JPS6333115B2 - - Google Patents

Info

Publication number
JPS6333115B2
JPS6333115B2 JP55024506A JP2450680A JPS6333115B2 JP S6333115 B2 JPS6333115 B2 JP S6333115B2 JP 55024506 A JP55024506 A JP 55024506A JP 2450680 A JP2450680 A JP 2450680A JP S6333115 B2 JPS6333115 B2 JP S6333115B2
Authority
JP
Japan
Prior art keywords
dry well
wall
piping
drywell
containment vessel
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
JP55024506A
Other languages
Japanese (ja)
Other versions
JPS56120982A (en
Inventor
Koji Kitagawa
Juichi Hashimoto
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
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP2450680A priority Critical patent/JPS56120982A/en
Publication of JPS56120982A publication Critical patent/JPS56120982A/en
Publication of JPS6333115B2 publication Critical patent/JPS6333115B2/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)

Description

【発明の詳細な説明】 本発明は原子炉格納容器に係り、特に内部空間
を拡大するのに好適な原子炉格納容器に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor containment vessel, and more particularly to a reactor containment vessel suitable for expanding internal space.

従来の原子炉格納容器は、ドライウエル壁の下
端周面にベント管が水平に貫通しており、このベ
ント管は、例えば700Aのものが120本程度設けら
れている。このため、全断面に占めるベント管に
よる断面欠損が大きく、地震、圧力、熱等の荷重
に耐えるように設計することが容易でない。
In a conventional nuclear reactor containment vessel, vent pipes horizontally penetrate the lower peripheral surface of the dry well wall, and about 120 vent pipes of, for example, 700 A are provided. For this reason, the cross-sectional loss due to the bent pipe in the entire cross-section is large, and it is not easy to design it to withstand loads such as earthquakes, pressure, and heat.

また、ドライウエル内の蒸気をベント管に連絡
させるため、従来はドライウエル壁の内側にウエ
アウオールを設けているが、このウエアウオール
が他部スペースの狭隘化の原因となつている。
Further, in order to communicate the steam in the dry well to the vent pipe, a wear wall has conventionally been provided inside the dry well wall, but this wear wall causes the space in other parts to become narrow.

本発明はかかる従来の難点を解決するためにな
されたもので、その目的とするところは、内部ス
ペースの拡大を図ることができる原子炉格納容器
を提供するにある。
The present invention has been made to solve these conventional problems, and its purpose is to provide a nuclear reactor containment vessel whose internal space can be expanded.

本発明は、従来の難点がドライウエル内の蒸気
をベント管に導びく手段としてドライウエル壁の
内側に配されたウエアウオールを用いていたこと
に起因する点に着目し、ウエアウオールに代えて
一端がドライウエル内に開口しかつ他端がベント
管に連通する配管を用いるようにしたものであ
る。
The present invention focuses on the fact that the conventional difficulty lies in the use of a wear wall placed inside the dry well wall as a means for guiding the steam in the dry well to the vent pipe, and the present invention has been developed by using a wear wall instead of a wear wall. This uses piping that opens into the dry well at one end and communicates with the vent pipe at the other end.

以下本発明を第1図に示す実施例に基づいて説
明する。
The present invention will be explained below based on the embodiment shown in FIG.

図において3は、ドライウエル壁1およびドラ
イウエル床5等により囲まれたドライウエルであ
り、ドライウエル壁1の内側には、上端部がドラ
イウエル床5を貫通してドライウエル3内に開口
し、かつ下端部がドライウエル壁1下部を水平に
貫通する複数のベント管2を介してサブレツシヨ
ンプール6に連通する配管7が略垂直方向に配設
されている。そしてこの配管7は、第1図に示す
ようにその外周部に打設されるとともにドライウ
エル壁1の一部を構成する補強コンクリート8に
よりドライウエル壁1と一体構造となつている。
In the figure, 3 is a dry well surrounded by a dry well wall 1, a dry well floor 5, etc., and inside the dry well wall 1, the upper end penetrates the dry well floor 5 and is opened into the dry well 3. In addition, piping 7 is arranged in a substantially vertical direction and communicates with the subression pool 6 via a plurality of vent pipes 2 whose lower ends horizontally penetrate the lower part of the dry well wall 1. As shown in FIG. 1, this piping 7 is integrally constructed with the dry well wall 1 by means of reinforcing concrete 8, which is cast on its outer periphery and constitutes a part of the dry well wall 1.

以上の構成において、ドライウエル3内の原子
炉一次系配管の破断事故時に放出される蒸気は、
配管7およびベント管2を介してサブレツシヨン
プール6に導びかれ、ここで凝縮冷却されてドラ
イウエル3内の圧力上昇が抑制される。
In the above configuration, the steam released in the event of a rupture accident of the reactor primary system piping in the dry well 3 is
It is led to the sub-reduction pool 6 via the piping 7 and the vent pipe 2, where it is condensed and cooled, thereby suppressing the pressure rise in the dry well 3.

以上説明したように本実施例によれば、配管は
ドライウエル壁内側のベント管に対応する部位の
みに設けられるので、ドライウエル壁内側周囲に
設けられていた従来のウエアウオールに比較して
内部空間の拡大を図ることができる。また、配管
は補強コンクリートによりドライウエル壁と一体
構造となつているので、断面が増加してベント管
による断面欠損が減少し、地震、圧力、熱等の荷
重に対して補強的な役割を果して構造強度が増大
する。また配管は外部へ露出しないので、外部か
らの圧力に対する強度を高めることができる。
As explained above, according to this embodiment, the piping is provided only in the area corresponding to the vent pipe inside the dry well wall, so compared to the conventional wear wall installed around the inside of the dry well wall, the piping is installed inside the dry well wall. It is possible to expand the space. In addition, since the piping is integrated with the drywell wall using reinforced concrete, the cross section increases, reducing cross section loss due to bent pipes, and plays a reinforcing role against loads such as earthquakes, pressure, heat, etc. Structural strength increases. Moreover, since the piping is not exposed to the outside, the strength against external pressure can be increased.

第2図は本発明の他の実施例を示すもので、以
下これについて説明する。
FIG. 2 shows another embodiment of the invention, which will be described below.

図において3は、ドライウエル壁1およびドラ
イウエル床5等により囲まれたドライウエルであ
り、ドライウエル壁1の内部には、上端部がドラ
イウエル3と連通する配管17が埋込まれて一体
構造となつている。そしてこの配管17の下端部
は、一端が配管17に連結されかつ他端がサブレ
ツシヨンプール6内に開口する水平な複数本のベ
ント管12を介してサブレツシヨンプール6に連
通している。
In the figure, 3 is a dry well surrounded by a dry well wall 1, a dry well floor 5, etc., and inside the dry well wall 1, a pipe 17 whose upper end communicates with the dry well 3 is embedded and integrated. It has a structure. The lower end of this piping 17 communicates with the sub-reduction pool 6 via a plurality of horizontal vent pipes 12, one end of which is connected to the piping 17 and the other end of which opens into the sub-reduction pool 6. .

以上の構成において、ドライウエル3内の原子
炉一次系配管の破断事故時に放出される蒸気は、
配管17およびベント管2を介してサブレツシヨ
ンプール6に導びかれ、ここで凝縮冷却されてド
ライウエル3内の圧力上昇が抑制される。なお、
ドライウエル3をドライウエル壁1およびドライ
ウエル床5等より囲んで構成した例を示したが、
ドライウエル床5の高さは任意に定めることがで
きる。例えばドライウエル床5の高さをサブレツ
シヨンプール6の床面と略同じ高さとすることも
できる。
In the above configuration, the steam released in the event of a rupture accident of the reactor primary system piping in the dry well 3 is
It is led to the sub-reduction pool 6 via the piping 17 and the vent pipe 2, where it is condensed and cooled, thereby suppressing the pressure rise in the dry well 3. In addition,
Although an example has been shown in which the dry well 3 is surrounded by the dry well wall 1 and the dry well floor 5, etc.,
The height of the dry well floor 5 can be determined arbitrarily. For example, the height of the dry well floor 5 can be made approximately the same as the floor surface of the sub-recession pool 6.

以上説明したように本実施例によれば、ドライ
ウエル壁の内側に突出する部分が全くないので、
内部スペースを大幅に拡大することができる。
As explained above, according to this embodiment, since there is no part protruding inside the dry well wall,
The interior space can be significantly expanded.

以上本発明を好適な実施例に基づいて説明した
が、本発明によれば、内部スペースの拡大を図る
ことができる。
The present invention has been described above based on preferred embodiments, but according to the present invention, it is possible to expand the internal space.

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

第1図は本発明に係る原子炉格納容器の第1実
施例を示す要部の縦断面図、第2図は本考案の他
の実施例を示す要部の縦断面図である。 1…ドライウエル壁、2,12…ベント管、3
…ドライウエル、6…サブレツシヨンプール、
7,17…配管。
FIG. 1 is a vertical cross-sectional view of a main part showing a first embodiment of a nuclear reactor containment vessel according to the present invention, and FIG. 2 is a vertical cross-sectional view of a main part showing another embodiment of the present invention. 1... Drywell wall, 2, 12... Vent pipe, 3
...dry well, 6...subrection pool,
7,17...Piping.

Claims (1)

【特許請求の範囲】[Claims] 1 ドライウエル内の原子炉一次系配管の破断事
故時に放出される蒸気をサプレツシヨンプールに
導くためにドライウエル壁下端に水平ベントを設
けた原子炉格納容器において、一端がドライウエ
ル内に開口しかつ他端が前記水平ベントに連通す
る配管を設け、この配管をドライウエル壁内部に
略垂直方向に埋込んだことを特徴とする原子炉格
納容器。
1 In a reactor containment vessel with a horizontal vent provided at the lower end of the drywell wall to guide steam released in the event of a rupture accident of the reactor primary system piping inside the drywell to the suppression pool, one end opens into the drywell. A nuclear reactor containment vessel characterized in that a pipe is provided whose other end communicates with the horizontal vent, and the pipe is embedded substantially vertically inside a dry well wall.
JP2450680A 1980-02-28 1980-02-28 Nuclear reactor container Granted JPS56120982A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2450680A JPS56120982A (en) 1980-02-28 1980-02-28 Nuclear reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2450680A JPS56120982A (en) 1980-02-28 1980-02-28 Nuclear reactor container

Publications (2)

Publication Number Publication Date
JPS56120982A JPS56120982A (en) 1981-09-22
JPS6333115B2 true JPS6333115B2 (en) 1988-07-04

Family

ID=12140061

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2450680A Granted JPS56120982A (en) 1980-02-28 1980-02-28 Nuclear reactor container

Country Status (1)

Country Link
JP (1) JPS56120982A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6193987A (en) * 1984-10-15 1986-05-12 石川島播磨重工業株式会社 Pedestal for pressure vessel of nuclear reactor
JPS6270793A (en) * 1985-09-25 1987-04-01 株式会社東芝 Method of installing bent tube and installation structure thereof

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS502992A (en) * 1973-05-09 1975-01-13

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS502992A (en) * 1973-05-09 1975-01-13

Also Published As

Publication number Publication date
JPS56120982A (en) 1981-09-22

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