JPS6135394A - Housing structure of pressure-tube type reactor - Google Patents

Housing structure of pressure-tube type reactor

Info

Publication number
JPS6135394A
JPS6135394A JP15534384A JP15534384A JPS6135394A JP S6135394 A JPS6135394 A JP S6135394A JP 15534384 A JP15534384 A JP 15534384A JP 15534384 A JP15534384 A JP 15534384A JP S6135394 A JPS6135394 A JP S6135394A
Authority
JP
Japan
Prior art keywords
reactor
steam
building
cooling system
separator
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
JP15534384A
Other languages
Japanese (ja)
Inventor
相沢 賢司
好雄 吉田
雅彦 田辺
潔 石川
和美 穴沢
道下 秀紀
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 JP15534384A priority Critical patent/JPS6135394A/en
Publication of JPS6135394A publication Critical patent/JPS6135394A/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

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  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (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】 r発明の利用分野〕 本発明は、圧力管型原子炉の建屋構造に関するものであ
る。
DETAILED DESCRIPTION OF THE INVENTION Field of Application of the Invention The present invention relates to a building structure for a pressure tube nuclear reactor.

〔発明の背景〕[Background of the invention]

以下に、第1図ないし第5図により、圧力管型原子炉の
従来の原子炉建屋構造について説明する。
DESCRIPTION OF THE PREFERRED EMBODIMENTS The conventional reactor building structure of a pressure tube nuclear reactor will be explained below with reference to FIGS. 1 to 5.

原子炉建屋2は、円筒壁3、井桁壁4及び床6よυ構成
され、基礎マット15から立上がった構造を成している
。該原子炉建屋2内には、原子炉本体7、気水分離器8
等の原子炉冷却系、燃料交換装置(図示せず)等が収容
されている。該原子炉建屋2の周囲には、該原子炉建屋
2内の主要な設備を格納するための円筒形の鋼製の原子
炉格納容器1が該原子炉建屋2と同様に、該基礎マット
15から立上がった構造を成している。
The reactor building 2 is composed of a cylindrical wall 3, a parallel wall 4, and a floor 6, and has a structure rising from a foundation mat 15. Inside the reactor building 2, there is a reactor main body 7 and a steam separator 8.
The reactor cooling system, fuel exchange equipment (not shown), etc. are accommodated. Around the reactor building 2, a cylindrical steel reactor containment vessel 1 for storing the main equipment in the reactor building 2 is placed around the base mat 15, similar to the reactor building 2. It has a structure that stands up from

以下に、原子炉冷却系について説明する。原子炉冷却系
は、炉心を2分割した二つの互いに独立なループに分れ
ていて、燃料集合体(図示せず)を収容し、冷却材(軽
水)の通路となる原子炉本体7の内部に位置する圧力管
(図示せず)の半数ずつが各々のループに接続されてい
る。冷却材は、ポンプ(図示せず)でヘツタ責図示せず
)へ送られ、ここで個々の入口管(図示せず)を経て該
原子炉本体7内部の圧力管内を上昇しながら、燃料から
の熱を吸収して沸騰し、蒸気と水の混合した2相流で出
口管(図示せず)を通って気水分離器8に入る。気水分
離器8では、蒸気と飽和水に分離され、蒸気の湿気を取
シ除いたあと、主蒸気管(図示せず)を通って、該原子
炉格納容器1を貫通して、タービン(図示せず)へ送ら
れる。該気水分離器8の中では、分離された飽和水とタ
ービン系から戻ってきた給水が再び混合し、ポンプによ
りヘッダーへ戻る。
The reactor cooling system will be explained below. The reactor cooling system is divided into two mutually independent loops that divide the reactor core into two.The reactor cooling system is divided into two mutually independent loops. Half of the pressure pipes (not shown) located in each loop are connected to each loop. The coolant is pumped by a pump (not shown) to the reactor (not shown), where it is pumped up from the fuel as it ascends through pressure pipes inside the reactor body 7 through individual inlet pipes (not shown). It absorbs the heat of water, boils, and enters the steam-water separator 8 through an outlet pipe (not shown) as a two-phase flow of steam and water. In the steam separator 8, steam and saturated water are separated, and after removing moisture from the steam, the steam passes through a main steam pipe (not shown), penetrates the reactor containment vessel 1, and is then connected to a turbine ( (not shown). In the steam/water separator 8, the separated saturated water and the feed water returned from the turbine system are mixed again and returned to the header by a pump.

以下に、該気水分離器8の該原子炉建屋2内での設置位
置について説明する。燃料交換装置(図示せず)は、該
原子炉本体7下の所定圧力管(図示せず)の位置まで走
行し、圧力管と結合後、圧力管下部のシールプラグ(図
示せず)を取り外し、使用済燃料集合体を取り出す。次
いで新燃料集合体を挿入し燃料交換を終える。従って、
該原子炉本体7は、基礎マット15より該燃料交換装置
の高さ分だけ上方に位置する。また、該気水分離器8は
、上記原子炉冷却系の説明より、該冷却系の流体状態及
び出口管(図示せず)の配置より、該原子炉本体7よね
更に上方に位置し、該原子炉建屋2全体から見ると高さ
的に、該原子炉建屋2内上方に位置する。そして、該原
子炉建屋2は、建設コスト(主に掘削等)、該原子炉本
体7の据付性等から、該原子炉本体7の据付レベル付近
を地表面とし、そのため、該気水分離器8は地上の上方
階に位置する。
The installation position of the steam/water separator 8 in the reactor building 2 will be explained below. The fuel exchange device (not shown) travels to a predetermined pressure pipe (not shown) under the reactor main body 7, and after connecting with the pressure pipe, removes the seal plug (not shown) at the bottom of the pressure pipe. , take out the spent fuel assembly. Next, a new fuel assembly is inserted to complete the fuel exchange. Therefore,
The reactor body 7 is located above the base mat 15 by the height of the refueling device. Also, from the description of the reactor cooling system above, the steam separator 8 is located further above the reactor main body 7 due to the fluid state of the cooling system and the arrangement of the outlet pipe (not shown). When viewed from the reactor building 2 as a whole, it is located above the reactor building 2 in terms of height. The reactor building 2 is built at the ground level near the installation level of the reactor body 7 due to construction costs (mainly excavation, etc.) and ease of installation of the reactor body 7. 8 is located on the upper floor above the ground.

また、従来の原子炉建屋構造2における従来の気水分離
器8の据付方法を第1図により、以下に説明する。初め
に、円筒壁3の地上1階部分に設けられた仮開口16か
ら原子炉建屋2の1階床6の吊上げ位置まで、気水分離
器8(スキッド9とコロ17により水平移動が可能な状
態になっている)をコロ引きにより引込む。次に、1階
床6より気水分離器据付位置まで複数の滑車23を使い
ウィンチ10で吊上げ、気水分離器吊棒18を仮固定す
る。芯出しを行なうため、下げ振りを据付基準の1階床
6のペンチマークまで下して、所定の位置に調整する。
Further, a method of installing a conventional steam-water separator 8 in a conventional reactor building structure 2 will be explained below with reference to FIG. First, a steam separator 8 (which can be horizontally moved by skids 9 and rollers 17 ) is pulled in by pulling the rollers. Next, the steam separator is lifted from the first floor floor 6 to the installation position of the steam separator using the winch 10 using a plurality of pulleys 23, and the steam separator hanging rod 18 is temporarily fixed. To perform centering, lower the plumb bob to the pliers mark on the first floor 6, which is the installation standard, and adjust it to a predetermined position.

据付高さについても基準点より確認する。芯出し終了後
、気水分離器吊棒18の止め金具を溶接して本固定する
。最上階支持梁19及び気水分離器支持梁20に、気水
分離器拘束用形鋼21を取り付け、該気水分離器拘束用
形鋼21と気水分離器8とを気水分離器振止金物22に
より固定し、該気水分離器8を拘束する。
Also check the installation height from the reference point. After centering is completed, the stopper of the steam-water separator hanging rod 18 is welded and permanently fixed. A steam separator restraint section steel 21 is attached to the top floor support beam 19 and steam water separator support beam 20, and the steam water separator restraint section steel 21 and the steam separator 8 are connected to the steam separator shaker. It is fixed with a stopper 22 to restrain the steam/water separator 8.

以上の方法により気水分離器8を据付ける。The steam separator 8 is installed by the above method.

上記の原子炉建屋2構造及び気水分離器8据付方法によ
れば、気水分離器8搬入通路となる地上上方階床6を後
打ちする必要があるため、該地上上方階の気水分離器8
室内には直方壁5が設置できない。そのため従来例では
同階の他の井桁壁4あるいは円筒壁3等の耐振壁となる
壁の厚さを増すことにより原子炉建屋2の耐震性に対拠
している。一方、我国の厳しい耐振条件下においては、
十分な耐振性を持たすために、十分な耐振壁壁厚が必要
となり、地上上方階の耐振壁の壁厚増加の要求が場合に
よっては、建屋上方の重量増加となり、そのため、原子
炉建屋全体の壁厚増加につながり、建屋の大きさが全体
的に増加し、建設コスト、工程等に大きな影響をおよほ
し、ひいてはプラント全体の経済性という観点からは好
ましからざる場合も有り得る。
According to the above-mentioned reactor building 2 structure and steam separator 8 installation method, it is necessary to post-construct the upper floor 6 above the ground, which serves as the passageway for transporting the steam separator 8. Vessel 8
A rectangular wall 5 cannot be installed indoors. For this reason, in the conventional example, the earthquake resistance of the reactor building 2 is improved by increasing the thickness of walls that serve as vibration-resistant walls, such as other cross-shaped walls 4 or cylindrical walls 3 on the same floor. On the other hand, under Japan's severe vibration resistance conditions,
In order to have sufficient vibration resistance, sufficient vibration resistance wall thickness is required, and in some cases, the requirement for an increase in the wall thickness of vibration resistance walls on floors above ground level may result in an increase in the weight of the upper part of the building. This will lead to an increase in wall thickness and the overall size of the building, which will have a significant impact on construction costs, processes, etc., and may even be unfavorable from the economical standpoint of the entire plant.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、原子炉建屋内の上部に設置される大物
機器である気水分離器の搬入据付方法を改良することに
より、直方壁をより多く設は耐震・]上を可能にした原
子炉建屋構造を提供する二ある。
The purpose of the present invention is to improve the method of transporting and installing the steam separator, which is a large piece of equipment installed in the upper part of the reactor building. There are two types of furnace building structures.

〔発明の概要〕[Summary of the invention]

本発明は、圧力管型原子炉建屋の検討において発明され
たものである。現在計画を進めている圧力管型原子炉建
屋は、円筒胴部の上に半球の碗部を有する鋼製格納容器
及びその内部に収納される内部コンクリートより構成さ
れている。該原子炉建屋には、第1図に示すように数千
トンを越える炉本体及び大型機器である再循環系機器が
内部コンクリート上に配置されている。これらの機器に
ついては、最重要機器であることから、機器重量及び地
震を考慮した建屋設計がなされ建屋基準を満足している
が原子炉冷却系機器(%に気水分離器)搬入上の制約か
ら、建屋直方壁(原子炉中心方向に)を取付できず、該
機器軸方向強度に比べ軸直角方向の強度が劣る傾向にあ
った。上記問題点を解決するためには、以下の方法が考
えられる。
The present invention was invented in consideration of a pressure tube type nuclear reactor building. The pressure tube reactor building currently being planned consists of a steel containment vessel with a hemispherical bowl on top of a cylindrical body, and a concrete interior housed inside the containment vessel. As shown in FIG. 1, the reactor building has a reactor body weighing over several thousand tons and recirculation system equipment, which is a large piece of equipment, arranged on internal concrete. As these equipment are the most important equipment, the building design takes into account the weight of the equipment and earthquake resistance, and the building standards are satisfied. Therefore, the rectangular wall of the building (towards the center of the reactor) could not be installed, and the strength in the direction perpendicular to the axis tended to be inferior to the strength in the axial direction of the equipment. In order to solve the above problems, the following methods can be considered.

(1)原子炉冷却系機器の構造を変更する。(1) Change the structure of reactor cooling system equipment.

(2)現状原子炉冷却系機器構造にて建屋の強度を向上
させる。
(2) Improve the strength of the building based on the current reactor cooling system equipment structure.

上記対策のうち、(1)の対策については、圧力管型原
子炉であることから、原子炉冷却系機器を小さくシ、据
付することは可能であるが、それに伴い該基数が増え建
設コスト及び据付後のメンテナンス等を考慮した場合、
得策とは言えない。特に、原子力発電プラントの大型化
に伴い、可能な限り■S■対象箇所を減らす傾向にあり
、その上からも、本図のような原子炉冷却系機器を大型
一体化した構造を採らざるを得ない。
Among the above measures, regarding measure (1), since it is a pressure tube reactor, it is possible to install the reactor cooling system equipment in a smaller size, but this will increase the number of reactor units and increase construction costs. When considering maintenance etc. after installation,
I can't say it's a good idea. In particular, as nuclear power plants become larger, there is a trend to reduce the number of parts subject to ■S■ as much as possible, and from this perspective, it is necessary to adopt a structure that integrates large reactor cooling system equipment as shown in this figure. I don't get it.

従って上記対策のうち(2)の対策を採る必要がある。Therefore, it is necessary to take measure (2) of the above measures.

建屋の耐震強度を増すためには、原子炉中心方向に直方
壁を入れる必要があね、本方法として原子炉冷却系機器
設定後、後打ちする方法と原子炉冷却系機器設定前に打
設する方法とがある。前記方法については、原子炉冷却
系機器設定後となり、このため建設工程が長くなりコス
ト面から見た場合有利でない。また、搬入時据付用強度
部材として使用できないディメリットがある。後記方法
については、建屋に干渉することなく原子炉冷、却系機
器(特に大物機器である気水分離器)の搬入方法を考慮
する必要がある。本発明は、上記対策として、気水分離
器を原子炉格納容器頂部より入れることにより、原子炉
中心方向の直方壁を後打ち構造とすることなく設置可能
にしたものであり、圧力管型原子炉建屋の耐震性向上対
策として有効である。
In order to increase the seismic strength of the building, it is necessary to install a rectangular wall toward the center of the reactor. Two methods are available: one is to install a rectangular wall after the reactor cooling system equipment is installed, and the other is to install it before the reactor cooling system equipment is installed. There is a way to do this. The method described above requires the installation of the reactor cooling system equipment, which lengthens the construction process and is not advantageous from a cost perspective. Another disadvantage is that it cannot be used as a strength member for installation during delivery. Regarding the method described later, it is necessary to consider how to bring in the reactor cooling system equipment (particularly the large equipment, the steam-water separator) without interfering with the building. As a countermeasure to the above, the present invention makes it possible to install a steam-water separator from the top of the reactor containment vessel without requiring a post-installation structure on the rectangular wall facing the center of the reactor. This is an effective measure to improve the earthquake resistance of furnace buildings.

本発明は、原子炉本体及び原子炉冷却系機器を支持する
井桁壁及び円筒壁からなる原子炉建屋において、該建屋
原子炉中心方向に直方壁を気水分離器設置階及び該以下
の階に設けたことにより、建屋の耐震性向上を図る圧力
管型原子炉建屋構造である。
The present invention provides a reactor building consisting of parallel walls and cylindrical walls that support the reactor body and reactor cooling system equipment, in which rectangular walls are installed in the direction of the reactor center of the building on the floor where the steam separator is installed and on the floors below. This is a pressure tube type reactor building structure that improves the earthquake resistance of the building.

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

以下に、第7図ないし第15図により、本発明の一実施
例について説明する。原子炉建屋2は、円筒壁3、井桁
壁4及び床6より構成され、基礎マット15から立上が
った構造を成している。該原子炉建屋2内には、原子炉
本体7、気水分離器8等の原子炉冷却系機器、配管燃料
交換装置(図示せず)等が収容されている。該原子炉建
屋2の周囲には、該原子炉建屋2内の主要な設備を格納
するための円筒形の鋼製の原子炉格納容器1が該原子炉
建屋2と同様に、該基礎マット15から立上がった構造
を成している。
An embodiment of the present invention will be described below with reference to FIGS. 7 to 15. The reactor building 2 is composed of a cylindrical wall 3, a parallel wall 4, and a floor 6, and has a structure rising from a foundation mat 15. The reactor building 2 houses a reactor main body 7, reactor cooling system equipment such as a steam separator 8, a piping fuel exchange device (not shown), and the like. Around the reactor building 2, a cylindrical steel reactor containment vessel 1 for storing the main equipment in the reactor building 2 is placed around the base mat 15, similar to the reactor building 2. It has a structure that stands up from

以下に、原子炉冷却系につらて説明する。原子炉冷却系
は、炉心を2分割した二つの互いに独立なループに分れ
ていて、燃料集合体(図示せず)を収容し、冷却材(軽
水)の通路となる原子炉本体7の内部−に位置する圧力
管(図示せず)の半数゛ずつが各々のループに接続され
ている。冷却材は、各々のループについて、ポンプ(図
示せず)でヘッダ(図示せず)へ送られ、ここで個々の
入口管(図示せず)を経て該原子炉本体7内部の圧力管
内を上昇しながら、燃料からの熱を吸収して沸騰し、蒸
気と水の混合した2相流で出口管(図示せず)を通って
気水分離器8に入る。気水分離器8では、蒸気と飽和水
に分離され、蒸気の湿分を取怜除いたあと、主蒸気管(
図示せず)を通って、該原子炉格納容器1を貫通して、
タービン(図示せず)へ送られる。該気水分離器8の中
では、分離された飽和水とタービン系から戻ってきた給
水が再び混合し、ポンプによりヘッダーへ戻る。
The reactor cooling system will be explained below. The reactor cooling system is divided into two mutually independent loops that divide the reactor core into two.The reactor cooling system is divided into two mutually independent loops. Half of the pressure pipes (not shown) located at - are connected to each loop. For each loop, the coolant is pumped (not shown) to a header (not shown) where it rises in pressure pipes inside the reactor body 7 via individual inlet pipes (not shown). At the same time, it absorbs heat from the fuel, boils, and enters the steam-water separator 8 through an outlet pipe (not shown) as a two-phase stream of steam and water mixture. In the steam separator 8, steam and saturated water are separated, and after removing moisture from the steam, the main steam pipe (
) through the reactor containment vessel 1,
to a turbine (not shown). In the steam/water separator 8, the separated saturated water and the feed water returned from the turbine system are mixed again and returned to the header by a pump.

以下に、該気水分離器8の該原子炉建屋2内での設置位
置について説明する。燃料交換装置(図示せず)は、該
原子炉本体7下の所定圧力管(図示せず)の位置まで走
行し、圧力管と結合後、圧力管下部のシールプラグ(図
示せず)を取シ外し、使用済燃料集合体を取り出す。次
いで新燃料集合体を挿入し燃料交換を終える。従って、
該原子炉本体7は、基礎マット15より該燃料交換装置
の高さ分だけ上方に位置する。また、該気水分離器8は
、上記原子炉冷却系の説明に示したように、該冷却系の
流体状態及び出口管(図示せず)の配置より、該原子炉
本体7より更に上方に位置し、該原子炉建屋2全体から
見ると高さ的に、該原子炉建屋2内最上方に位置する。
The installation position of the steam/water separator 8 in the reactor building 2 will be explained below. The fuel exchange device (not shown) travels to a predetermined pressure pipe (not shown) under the reactor main body 7, and after connecting with the pressure pipe, removes the seal plug (not shown) at the bottom of the pressure pipe. Remove the spent fuel assembly. Next, a new fuel assembly is inserted to complete the fuel exchange. Therefore,
The reactor body 7 is located above the base mat 15 by the height of the refueling device. Furthermore, as shown in the description of the reactor cooling system above, the steam separator 8 is located further above the reactor main body 7 due to the fluid state of the cooling system and the arrangement of the outlet pipe (not shown). When viewed from the entire reactor building 2, it is located at the uppermost position in the reactor building 2 in terms of height.

また、該原子炉建屋2は、建設コスト(主に掘削等)、
該原子炉本体7の据付性等から、該原子炉本体7の据付
レベル付近を地表面とし、そのため、該気水分離器8け
地上の上方階に位置する。第13図ないし第15図に示
すように、該気水分離器8の設置される階には、該原子
炉本体7の中心に向けて、直方壁5が設置されている。
In addition, the reactor building 2 has construction costs (mainly excavation etc.),
For ease of installation of the reactor main body 7, the vicinity of the installation level of the reactor main body 7 is set at the ground surface, and therefore the steam/water separator 8 is located on an upper floor above the ground. As shown in FIGS. 13 to 15, a rectangular wall 5 is installed toward the center of the reactor body 7 on the floor where the steam separator 8 is installed.

該直方壁5の設置により、本発明によれば、該直方壁5
の長手方向(第14図及び第15図中の矢印方向)の該
原子炉建屋2の耐震性が向上するという効果がある。
By installing the rectangular wall 5, according to the present invention, the rectangular wall 5
This has the effect of improving the earthquake resistance of the reactor building 2 in the longitudinal direction (arrow direction in FIGS. 14 and 15).

以下に、第7図〜第15図により、本発明における該気
水分離器8の据付手順について説明する。
Below, the installation procedure of the steam-water separator 8 according to the present invention will be explained with reference to FIGS. 7 to 15.

まず、第7図に示すように、原子炉格納容器1をまた、
該原子炉建屋2を該気水分離器8の据付階まで立上げた
状態とする。次に、第8図に示すように、該原子炉格納
容器1のドーム部に仮開口16を設け、該気水分離器8
を吊治具13を介してクレーン24等により、該仮開口
16から該原子炉格納容器1内に吊り降ろす。
First, as shown in FIG. 7, the reactor containment vessel 1 is also
The reactor building 2 is raised to the installation floor of the steam separator 8. Next, as shown in FIG. 8, a temporary opening 16 is provided in the dome portion of the reactor containment vessel 1, and the steam separator 8
is lowered into the reactor containment vessel 1 from the temporary opening 16 via the lifting jig 13 by a crane 24 or the like.

その後、該気水分離器8の下部トラニオン11をスキッ
ド9上に下ろし、(この状態では、該気水分離器8は垂
直)、第9図に示すように、該スキッド9をウィンチ等
(図示せず)でコロ(図示せず)引きしながら、該気水
分離器8を除々に下降させ、水平になるまで吊降ろす。
Thereafter, lower the lower trunnion 11 of the steam/water separator 8 onto the skid 9 (in this state, the steam/water separator 8 is vertical), and as shown in FIG. The steam/water separator 8 is gradually lowered while being pulled by a roller (not shown) until it becomes horizontal.

そして、該気水分離器8の上部側(吊位置側)を仮置台
25の上に載せ、該スキッド9を固定し、その後、該吊
治具13を取り外す。(第10図) その後、第11図に示すように、仮設サポート14を設
置し、該気水分離器8を水平に吊上げ、所定位置にきた
ときUボルト26で該仮設サポート14に据付ける。そ
の後、第12図に示すように、該気水分離器8の設置階
における、円筒壁3及び該直方壁5を立上げる。その後
、第13ないし第15図に示すように、該仮設サポート
14を撤去し、床6を設置し、該気水分離器8を該Uボ
ルト26を介して該床6に設置する。
Then, the upper side (hanging position side) of the steam/water separator 8 is placed on the temporary stand 25, the skid 9 is fixed, and then the hanging jig 13 is removed. (FIG. 10) Thereafter, as shown in FIG. 11, a temporary support 14 is installed, and the steam/water separator 8 is hoisted horizontally, and when it reaches a predetermined position, it is installed on the temporary support 14 with U-bolts 26. Thereafter, as shown in FIG. 12, the cylindrical wall 3 and the rectangular wall 5 are erected on the floor where the steam separator 8 is installed. Thereafter, as shown in FIGS. 13 to 15, the temporary support 14 is removed, the floor 6 is installed, and the steam separator 8 is installed on the floor 6 via the U bolts 26.

第16ないし第20図に、本発明の他の実施例を示す。Other embodiments of the present invention are shown in FIGS. 16 to 20.

本実施例によれば、該気水分離器8の設置階ばかりでな
く、その他の各階においても、同様に、直方壁5を設置
することにより、該直方壁5の長手方向の該原子炉建屋
2の耐震性が更に向上するという効果がある。
According to this embodiment, by installing the rectangular wall 5 not only on the floor where the steam separator 8 is installed but also on each other floor, the reactor building in the longitudinal direction of the rectangular wall 5 can be This has the effect of further improving the earthquake resistance of item 2.

〔発明の効果〕〔Effect of the invention〕

本発明によれば直方壁をより多く設置出来るととにより
原子炉建屋構造の耐震性を向上させることが出来る。ま
た、原子炉冷却系機器が配置される間を直方壁にて仕切
ることにより、高温高圧で使用される原子炉冷却系配管
が万一破断した場合に生じる配管のむち打ち現象による
他機器の損傷拡大の防止及び原子炉冷却系ポンプの万一
の損壊による破片の飛散による他機器の損傷拡大の防止
を図ることができる。さらに、井桁壁及び直方壁を後打
ちをすることなく建屋躯体の建ち上げが可能であり、後
打ちコンクリート施工の工程短縮を図ることができる、
などの効果がある。
According to the present invention, it is possible to install more rectangular walls, thereby improving the earthquake resistance of the reactor building structure. In addition, by partitioning the space where reactor cooling system equipment is placed with a rectangular wall, damage to other equipment will be increased due to the whiplash phenomenon that would occur if the reactor cooling system piping used at high temperature and high pressure were to break. It is possible to prevent damage to other equipment from spreading due to the scattering of fragments in the unlikely event that the reactor cooling system pump is damaged. Furthermore, the building frame can be erected without post-casting the parallel walls and rectangular walls, and the post-cast concrete construction process can be shortened.
There are effects such as

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

第1図は従来の原子炉建屋構造の縦断面図、第2図、第
3図、第4図、第5図はそれぞれ第1図のA−A、B−
BXC−C,D−D矢視断面図、第6図は第1図の気水
分離器の据付は状態を示す断面図、第7図ないし第13
図はそれぞれ本発明の圧力管型原子炉の建屋構造の実施
例の建屋躯体の建方手1−及び気水分離器の搬入据付は
手順を示す説明図、第14.15図はそれぞれ第13図
のE−E、F−F矢視断面図、第16図は本発明の圧力
管゛型原子炉の建屋構造の他の実施例の原子炉建屋の縦
断面図、第17図、第18図、第19図、第20図はそ
れぞれ第16図のG−GXH−H。 I−I、J−Jの矢視断面図である。 1・・・原子炉格納容器、2・・・原子炉建屋、3・・
・円筒壁、4・・・井桁壁、5・・・直方壁、6・・・
床、7・・・原子第1図 χ15 も4図 躬2図 も3図 摺四図 も10図 ″X15 光11図 へ15 ′\。 宿13図 〜15 も140 高15図 躬16図 〜15 東口図 千18図 +2−  年 ′+5 5 洋傘 ζ
Figure 1 is a vertical cross-sectional view of a conventional reactor building structure, and Figures 2, 3, 4, and 5 are A-A, B--A-B in Figure 1, respectively.
BXC-C, DD arrow sectional view, Figure 6 is a sectional view showing the installation state of the steam separator in Figure 1, Figures 7 to 13
14 and 15 are explanatory diagrams showing the procedure for constructing the building frame 1- and the delivery and installation of the steam-water separator in an embodiment of the building structure of a pressure tube nuclear reactor according to the present invention, respectively. 16 is a longitudinal sectional view of a reactor building of another embodiment of the building structure of a pressure tube type nuclear reactor according to the present invention, and FIGS. 19 and 20 are G-GXH-H in FIG. 16, respectively. It is an arrow sectional view taken along I-I and J-J. 1... Reactor containment vessel, 2... Reactor building, 3...
・Cylindrical wall, 4... parallel wall, 5... rectangular wall, 6...
Floor, 7...Atom 1st diagram χ15 also 4th diagram 2nd and 3rd diagram 4th diagram 10" 15 East exit map 18th map +2- year'+5 5 Western umbrella ζ

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉本体及び原子炉冷却系機器を支持する井桁壁
及び円筒壁からなる原子炉建屋において、該建屋原子炉
中心方向に直方壁を設けたことを特徴とする圧力管型原
子炉の建屋構造。
1. A pressure tube reactor building characterized by having a rectangular wall in the direction of the reactor center in a reactor building consisting of parallel walls and cylindrical walls that support the reactor body and reactor cooling system equipment. structure.
JP15534384A 1984-07-27 1984-07-27 Housing structure of pressure-tube type reactor Pending JPS6135394A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP15534384A JPS6135394A (en) 1984-07-27 1984-07-27 Housing structure of pressure-tube type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP15534384A JPS6135394A (en) 1984-07-27 1984-07-27 Housing structure of pressure-tube type reactor

Publications (1)

Publication Number Publication Date
JPS6135394A true JPS6135394A (en) 1986-02-19

Family

ID=15603814

Family Applications (1)

Application Number Title Priority Date Filing Date
JP15534384A Pending JPS6135394A (en) 1984-07-27 1984-07-27 Housing structure of pressure-tube type reactor

Country Status (1)

Country Link
JP (1) JPS6135394A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2004249327A (en) * 2003-02-20 2004-09-09 Toshiba Corp Welding equipment

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2004249327A (en) * 2003-02-20 2004-09-09 Toshiba Corp Welding equipment

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