JPS6410795B2 - - Google Patents

Info

Publication number
JPS6410795B2
JPS6410795B2 JP57022652A JP2265282A JPS6410795B2 JP S6410795 B2 JPS6410795 B2 JP S6410795B2 JP 57022652 A JP57022652 A JP 57022652A JP 2265282 A JP2265282 A JP 2265282A JP S6410795 B2 JPS6410795 B2 JP S6410795B2
Authority
JP
Japan
Prior art keywords
containment vessel
reactor
dry well
installing
installation
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
Application number
JP57022652A
Other languages
Japanese (ja)
Other versions
JPS58140687A (en
Inventor
Masanori Suzuki
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 JP57022652A priority Critical patent/JPS58140687A/en
Publication of JPS58140687A publication Critical patent/JPS58140687A/en
Publication of JPS6410795B2 publication Critical patent/JPS6410795B2/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)

Description

【発明の詳細な説明】 本発明は原子炉格納容器の据付工法に係り、原
子炉格納容器と原子炉格納容器内構造物とを並行
して据付を行う原子炉格納容器の据付手順に関す
る。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for installing a reactor containment vessel, and more particularly, to a procedure for installing a reactor containment vessel in which a reactor containment vessel and internal structures of the reactor containment vessel are installed in parallel.

従来、原子炉格納容器および格納容器内構造物
は、別々に据付を行つていた。即ち、格納容器内
構造物は、原子炉格納容器据付完了後、原子炉格
納容器の上部より吊込、搬入されていたため、前
記構造物製品の大形化が計れない。また格納容器
内配管の据付作業が原子炉本体基礎、原子炉遮蔽
壁の据付完了後に行うために、原子炉格納容器耐
圧試験後、直ちに開始する事が出来ず格納容器耐
圧試験完了後の建設期間が長いと言う欠点があつ
た。
Conventionally, the reactor containment vessel and the internal structures of the containment vessel were installed separately. That is, since the internal structures of the containment vessel were suspended and carried in from the upper part of the reactor containment vessel after the installation of the reactor containment vessel was completed, it was impossible to increase the size of the structural products. In addition, since the installation of piping inside the containment vessel is carried out after the installation of the reactor body foundation and reactor shielding wall is completed, it is not possible to start immediately after the reactor containment vessel pressure test, and the construction period after the containment vessel pressure test is completed. It had the disadvantage of being long.

本発明の目的は、原子炉格納容器と格納容器内
構造物である原子炉本体基礎および原子炉遮蔽壁
の据付を同時に行い、原子力発電所の建設期間を
短縮する原子炉格納容器の据付工法を提供するこ
とにある。
An object of the present invention is to provide a method for installing a reactor containment vessel that simultaneously installs the reactor containment vessel and the reactor body foundation and reactor shielding wall, which are internal structures of the containment vessel, thereby shortening the construction period of a nuclear power plant. It is about providing.

本発明の原子炉格納容器の据付工法は、原子炉
格納容器のドライウエルと、前記原子炉格納容器
のドライウエル内に格納される格納容器内構造物
である原子炉本体基礎とその原子炉本体基礎上の
原子炉遮蔽壁とを据付る方法において、前記格納
容器内構造物と前記原子炉格納容器のドライウエ
ルとの据付を段々に並行して行い、その各段段ご
との並行据付作業は前記格納容器内構造物を先行
させて据え付けし、後行して据え付けされた前記
原子炉格納容器のドライウエルを先行して据付た
前記格納容器内構造物の据付済み段部分に取付け
た据付用サポートで所定の位置に仮固定し、溶接
を行いながら、前記原子炉格納容器のドライウエ
ルと前記格納容器内構造物とを並行して組み上げ
ていくものであり、この工法によれば、前記格納
容器内構造物と前記原子炉格納容器のドライウエ
ルとの据付を段々に並行して行い原子炉格納容器
のドライウエルを組立たときにはすでに格納容器
内構造物は格納状態に有つて、原子炉本体基礎や
原子炉遮蔽壁の据付後に行うべき格納容器内配管
の据付作業が出来る状態に有るから、原子炉格納
容器の耐圧試験完了後、直ちに配管据付作業を可
能にしたことを特徴とする。
The installation method of a reactor containment vessel of the present invention includes a dry well of a reactor containment vessel, a reactor body foundation that is a structure inside the containment vessel stored in the dry well of the reactor containment vessel, and the reactor body. In the method of installing a reactor shielding wall on a foundation, the internal structure of the containment vessel and the dry well of the reactor containment vessel are installed in parallel step by step, and the parallel installation work for each step is performed as described above. An installation support that is attached to the installed stage part of the containment vessel internal structure, in which the containment vessel internal structure is installed first, and the dry well of the reactor containment vessel is installed subsequently. The dry well of the reactor containment vessel and the internal structures of the containment vessel are assembled in parallel while being temporarily fixed in a predetermined position and welded. According to this method, the containment vessel The internal structures and the dry well of the reactor containment vessel are installed step by step in parallel, and by the time the dry well of the reactor containment vessel is assembled, the internal structures of the containment vessel are already in the stored state, and the reactor main body foundation is The present invention is characterized in that the piping installation work can be carried out immediately after the pressure test of the reactor containment vessel is completed, since the installation work of the piping inside the containment vessel, which should be carried out after the installation of the reactor shielding wall, can be carried out.

以下、本発明の一実施例を説明する。第1図に
おいて原子炉格納容器はドライウエル1、サプレ
ツシヨンチエンバ2、および前記ドライウエル1
とサプレツシヨンチエンバ2を連結しているベン
ト管3より構成されている。原子炉圧力容器4は
ドライウエル1内にあり原子炉本体基礎5上に基
礎ボルト(図示せず)によつて支持される。前記
原子炉本体基礎5はドライウエル1の下部内面お
よび外面に夫々溶接されていて、マツトコンクリ
ート6に埋込まれている基礎ボルト(図示せず)
に支持されている。原子炉遮蔽壁7は前記した原
子炉圧力容器4の廻りに配置されている。
An embodiment of the present invention will be described below. In FIG. 1, the reactor containment vessel includes a dry well 1, a suppression chamber 2, and the dry well 1.
and a vent pipe 3 connecting the suppression chamber 2 and the suppression chamber 2. The reactor pressure vessel 4 is located within the dry well 1 and supported on the reactor body foundation 5 by foundation bolts (not shown). The reactor body foundation 5 is welded to the inner and outer surfaces of the lower part of the dry well 1, respectively, and includes foundation bolts (not shown) embedded in the pine concrete 6.
is supported by The reactor shielding wall 7 is arranged around the reactor pressure vessel 4 described above.

前述した原子炉格納容器の据付手順を図に従つ
て説明する。第2図において原子炉本体基礎5、
およびスカート8の基礎ボルト(図示せず)が埋
込まれているマツトコンクリート6上にドライウ
エル1段1aと原子炉本体基礎5aを工場又は現
地において一体にしたものを設定する。次に第3
図に示す様にスカート8をマツトコンクリート6
上に設定し、ドライウエル2段1bおよび原子炉
本体基礎5bを設定する。次に第4図に示す様に
ドライウエル3段1cを吊込み、据付用サポート
9を原子炉本体基礎5bおよびドライウエル3段
1cに取付けられた据付用金具10に複数個にて
固定し、ドライウエル3段1cを設定する。前記
した据付用サポート9はターンバツクル11が取
付けられドライウエル3段1cの寸法調整を可能
にしてあり、ドライウエル2段1bとドライウエ
ル3段1cの合せ部は、第7図に示す様に、ドラ
イウエル2段1bの外面に設定用ピース12を取
付けておき、ドライウエル1cを容易に据付け出
来る様にしている。次に第5図に示す様に原子炉
本体基礎5cを吊込み設定し、ドライウエル4段
1dを吊込み設定する。設定方法は前記したドラ
イウエル3段1cと同様、ターンバツクル10に
より行う。ドライウエル4段1dにはベント管用
貫通部13が設けられている。次に第6図に示す
様に原子炉遮蔽壁7の全高の約1/2の原子炉遮蔽
壁7aを原子炉本体基礎5c上に吊込設定し、ド
ライウエル5段1eを吊込み、据付用サポート1
0を原子炉遮蔽壁下部7aとドライウエル5段1
eに取付けられた据付用金具10に複数個で固定
し設定する。ドライウエル4段1dとドライウエ
ル5段1eの合せ部は、第8図に示す様にドライ
ウエル4段の内外面に複数個のガイドピース14
が溶接によつて取付けられていて、ドライウエル
5段1eが容易に設定出来る様にしてある。次に
第1図に示す様に、ドライウエル6段1f、ドラ
イウエル7段1g、ドライウエル下部フランジ1
hを据付ける。前記したドライウエル1の据付手
順で組立を行うが溶接作業は据付、設定した後、
直ちに溶接作業を行い、更に、サプレツシヨンチ
エンバ2、およびベント管3は、ドライウエル1
の据付途中に行い、ドライウエル内コンクリート
16,17、および原子炉本体基礎5内のコンク
リート15の打設は、ドライウエル下部フランジ
1hが完了、若しくは原子炉格納容器の耐圧試験
完了前に行うものとするが、工程によつては格納
容器の耐圧試験完了後でも良い。前記した据付作
業が完了した時点でドライウエル上部フランジ1
iを取付して原子炉格納容器の耐圧試験を実施し
据付作業が完了する。
The procedure for installing the reactor containment vessel described above will be explained with reference to the drawings. In Figure 2, the reactor body foundation 5,
The first stage of the dry well 1a and the reactor body foundation 5a are integrated in a factory or on site on the mat concrete 6 in which the foundation bolts (not shown) of the skirt 8 are embedded. Then the third
As shown in the figure, attach the skirt 8 to the matte concrete 6.
the second dry well stage 1b and the reactor main body foundation 5b. Next, as shown in FIG. 4, the third stage dry well 1c is suspended, and a plurality of installation supports 9 are fixed to the installation fittings 10 attached to the reactor body foundation 5b and the third stage dry well 1c. Set up 3 dry wells 1c. The above-mentioned installation support 9 has a turnbuckle 11 attached thereto to enable the dimension adjustment of the third dry well stage 1c, and the joint portion of the second dry well stage 1b and the third dry well stage 1c is as shown in FIG. A setting piece 12 is attached to the outer surface of the second dry well 1b so that the dry well 1c can be easily installed. Next, as shown in FIG. 5, the reactor main body foundation 5c is suspended, and the four dry well stages 1d are suspended. The setting method is performed using the turnbuckle 10, as in the case of the three-stage dry well 1c described above. A vent pipe penetration portion 13 is provided in the four-stage dry well 1d. Next, as shown in Fig. 6, the reactor shielding wall 7a, which is approximately 1/2 of the total height of the reactor shielding wall 7, is suspended above the reactor main body foundation 5c, and the 5th stage dry well 1e is suspended and installed. Support 1
0 to the lower part of the reactor shielding wall 7a and the dry well 5th stage 1
A plurality of pieces are fixed and set to the installation fittings 10 attached to e. As shown in FIG. 8, the joint portion of the fourth dry well stage 1d and the fifth dry well stage 1e has a plurality of guide pieces 14 on the inner and outer surfaces of the four dry well stages.
are attached by welding, so that the five-stage dry well 1e can be easily set. Next, as shown in Figure 1, dry well 6 stages 1f, dry well 7 stages 1g, dry well lower flange 1
Install h. Assembly is performed according to the installation procedure of dry well 1 described above, but welding work is performed after installation and setting.
Welding work will be carried out immediately, and the suppression chamber 2 and vent pipe 3 will be attached to the dry well 1.
The concrete 16, 17 in the dry well and the concrete 15 in the reactor body foundation 5 are placed during the installation of the dry well, and the concrete 15 in the reactor body foundation 5 is performed before the dry well lower flange 1h is completed or the pressure test of the reactor containment vessel is completed. However, depending on the process, it may be possible to do this after the pressure test of the containment vessel is completed. Once the above installation work is completed, install the drywell upper flange 1.
i was installed, a pressure test was conducted on the reactor containment vessel, and the installation work was completed.

本発明によれば、原子炉格納容器と原子炉本体
基礎および原子炉遮蔽壁が同時に並行して行われ
るため、原子力発電所の建設期間の短縮に効果が
あると共に、建設期間短縮により建設費が安価と
なり経済性に優れている。
According to the present invention, since the reactor containment vessel, the reactor body foundation, and the reactor shielding wall are constructed simultaneously and in parallel, it is effective in shortening the construction period of a nuclear power plant, and the construction cost is also reduced by shortening the construction period. It is inexpensive and has excellent economic efficiency.

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

第1図は原子炉格納容器、原子炉本体基礎およ
び原子炉遮蔽壁の縦断面図、第2〜6図は本発明
の実施例を示す据付手順説明図、第7図は第5図
のA部詳細図、第8図は第6図のB部詳細図であ
る。 1……ドライウエル、5……原子炉本体基礎、
7……原子炉遮蔽壁、9……据付用サポート。
Figure 1 is a vertical sectional view of the reactor containment vessel, reactor body foundation, and reactor shielding wall, Figures 2 to 6 are installation procedure explanatory diagrams showing embodiments of the present invention, and Figure 7 is A of Figure 5. 8 is a detailed view of section B in FIG. 6. 1...Dry well, 5...Reactor main body foundation,
7... Reactor shielding wall, 9... Installation support.

Claims (1)

【特許請求の範囲】[Claims] 1 原子炉格納容器のドライウエルと、前記原子
炉格納容器のドライウエル内に格納される格納容
器内構造物である原子炉本体基礎とその原子炉本
体基礎の原子炉遮蔽壁とを据付る方法において、
前記格納容器内構造物と前記原子炉格納容器のド
ライウエルとの据付を段々に並行して行い、その
各段々ごとの並行据付作業は前記格納容器内構造
物を先行させて据え付けし、後行して据え付けさ
れた前記原子炉格納容器のドライウエルを先行し
て据付た前記格納容器内構造物の据付済み段部分
に取付けた据付用サポートで所定の位置に仮固定
し、溶接を行いながら、前記原子炉格納容器のド
ライウエルと前記格納容器内構造物とを並行して
組み上げていくことを特徴とした原子炉格納容器
の据付工法。
1. A method of installing a dry well of a reactor containment vessel, a reactor body foundation that is a containment vessel internal structure stored in the dry well of the reactor containment vessel, and a reactor shielding wall of the reactor body foundation. In,
The internal structures of the containment vessel and the dry well of the reactor containment vessel are installed in parallel in stages, and the parallel installation work for each stage is performed by installing the internal structures of the containment vessel first, and then installing the internal structures of the containment vessel later. Temporarily fixing the dry well of the reactor containment vessel installed in a predetermined position with an installation support attached to the installed step part of the structure inside the containment vessel previously installed, and while performing welding, A method for installing a reactor containment vessel, characterized in that a dry well of the reactor containment vessel and internal structures of the containment vessel are assembled in parallel.
JP57022652A 1982-02-17 1982-02-17 Method of installing reactor container Granted JPS58140687A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57022652A JPS58140687A (en) 1982-02-17 1982-02-17 Method of installing reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57022652A JPS58140687A (en) 1982-02-17 1982-02-17 Method of installing reactor container

Publications (2)

Publication Number Publication Date
JPS58140687A JPS58140687A (en) 1983-08-20
JPS6410795B2 true JPS6410795B2 (en) 1989-02-22

Family

ID=12088772

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57022652A Granted JPS58140687A (en) 1982-02-17 1982-02-17 Method of installing reactor container

Country Status (1)

Country Link
JP (1) JPS58140687A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60128391A (en) * 1983-12-16 1985-07-09 株式会社東芝 Method of installing container for nuclear reactor

Also Published As

Publication number Publication date
JPS58140687A (en) 1983-08-20

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