JPS6269198A - Method of construction of reactor container - Google Patents

Method of construction of reactor container

Info

Publication number
JPS6269198A
JPS6269198A JP60208854A JP20885485A JPS6269198A JP S6269198 A JPS6269198 A JP S6269198A JP 60208854 A JP60208854 A JP 60208854A JP 20885485 A JP20885485 A JP 20885485A JP S6269198 A JPS6269198 A JP S6269198A
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor
wall
reactor pressure
heat
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
JP60208854A
Other languages
Japanese (ja)
Inventor
成瀬 佳宏
船橋 俊博
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 JP60208854A priority Critical patent/JPS6269198A/en
Publication of JPS6269198A publication Critical patent/JPS6269198A/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

  • Feeding, Discharge, Calcimining, Fusing, And Gas-Generation Devices (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】 〔発明の技術分野〕 本発明は、原子炉格納容器の建設工法に関する。[Detailed description of the invention] [Technical field of invention] The present invention relates to a construction method for a nuclear reactor containment vessel.

〔発明の技術的背景〕[Technical background of the invention]

以下、従来の原子炉格納容器の建設工法を第3図及び$
4図を参照して説明する。ここで第3図に原子炉格納容
器の縦断面図を示す。第3図において、原子炉格納容器
1内には空間ボリュームを調整する為の底部コンクリー
ト2が充填され、この底部コンクリート2を支持するた
め下部コンクリート3が原子炉格納容器1に密着充填さ
れている。この底部コンクリート2には圧力容器ペデス
タル(以下単にペデスタルと呼ぶ)4が立設され、この
ペデスタル4の上部には原子炉圧力容器6から放出され
る放射線を遮蔽する原子炉熱遮蔽壁(以下単に熱遮蔽壁
と呼ぶ)5を形成している1、前記ペデスタル4は内部
に炉心(図示せず)を収容した原子炉圧力容器6を支持
している。また、前記原子炉格納容器1の周囲にはサプ
レッションチェンバ7が設置され、このサブレッション
チェンパ羊功魂1資さ本〒ミーH嫂た姓ムーーン4遥、
φ−7内にはプール水8が収容されている。前記サプレ
ッションチェンバ7と前記原子炉圧力容器1はベント管
9にて接続され、このベント管9のサブレツションテエ
ンパ7側には、ベントヘッダ10を介してダウンカマ1
1が設けられ、このダウンカマ11の先端部は前記プー
ル水8中に開放されている。
Below, the conventional construction method of the reactor containment vessel is shown in Figure 3 and $
This will be explained with reference to FIG. Here, FIG. 3 shows a longitudinal sectional view of the reactor containment vessel. In Figure 3, a bottom concrete 2 is filled in the reactor containment vessel 1 to adjust the spatial volume, and a lower concrete 3 is tightly packed into the reactor containment vessel 1 to support the bottom concrete 2. . A pressure vessel pedestal (hereinafter simply referred to as the pedestal) 4 is erected on the bottom concrete 2, and a reactor heat shielding wall (hereinafter simply referred to as the The pedestal 4 forming a heat shield wall 5 supports a reactor pressure vessel 6 containing a reactor core (not shown) therein. Further, a suppression chamber 7 is installed around the reactor containment vessel 1, and this suppression chamber 7 is installed around the reactor containment vessel 1.
Pool water 8 is accommodated in φ-7. The suppression chamber 7 and the reactor pressure vessel 1 are connected by a vent pipe 9, and a downcomer 1 is connected to the suppression chamber 7 side of the vent pipe 9 via a vent header 10.
1 is provided, and the tip of this downcomer 11 is open into the pool water 8.

以上に示した1皇子炉格納容器の従来の建設工法を第4
図(a)〜(a)を3照して説明する。なお、第3図と
同一部分には同一符号を付しその偶成の説明は省略する
。第4図において、従来の建設工法は、まず第4図(a
)に示すよ5にペデスタル4を底部コンクリート2上に
構築した後に、熱遮蔽t5の下部を据付ける。その後、
第4図(b)に示すよプに熱−A蔽啼5の上部を据付け
て、この熱遮蔽壁5は完成する。なお、熱遮蔽壁5は原
子炉圧力容器6の搬入を充分安全に行なえるよう原子炉
圧力容器6との間隔を充分に余裕を見込んで設置される
。そして、熱遮蔽」簑5が完成した後、第4図(c)に
示すよ5に原子炉圧力容器6を熱3a蔽壁5内に収容し
、ペデスタル4に固定する。そして、原子炉圧力容器6
を据付だ後に第4図(d)に示すように原子炉圧力容器
6に形成されたノズル12と配管13との溶接工事が開
始され、その後頭次、その先の配管工事が始まるとい5
建設工法を行なっている。
The conventional construction method for the 1st Oji reactor containment vessel shown above is the 4th construction method.
This will be explained with reference to Figures (a) to (a). Note that the same parts as in FIG. 3 are given the same reference numerals, and a description of their combination will be omitted. In Figure 4, the conventional construction method is shown in Figure 4 (a).
) As shown in 5, after the pedestal 4 is constructed on the bottom concrete 2, the lower part of the heat shield t5 is installed. after that,
The heat shield wall 5 is completed by installing the upper part of the heat-A shield 5 as shown in FIG. 4(b). The heat shielding wall 5 is installed with a sufficient distance from the reactor pressure vessel 6 so that the reactor pressure vessel 6 can be carried in safely. After the heat shield wall 5 is completed, the reactor pressure vessel 6 is housed within the heat shield wall 5 and fixed to the pedestal 4 as shown in FIG. 4(c). And reactor pressure vessel 6
After the installation, as shown in Figure 4(d), welding work between the nozzle 12 formed in the reactor pressure vessel 6 and the piping 13 begins, and then the piping work beyond that begins.
We are engaged in construction methods.

〔背景技術の問題点〕[Problems with background technology]

前述したように、従来の建設工法においては熱遮蔽壁の
完成後に原子炉圧力容器の搬入を行な5手順となってい
る為、原子炉圧力容器搬入時の安全性を考慮して圧力容
器と熱遮蔽壁との間隔を充分確保する必要があった。そ
の為、熱遮蔽壁の径が大ぎくなり、それにともなって原
子炉格納容器全体も大きくなり、ひいては原子炉建屋全
体の大きさにまで影響を及ぼしていた。
As mentioned above, in the conventional construction method, the reactor pressure vessel is carried in after the completion of the heat shield wall, which is a five-step process. It was necessary to ensure sufficient distance from the heat shield wall. As a result, the diameter of the heat shield wall became larger, and the reactor containment vessel as a whole also became larger, which in turn affected the overall size of the reactor building.

また、従来の工事手順では熱i!i蔽壁及び圧力容器設
置完了後に圧力容器に形成されたノズルと配管の溶接工
事を開始し、その後順次その先の配管工事を行なってい
た為、圧力容器の搬入時期がクリティカルとなっていた
In addition, conventional construction procedures require heat i! After the installation of the i-wall and pressure vessel was completed, welding work for the nozzle and piping formed on the pressure vessel began, and subsequent piping work was then carried out in sequence, making the timing of the delivery of the pressure vessel critical.

〔発明の目的〕[Purpose of the invention]

本発明は、原子炉圧力容器の搬入を早期に行ない、かつ
配管工事を従来より先行して工期短縮を計り、さらには
熱遮蔽壁の径を縮小することのでさる原子炉格納容器の
建設工法を得ることを目的とする。
The present invention provides a construction method for a reactor containment vessel, which involves carrying in the reactor pressure vessel early, carrying out piping work earlier than before to shorten the construction period, and further reducing the diameter of the heat shield wall. The purpose is to obtain.

〔発明の概要〕[Summary of the invention]

本発明は、底部コンクリート上に立設され上部に原子炉
熱遮蔽壁を形成した圧力容器ペデスタルにより原子炉圧
力容器を支持せしめ、この原子炉圧力容器を格納する原
子炉格納容器を建設する原子炉格納容器ヒ)建設工法に
おいて、前記底部コンクリートを完成させた後、この底
部コンクリート上に圧力容器ペデスタルを構築し、この
構築後に前記熱遮蔽壁の下部を形成させ、この熱遮蔽壁
の下部を形成後に熱遮蔽壁の上部を分割して仮置きして
前記原子炉圧力容器を熱遮蔽壁内に搬入し、この原子炉
圧力容器を熱遮蔽壁の中に搬入後に原子炉圧力容器に形
成されたノズルと配管との溶接工事を実施し、この溶接
工事を実施後に仮置きした前記熱遮蔽壁の上部を下部と
接続して成ることを特徴とする[祭子炉格納容器の建設
工法にある。。
The present invention relates to a nuclear reactor in which a reactor pressure vessel is supported by a pressure vessel pedestal that is erected on a concrete bottom and has a reactor heat shielding wall formed on the upper part, and a reactor containment vessel is constructed to store the reactor pressure vessel. Containment vessel h) In the construction method, after the bottom concrete is completed, a pressure vessel pedestal is constructed on this bottom concrete, and after this construction, the lower part of the heat shielding wall is formed, and the lower part of this heat shielding wall is formed. Later, the upper part of the heat shield wall is divided and temporarily placed, and the reactor pressure vessel is carried into the heat shield wall, and after this reactor pressure vessel is carried into the heat shield wall, the reactor pressure vessel is formed. The method is characterized in that the nozzle and the piping are welded together, and after the welding work is performed, the upper part of the temporarily placed heat shielding wall is connected to the lower part. .

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

以下、本発明の一実施例を第1図及び第2図を参照して
説明する。また、第1図及び第2図において、第3図及
び第4図と同一部分には同一符号を付し、その部分の構
成の説明は省略する。ここで第1図(a)から(d)に
本発明の一実施+Miの工法を示す概略縦断面図を示し
、第2図に第1図(b)の入−人矢視断面図を示す。第
1図において、本発明の建設工法は、まず第1図(1)
に示すよ5に、ペデスタル4を底部コンクリート3上に
構築した後に、熱遮蔽壁5の下部5aを据付ける、そし
て、この下部5aの先端部に仮置用架台I4を取付ける
。その後、第1図(b)及び第2図に示すように、熱遮
蔽壁5の上部5bを分割した形で搬入し、熱SU壁5の
下部5aの上方に花弁状に仮置きする。なお、熱遮蔽壁
5は鋼板で作られており、中にコンクリートを打設して
最終的に完成する訳であるが、ここではまだ上部の熱遮
蔽壁5bにはコンクリートの打設は行なわれない、、ま
たこの熱遮蔽壁5の上部5bを仮置きした後に原子炉圧
力容器6はペデスタル4上に設置される。そして、原子
炉圧力容器6の設置後に第1図(C)に示すよ5に、r
a子炉圧力容器6のノズル12と配管13の溶接工事を
行な5゜その後、$1図(d)に小すよ5に反訳きして
あったfAR蔽壁上壁上部5b行移動して据付け、同時
に配管工事を開始する。以上の画成より熱遮蔽壁の上部
5bは、まだコンクリートが打設されていない為、移動
させることは困難ではなく、周12月に花弁状に、F)
つた燕遮7表壁5の上部5bを平行移動して各熱1蔽壁
5の上部5hを接続させることができる。またこの時す
でにノズル12と配管13との溶接工事は先行している
為、その先の配管の工事を実施することが可能となる。
An embodiment of the present invention will be described below with reference to FIGS. 1 and 2. Further, in FIGS. 1 and 2, the same parts as in FIGS. 3 and 4 are given the same reference numerals, and explanations of the configurations of these parts will be omitted. Here, FIGS. 1(a) to (d) show schematic longitudinal cross-sectional views showing one implementation of the present invention + Mi construction method, and FIG. . In Fig. 1, the construction method of the present invention is first shown in Fig. 1 (1).
As shown in Figure 5, after the pedestal 4 is constructed on the bottom concrete 3, the lower part 5a of the heat shielding wall 5 is installed, and the temporary mounting frame I4 is attached to the tip of this lower part 5a. Thereafter, as shown in FIGS. 1(b) and 2, the upper part 5b of the heat shielding wall 5 is carried in a divided form and temporarily placed above the lower part 5a of the heat SU wall 5 in the shape of a flower petal. Note that the heat shield wall 5 is made of a steel plate and is finally completed by pouring concrete inside, but concrete has not yet been poured on the upper heat shield wall 5b. No, the reactor pressure vessel 6 is installed on the pedestal 4 after the upper part 5b of the heat shielding wall 5 is temporarily placed. After the reactor pressure vessel 6 is installed, r
After welding the nozzle 12 and piping 13 of the a child reactor pressure vessel 6, we moved the upper part of the upper wall of the fAR shield wall to the line 5b, which was marked as 5 in Figure 1 (d). installation and piping work will begin at the same time. From the above definition, it is not difficult to move the upper part 5b of the heat shielding wall because the concrete has not yet been placed, and it will be shaped like a petal in December.F)
By moving the upper part 5b of the front wall 5 of the ivy swallow shield 7 in parallel, the upper parts 5h of the respective heat shielding walls 5 can be connected. Furthermore, since the welding work between the nozzle 12 and the pipe 13 has already been carried out at this time, it becomes possible to carry out the work on the pipe after that.

従って従来は熱遮蔽壁5の建設工事と配管工事とは別々
のシーケンスで同時には行な5ことができなかったもの
を本発明における工法では、それらを同時期に並行して
行なうことかでさることになり、工程の短縮をはかるこ
とが可能となる〇 更に圧力容器は熱遮蔽壁が完成する前に搬入し、搬入後
に分割して仮置きしてあった熱遮蔽壁を移動させること
になる為、原子炉圧力容器と熱遮蔽壁との間隔は従来寸
法より小さくて済み熱遮蔽壁の径は縮小することができ
る。
Therefore, in the construction method of the present invention, the construction work of the heat shield wall 5 and the piping work were performed in separate sequences and could not be done at the same time, but with the construction method of the present invention, they can be done in parallel at the same time. This makes it possible to shorten the process. Furthermore, the pressure vessel will be brought in before the heat shielding wall is completed, and the heat shielding wall that was temporarily placed in parts after being brought in will be moved. Therefore, the distance between the reactor pressure vessel and the heat shield wall can be smaller than the conventional size, and the diameter of the heat shield wall can be reduced.

〔発明の効果〕〔Effect of the invention〕

以上、説明したように、本発明によるha子炉格納容器
の建設工法では、熱遮蔽壁の上部を花弁状に仮置きして
おき、原子炉圧力容器を搬入した後原子炉圧力容器に形
成されたノズルと配管との浴接工事を先行する為、その
後の熱a融壁設置工事及び配管工事を同時に実施するこ
とが可能となり、工期の短縮をはかることができる。
As explained above, in the construction method of the HA reactor containment vessel according to the present invention, the upper part of the heat shielding wall is temporarily placed in the shape of a flower petal, and after the reactor pressure vessel is brought in, it is formed in the reactor pressure vessel. Since the bath contact work between the nozzle and the piping is carried out in advance, it is possible to carry out the subsequent thermal a-melting wall installation work and piping work at the same time, thereby shortening the construction period.

さらには、熱遮蔽壁を横に移動して据けけることになる
為、熱遮蔽壁と唄子炉圧力容器の間隔は削減することが
でき、熱!趨薮慴の径を縮小することが可能となる。従
って原子炉格納容器及び原子炉建屋の縮小化を計かるこ
とができるようになるので大幅な物量の削減が可能とな
り、合理化を計ることができる。
Furthermore, since the heat shielding wall can be moved laterally and installed, the distance between the heat shielding wall and the Utako reactor pressure vessel can be reduced, reducing the heat! It becomes possible to reduce the diameter of the bush. Therefore, it becomes possible to reduce the size of the reactor containment vessel and the reactor building, thereby making it possible to significantly reduce the amount of materials and to achieve rationalization.

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

第1図(a)〜(d)は各々本発明の原子炉格納容器の
建設工法を示す原子炉格納容器の要部の概略縦断面図、
第2図は第1図(b)の入−人矢視断面図、第3図は原
子炉格納容器の概略縦断面図、第4図(、)−(a)は
各々従来の原子炉格納容器の建設工法を示す原子炉格納
容器の要部の概略縦断面図である、1・・・原子炉格納
容器 2・・・底部コンクリート3・・・下部コンクリ
ート 4・・・圧力容器ペデスタル5・・・原子炉熱遮
蔽壁 6・・・原子炉圧力容器12・・・ノズル   
  I3・・・配管14・・・仮置用架台 代理人 弁理士  則 近 庖 信 置  三俣弘文 (Q、)                     
   (/l)第1図 第3図 (α)(b) 第4図
FIGS. 1(a) to 1(d) are schematic vertical cross-sectional views of the main parts of the reactor containment vessel, respectively showing the construction method of the reactor containment vessel of the present invention;
Figure 2 is a cross-sectional view taken from the entry point in Figure 1 (b), Figure 3 is a schematic vertical cross-sectional view of the reactor containment vessel, and Figures 4 (,) - (a) are each a conventional reactor containment vessel. 1. Reactor containment vessel 2. Bottom concrete 3. Lower concrete 4. Pressure vessel pedestal 5. ...Reactor heat shield wall 6...Reactor pressure vessel 12...Nozzle
I3...Piping 14...Temporary mount agent Patent attorney Nori Chika Isao Nobuyuki Mitsumata Hirofumi (Q,)
(/l) Figure 1 Figure 3 (α) (b) Figure 4

Claims (1)

【特許請求の範囲】[Claims] 底部コンクリート上に立設され上部に原子炉熱遮蔽壁を
形成した圧力容器ペデスタルにより原子炉圧力容器を支
持せしめ、この原子炉圧力容器を格納する原子炉格納容
器を建設する原子炉格納容器の建設工法において、前記
底部コンクリートを完成させた後、この底部コンクリー
ト上に圧力容器ペデスタルを構築し、この構築後に前記
熱遮蔽壁の下部を形成させ、この熱遮蔽壁の下部を形成
後に熱遮蔽壁の上部を分割して仮置きして前記原子炉圧
力容器を熱遮蔽壁内に搬入し、この原子炉圧力容器を熱
遮蔽壁の中に搬入後に原子炉圧力容器に形成されたノズ
ルと配管との溶接工事を実施し、この溶接工事を実施後
に仮置きした前記熱遮蔽壁の上部を下部と接続して成る
ことを特徴とする原子炉格納容器の建設工法。
Construction of a reactor containment vessel in which a reactor pressure vessel is supported by a pressure vessel pedestal that is erected on a concrete bottom and has a reactor heat shielding wall formed on the top, and a reactor containment vessel is constructed to house this reactor pressure vessel. In the construction method, after the bottom concrete is completed, a pressure vessel pedestal is constructed on the bottom concrete, the lower part of the heat shield wall is formed after this construction, and the lower part of the heat shield wall is formed after the lower part of the heat shield wall is formed. The reactor pressure vessel is carried into the heat shielding wall with the upper part divided and temporarily placed, and after the reactor pressure vessel is carried into the heat shielding wall, the nozzle and piping formed in the reactor pressure vessel are connected. A method for constructing a nuclear reactor containment vessel, comprising performing welding work, and connecting the upper part of the temporarily placed heat shielding wall to the lower part after the welding work is performed.
JP60208854A 1985-09-24 1985-09-24 Method of construction of reactor container Pending JPS6269198A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60208854A JPS6269198A (en) 1985-09-24 1985-09-24 Method of construction of reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60208854A JPS6269198A (en) 1985-09-24 1985-09-24 Method of construction of reactor container

Publications (1)

Publication Number Publication Date
JPS6269198A true JPS6269198A (en) 1987-03-30

Family

ID=16563212

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60208854A Pending JPS6269198A (en) 1985-09-24 1985-09-24 Method of construction of reactor container

Country Status (1)

Country Link
JP (1) JPS6269198A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH04135400U (en) * 1991-06-07 1992-12-16 宏明 安田 Trial painting board for color toning work in painting
JP2009210497A (en) * 2008-03-06 2009-09-17 Akira Tanabe Low-pressure loss steam separator of boiling water reactor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH04135400U (en) * 1991-06-07 1992-12-16 宏明 安田 Trial painting board for color toning work in painting
JP2009210497A (en) * 2008-03-06 2009-09-17 Akira Tanabe Low-pressure loss steam separator of boiling water reactor

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