7に、仮設キャッ
プを取り付けた状態としておく。
For this reason, during the pressure leakage test of the reactor containment vessel, a temporary cap is attached to the penetration seat 7, as shown in FIG. 4.

第5図に示すよう、生体じゃへい体配筋、必要に応じて
コンクリート打設後、ペネトレーションスリーブ4.プ
ロセス配管5、プロセス配管の保温材6を、仮設キャッ
プ8を撤去した後、挿入する。
As shown in Fig. 5, after placing the biological reinforcement and placing concrete as necessary, the penetration sleeve 4. After removing the temporary cap 8, the process piping 5 and the heat insulating material 6 for the process piping are inserted.

次に、ペネトレーション座7とペネトレーションスリー
ブ4とを、9にて溶接にて固定する。
Next, the penetration seat 7 and the penetration sleeve 4 are fixed by welding at 9.

溶接点9の健全性確認のため、ペネトレーション座7は
、X線検査及び溶接部の漏洩試験を可能とする空間を確
保するため、最短数十ll11を必要とする。
In order to confirm the integrity of the welding point 9, the penetration seat 7 requires a minimum length of several tens of liters to ensure a space that allows for X-ray inspection and leakage testing of the welded portion.

第6図は、溶接点9の健全性確認のため、テストチャン
ネル10を取り付けた状態を示す。
FIG. 6 shows a state in which a test channel 10 is attached to confirm the soundness of the welding point 9.

上記ペネトレーション座4を、あらかじめ2M子炉格納
容器に取り付けておくことにより、ペネトレーションス
リーブを、生体じゃへい体配筋、必要に応じて、コンク
リート打設後、取り付けるとともに、取り付は溶接点の
健全性を確認できる。
By attaching the penetration seat 4 to the 2M sub-reactor containment vessel in advance, the penetration sleeve can be attached to the living body reinforcement, if necessary, after concrete is poured, and the attachment can be done to ensure a sound welding point. You can check the gender.

第7図は、第6図に示すテスト方式の変形例で、ペネト
レーション座4とテストチャンネル10の溶接を強固な
ものとし、かつ導管10をネジ込みとすることで、テス
トチャンネルを取り付けたものとできる方式を示す。
FIG. 7 shows a modification of the test method shown in FIG. 6, in which the penetration seat 4 and the test channel 10 are welded firmly and the conduit 10 is screwed in to attach the test channel. Here's how you can do it.

〔発明の効果〕〔Effect of the invention〕

原子炉プラント建設工程のクリティカルパスである生体
じゃへい体の配筋工程を短縮する一方策としての鉄筋群
のブロック積み施工の障害となっている原子炉格納容器
ペネトレーションの大半を、上記鉄筋群ブロック積み施
工後、PCvに取り付けることで、生体じゃへい体施工
工期を約25%短縮し、プラント建設工程を大幅に短縮
する。
Most of the penetration of the reactor containment vessel, which is an obstacle to the construction of blocks of reinforcing bars, as a way to shorten the reinforcement process of living body structures, which is a critical path in the reactor plant construction process, can be achieved by using the above-mentioned reinforcing bars blocks. By attaching it to the PCv after piling and construction, the biomechanical structure construction period will be shortened by approximately 25%, and the plant construction process will be significantly shortened.

【図面の簡単な説明】 第1図は本発明の一実施例になる構造断面図を示す。第
2図は原子炉建屋の縦断面図を示す。第3図は配管貫通
ペネトレーションの従来構造の断面図を示す、第4図は
原子炉格納容器の組立完了耐圧試験時の状況図を示す、
第5図は生体じゃへい体建設後の配管ペネトレーション
取付断面図を示す、第6図は本発明における溶接部の健
全性の確認のためのテスト方式を示す。第7図は第6図
に示す溶接部の健全性確認方式の変形例を示す。 1・・・原子炉格納容器(鋼板構造)、2・・・原子炉
格納容器を取囲む鉄筋コンクリートの生体しやへい体、
3・・・配管等貫通ペネトレーション、4・・・原子炉
格納容器に溶接固定されるペネトレーションスリーブ、
5・・・プロセス配管、6・・・プロセス配管の保温材
、7・・・ペネトレーション座、8・・・原子炉格納容
器の耐圧試験時に用いられる仮設の閉止キャップ、9・
・・7のペネトレーション座と4のペネトレーションス
リーブの溶接部、10・・・テストチャンネル、11・
・・導管、12・・・圧力計、13・・・耐圧バウンダ
リ部材、14.15・・・溶接部。
BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 shows a cross-sectional view of a structure according to an embodiment of the present invention. Figure 2 shows a longitudinal cross-sectional view of the reactor building. Figure 3 shows a cross-sectional view of a conventional structure for pipe penetration, Figure 4 shows a diagram of the situation during a pressure test after completing the assembly of the reactor containment vessel.
FIG. 5 shows a cross-sectional view of piping penetration installation after construction of the living body, and FIG. 6 shows a test method for confirming the soundness of the welded part in the present invention. FIG. 7 shows a modification of the welded part soundness confirmation method shown in FIG. 6. 1... Reactor containment vessel (steel plate structure), 2... Reinforced concrete living body surrounding the reactor containment vessel,
3... Penetration through piping, etc., 4... Penetration sleeve welded and fixed to the reactor containment vessel,
5... Process piping, 6... Heat insulating material for process piping, 7... Penetration seat, 8... Temporary closing cap used during pressure test of reactor containment vessel, 9...
・・Welded part of penetration seat 7 and penetration sleeve 4, 10・Test channel, 11・
... Conduit, 12 ... Pressure gauge, 13 ... Pressure-resistant boundary member, 14.15 ... Welded part.

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉格納容器の配管貫通ペネトレーションに於い
て、配管貫通部ペネトレーション取付座を設け、原子炉
しゃへい体の施工途中又は後配管貫通部を前記配管貫通
部ペネトレーション取付座内に挿入、溶接してなる原子
炉格納容器配管貫通部構造。
1. For pipe penetration of the reactor containment vessel, a pipe penetration mounting seat is provided, and the pipe penetration is inserted and welded into the pipe penetration mounting seat during or after construction of the reactor shield body. Reactor containment vessel piping penetration structure.
JP60030431A 1985-02-20 1985-02-20 Piping penetrating section structure of reactor container Pending JPS61192986A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60030431A JPS61192986A (en) 1985-02-20 1985-02-20 Piping penetrating section structure of reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60030431A JPS61192986A (en) 1985-02-20 1985-02-20 Piping penetrating section structure of reactor container

Publications (1)

Publication Number Publication Date
JPS61192986A true JPS61192986A (en) 1986-08-27

Family

ID=12303753

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60030431A Pending JPS61192986A (en) 1985-02-20 1985-02-20 Piping penetrating section structure of reactor container

Country Status (1)

Country Link
JP (1) JPS61192986A (en)

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