JP2530865Y2 - Pedestal structure of reactor pressure vessel - Google Patents

Pedestal structure of reactor pressure vessel

Info

Publication number
JP2530865Y2
JP2530865Y2 JP1990040620U JP4062090U JP2530865Y2 JP 2530865 Y2 JP2530865 Y2 JP 2530865Y2 JP 1990040620 U JP1990040620 U JP 1990040620U JP 4062090 U JP4062090 U JP 4062090U JP 2530865 Y2 JP2530865 Y2 JP 2530865Y2
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor pressure
dry well
pedestal
divided
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 - Lifetime
Application number
JP1990040620U
Other languages
Japanese (ja)
Other versions
JPH041493U (en
Inventor
敦美 岡本
Original Assignee
石川島播磨重工業株式会社
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 石川島播磨重工業株式会社 filed Critical 石川島播磨重工業株式会社
Priority to JP1990040620U priority Critical patent/JP2530865Y2/en
Publication of JPH041493U publication Critical patent/JPH041493U/ja
Application granted granted Critical
Publication of JP2530865Y2 publication Critical patent/JP2530865Y2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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)
  • Pressure Vessels And Lids Thereof (AREA)

Description

【考案の詳細な説明】 [産業上の利用分野] 本考案は、原子炉格納容器内の原子炉圧力容器を支持
するためのペデスタル構造に関するものである。
DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a pedestal structure for supporting a reactor pressure vessel in a reactor containment vessel.

[従来の技術] 従来のコンクリート製の原子炉格納容器は、例えば、
第4図に示すように原子炉格納容器1内に原子炉圧力容
器2が収納され、その圧力容器2を支持する円筒状のペ
デスタル3(支持受座)が立設されている。また、この
ペデスタル3と原子炉格納容器1の外壁4との間には、
原子炉格納容器1内を上下に仕切るダイヤフラムフロア
5が架け渡され、その下方にはプール水7aが貯溜された
圧力抑制室7が形成されると共に、その上方には原子炉
圧力容器2を囲むように上部ドライウェル6が形成され
ている。さらに、このペデスタル3内には下部ドライウ
ェル8が形成されている。
[Prior Art] Conventional reactor vessels made of concrete include, for example,
As shown in FIG. 4, a reactor pressure vessel 2 is housed in a reactor containment vessel 1, and a cylindrical pedestal 3 (support seat) for supporting the pressure vessel 2 is provided upright. Also, between the pedestal 3 and the outer wall 4 of the containment vessel 1,
A diaphragm floor 5 that vertically partitions the inside of the reactor containment vessel 1 is bridged, a pressure suppression chamber 7 storing pool water 7a is formed below the diaphragm floor 5, and the reactor pressure vessel 2 is surrounded above the pressure suppression chamber 7. The upper dry well 6 is formed as described above. Further, a lower dry well 8 is formed in the pedestal 3.

上記ペデスタル3は、構成のブロック体9とこれに沿
って打設されるコンクリート壁10とで構成されており、
構成のブロック体9は、図示するように同心状に設けら
れた内筒11、中間筒12、外筒13の筒体と、これら内筒1
1、中間筒12、外筒13の円周方向に配列された多数の縦
リブ14とで形成され、内筒11、中間筒12、縦リブ14で円
周方向に区画される孔のうちその一部は、上記上部ドラ
イウェル6から下部ドライウェル8へ連通する連通孔15
が形成されている。また、他の孔の一部には、上部ドラ
イウェル6に高温高圧の蒸気が漏れだした際に、これを
圧力抑制室7内のプール水7a中に導くためのベント通路
16が形成されている。
The pedestal 3 is composed of a block body 9 having a configuration and a concrete wall 10 cast along the block body 9.
The block body 9 having the configuration includes a cylindrical body of an inner cylinder 11, an intermediate cylinder 12, and an outer cylinder 13 provided concentrically as shown
1, the intermediate cylinder 12, the outer cylinder 13 is formed with a number of vertical ribs 14 arranged in the circumferential direction, the inner cylinder 11, the intermediate cylinder 12, the Some of the communication holes 15 communicate from the upper dry well 6 to the lower dry well 8.
Are formed. In addition, a vent passage for guiding high-temperature and high-pressure steam leaking into the upper dry well 6 into the pool water 7a in the pressure suppression chamber 7 is provided in a part of the other holes.
16 are formed.

[考案が解決しようとする課題] ところで、上述のペデスタル構造においては、上記連
通孔15内に、上部ドライウェル6から下部ドライウェル
8に通じる配管やダクト及び昇降用の梯子(いずれも図
示省略)等が設けられている。そして、これら配管や梯
子等は構成のブロック体9を立設した後、その上方から
図示しないクレーンなどで吊り下げられて連通孔15内に
挿入され、空中で宙吊り状態で内筒11あるいは中間筒12
のいずれかに据え付けられるようになっている。
[Problem to be Solved by the Invention] In the above-described pedestal structure, in the communication hole 15, a pipe, a duct, and a ladder for lifting and lowering (all not shown) are provided from the upper dry well 6 to the lower dry well 8. Etc. are provided. These pipes, ladders, and the like are erected on a block body 9 having a structure, suspended from above by a crane or the like (not shown), inserted into the communication hole 15, and suspended in the air in the inner cylinder 11 or the intermediate cylinder. 12
It is designed to be installed in any of

しかしながら、上記連通孔16は深くて狭い空間である
ため、この空間内において上述のように宙吊り状態で据
付け作業を行うことは危険を伴い、しかも、その取付作
業は不安定な状態で行われるため、据付精度が悪くなる
上に据付に多くの時間が掛かるといった欠点がある。
However, since the communication hole 16 is a deep and narrow space, performing the installation work in a suspended state as described above in this space involves danger, and the mounting work is performed in an unstable state. However, there are disadvantages that the installation accuracy is deteriorated and that much time is required for installation.

そこで、本考案はこれらの不都合を有効に解決するた
めに創案されたものであり、その目的は、連通孔の配管
やダクト及び梯子などを安全容易に取り付けることので
きる新規な原子炉圧力容器のペデスタル構造を提供する
ものである。
Therefore, the present invention has been made in order to effectively solve these inconveniences, and an object of the present invention is to provide a new reactor pressure vessel in which piping, ducts and ladders of communication holes can be easily and safely attached. It provides a pedestal structure.

[課題を解決するための手段] 上記課題を解決するために本考案は、原子炉圧力容器
を支持するペデスタルの鋼製ブロック体を、同心状に複
数配置した筒体とこれら筒体間を接続する複数の縦リブ
から構成すると共に、この鋼製ブロック体を、その円周
方向及び上下方向に格子状に分割した分割ブロックを順
次溶接して形成し、上記各分割ブロックを構成する筒体
と縦リブで区画される孔の一部を原子炉圧力容器外周の
上部ドライウェルと原子炉圧力容器下部の下部ドライウ
ェルとを連通する連通孔とすると共に、その連通孔の内
壁に、上記上部ドライウェルから下部ドライウェル側に
延びるダクト及び配管類の一部及び上記上部ドライウェ
ルと下部ドライウェル間を移動する梯子の一部を予め組
み込んでおくようにしたものである。
[Means for Solving the Problems] In order to solve the above problems, the present invention connects a cylindrical body in which a plurality of steel blocks of a pedestal supporting a reactor pressure vessel are concentrically arranged, and connects these cylindrical bodies. The steel block body is formed by sequentially welding the divided blocks obtained by dividing the steel block body into a lattice shape in the circumferential direction and the vertical direction, and a cylindrical body constituting each of the divided blocks. Some of the holes defined by the vertical ribs are used as communication holes for communicating the upper dry well on the outer periphery of the reactor pressure vessel with the lower dry well below the reactor pressure vessel, and the upper dry well is formed on the inner wall of the communication hole. A part of ducts and pipes extending from the well to the lower drywell side and a part of a ladder moving between the upper drywell and the lower drywell are incorporated in advance.

[作用] 本発明はペデスタルは上述したように、原子炉圧力容
器を支持するペデスタルの鋼製ブロック体を、予め工場
などにおいて配管類及び梯子の一部を据え付けた分割ブ
ロックで構成したことから、現場におけるダクト及び配
管類や梯子の宙吊り状態での据付作業を省略することが
できる。
[Operation] As described above, the pedestal according to the present invention has a steel block body of the pedestal supporting the reactor pressure vessel as a divided block in which pipes and a part of a ladder are previously installed in a factory or the like. The installation work in the suspended state of the duct, the piping, and the ladder at the site can be omitted.

[実施例] 次に本考案の実施例を添付図面に基づいて説明する。[Example] Next, an example of the present invention will be described with reference to the accompanying drawings.

第1図乃至第3図は本考案に係る原子炉圧力容器のペ
デスタル構造の一実施例を示すものある。なお、図中従
来例と共通の部分には同一符号を付し、説明を省略す
る。
1 to 3 show an embodiment of the pedestal structure of the reactor pressure vessel according to the present invention. In the drawing, the same reference numerals are given to the same parts as those in the conventional example, and the description will be omitted.

図示するように、原子炉圧力容器2を支持するペデス
タル3は筒状をした鋼製のブロック体9からなってお
り、さらに、このブロック体9は、同心状に設けられた
内筒11、中間筒12、外筒13の筒体と、これら内筒11、中
間筒12、外筒13間にその円周方向に配列された多数の縦
リブ14とで形成されている。また、この内筒11と中間筒
12及び縦リブ14で区画形成される複数の孔のうち、その
一部は上述した上部ドライウェル6から下部ドライウェ
ル8に連通する連通孔15となっており、さらにこの連通
孔15内には、上部ドライウェル6から下部ドライウェル
8に通じる配管17や昇降用の梯子18等が設けられてい
る。
As shown in the figure, the pedestal 3 supporting the reactor pressure vessel 2 is composed of a cylindrical steel block body 9, and this block body 9 is further provided with a concentric inner cylinder 11, an intermediate cylinder It is formed by a cylindrical body of a cylinder 12, an outer cylinder 13, and a number of vertical ribs 14 arranged in the circumferential direction between the inner cylinder 11, the intermediate cylinder 12, and the outer cylinder 13. The inner cylinder 11 and the intermediate cylinder
Among the plurality of holes defined by the vertical ribs 12 and 12, a part of the holes is a communication hole 15 communicating from the upper dry well 6 to the lower dry well 8 described above. A pipe 17 leading from the upper dry well 6 to the lower dry well 8 and a ladder 18 for raising and lowering are provided.

また、この鋼製のブロック体9は、その円周方向及び
上下方向に格子状に分割(図中二点鎖線A,B,C,Dは分割
線を示す)された複数のブロック19にからなっており、
これら各分割ブロック19を原子炉格納容器1内に筒状に
順次積み重ねてそれぞれを接合して立設形成されてい
る。
The steel block body 9 is divided into a plurality of blocks 19 that are divided in a grid shape in the circumferential direction and the vertical direction (two-dot chain lines A, B, C, and D indicate dividing lines in the figure). Has become
Each of these divided blocks 19 is sequentially stacked in a cylindrical shape in the reactor containment vessel 1 and joined to each other to be erected.

そして、これら分割ブロック19の連通孔15内には、第
3図に示すように、分割ブロック19の高さと略同じ長さ
に分割された配管17や梯子18類が据付けられている。
As shown in FIG. 3, pipes 17 and ladders 18 which are divided into the same length as the height of the divided block 19 are installed in the communication holes 15 of the divided blocks 19.

そして、このような鋼製をした鋼製ブロック体9を組
み立てるには、先ずその円周方向及び上下方向に格子状
に分割(第1図及び第2図中、A,B,C,Dは分割線を示
す)したような複数の分割ブロック19を工場などにおい
て予め製作する。この時、これら各分割ブロック19を製
作する際に、分割ブロック19に形成される連通孔15内
に、分割された配管17及び梯子18等を同時に組み付けて
おく。次に、これら各分割ブロック19を現場に搬送した
後、原子炉格納容器1内に順次積み重ねて接合して筒状
をした鋼製のブロック体9を形成する。そして、このブ
ロック体9の組立に際して各分割ブロック19内に予め取
り付けてある分割された配管17や梯子18等を接合すれば
鋼製のブロック体9が形成されると同時にその連通孔15
内に位置する配管17や梯子18の据え付けが完了する。
In order to assemble the steel block body 9 made of such steel, first, the steel block body 9 is divided into a lattice shape in the circumferential direction and the vertical direction (A, B, C, and D in FIGS. A plurality of divided blocks 19 (showing dividing lines) are manufactured in advance in a factory or the like. At this time, when manufacturing each of the divided blocks 19, the divided pipes 17 and the ladders 18 and the like are simultaneously assembled in the communication holes 15 formed in the divided blocks 19. Next, after transporting these divided blocks 19 to the site, they are sequentially stacked in the reactor containment vessel 1 and joined to form a tubular steel block 9. At the time of assembling the block body 9, if the divided pipes 17, ladders 18, etc., which are attached in advance in the respective divided blocks 19, are joined, the steel block body 9 is formed and at the same time, the communication holes 15 are formed.
The installation of the piping 17 and the ladder 18 located inside is completed.

これにより、配管17や梯子18等の取付作業が分割ブロ
ック19を製作する工場などで取り付けられ、現場で連結
するだけなので、その据付作業を安全確実に行うことが
でき、またその据付精度も大幅に向上させることができ
る。
As a result, installation work such as pipes 17 and ladders 18 can be installed at the factory where the split block 19 is manufactured, and only connected at the site, so that the installation work can be performed safely and securely, and the installation accuracy is greatly improved. Can be improved.

[考案の効果] 以上要するに本考案によれば、鋼製ブロック体の連通
孔に備えられるダクト及び配管類や梯子の現場での宙吊
り状態での据付作業を省略できるため、据付時の安全性
が大きく向上すると共に、ダクト及び配管類や梯子の据
付精度も大幅に向上して信頼性の高いペデスタルを提供
することができる。
[Effects of the Invention] In summary, according to the present invention, it is possible to omit installation work in a suspended state at the site of ducts, pipes and ladders provided in the communication holes of the steel block body, so that safety at the time of installation can be reduced. This greatly improves the installation accuracy of ducts, piping, and ladders, and provides a highly reliable pedestal.

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

第1図は本考案の一実施例を示すペデスタルの一部断面
図、第2図は第1図のII-II線断面図、第3図は連通孔
を有する分割ブロックの一部を示す斜視図、第4図は原
子炉格納容器を示す概略全体断面図である。 図中2は原子炉圧力容器、3はペデスタル、6は上部ド
ライウェル、8は下部ドライウェル、9は鋼製のブロッ
ク体、11,12,13はそれぞれ筒体である内筒,中間筒,外
筒、14は縦リブ、15は連通孔、17は配管、18は梯子、19
は分割ブロックである。
1 is a partial sectional view of a pedestal showing one embodiment of the present invention, FIG. 2 is a sectional view taken along line II-II of FIG. 1, and FIG. 3 is a perspective view showing a part of a divided block having a communication hole. FIG. 4 is a schematic overall sectional view showing the containment vessel. In the figure, reference numeral 2 denotes a reactor pressure vessel, 3 denotes a pedestal, 6 denotes an upper dry well, 8 denotes a lower dry well, 9 denotes a steel block, and 11, 12, and 13 denote inner and intermediate cylinders, respectively. Outer cylinder, 14 is a vertical rib, 15 is a communication hole, 17 is a pipe, 18 is a ladder, 19
Is a divided block.

Claims (1)

(57)【実用新案登録請求の範囲】(57) [Scope of request for utility model registration] 【請求項1】原子炉圧力容器を支持するペデスタルの鋼
製ブロック体を、同心状に複数配置した筒体とこれら筒
体間を接続する複数の縦リブから構成すると共に、この
鋼製ブロック体を、その円周方向及び上下方向に格子状
に分割した分割ブロックを順次溶接して形成し、上記各
分割ブロックを構成する筒体と縦リブで区画される孔の
一部を原子炉圧力容器外周の上部ドライウェルと原子炉
圧力容器下部の下部ドライウェルとを連通する連通孔と
すると共に、その連通孔の内壁に、上記上部ドライウェ
ルから下部ドライウェル側に延びるダクトや配管類の一
部及び上記上部ドライウェルと下部ドライウェル間を移
動する梯子の一部を予め組み込んでおくようにしたこと
を特徴とする原子炉圧力容器のペデスタル構造。
1. A steel block for a pedestal supporting a reactor pressure vessel, comprising a plurality of concentrically arranged cylinders and a plurality of longitudinal ribs connecting between the cylinders. Are formed by sequentially welding the divided blocks divided in a grid shape in the circumferential direction and the vertical direction, and a part of the hole defined by the cylindrical body and the vertical rib constituting each of the divided blocks is formed in the reactor pressure vessel. A part of ducts and pipes extending from the upper dry well to the lower dry well side is formed on the inner wall of the communication hole, with a communication hole communicating the upper dry well on the outer periphery and the lower dry well below the reactor pressure vessel. A pedestal structure for a reactor pressure vessel, wherein a part of a ladder that moves between the upper drywell and the lower drywell is incorporated in advance.
JP1990040620U 1990-04-18 1990-04-18 Pedestal structure of reactor pressure vessel Expired - Lifetime JP2530865Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1990040620U JP2530865Y2 (en) 1990-04-18 1990-04-18 Pedestal structure of reactor pressure vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1990040620U JP2530865Y2 (en) 1990-04-18 1990-04-18 Pedestal structure of reactor pressure vessel

Publications (2)

Publication Number Publication Date
JPH041493U JPH041493U (en) 1992-01-08
JP2530865Y2 true JP2530865Y2 (en) 1997-04-02

Family

ID=31550564

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1990040620U Expired - Lifetime JP2530865Y2 (en) 1990-04-18 1990-04-18 Pedestal structure of reactor pressure vessel

Country Status (1)

Country Link
JP (1) JP2530865Y2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0633897Y2 (en) * 1989-03-03 1994-09-07 株式会社松田佛檀店 Assembled Kiriko Lantern
JP4987681B2 (en) * 2007-12-12 2012-07-25 株式会社東芝 Primary containment vessel and leak detection floor

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6381298U (en) * 1986-11-17 1988-05-28
JPH0545999Y2 (en) * 1987-05-13 1993-11-30

Also Published As

Publication number Publication date
JPH041493U (en) 1992-01-08

Similar Documents

Publication Publication Date Title
JP2530865Y2 (en) Pedestal structure of reactor pressure vessel
JP3946352B2 (en) Construction method of reactor containment vessel
JPS597929Y2 (en) steel pipe coupling
JPH09113667A (en) Method for constructing upper drywell in reactor containment and module used in this method
JP4352071B2 (en) Construction method of reactor containment vessel
JPS59192159A (en) Construction of plant structure
JPH0648377A (en) Fitting-out method for vessel funnel
JPH0669893U (en) Concrete containment pedestal
JP4251597B2 (en) Condenser and its construction method
JP4329156B2 (en) Construction method of above ground type double shell cryogenic tank
JPS581037B2 (en) Construction method of lining tank
JPH0455797A (en) Nuclear reactor containment
JPS626056A (en) Rising and falling stand for constructing high structure
JPH0242743Y2 (en)
JPS6257238B2 (en)
JPH01237493A (en) Reactor container made of concrete and construction thereof
JPS6315832Y2 (en)
JPS61270410A (en) Reinforcing device for leg column of elevatable offshore working platform
JPS6392895A (en) Construction of inner tank of double shell tank
JPH0571798U (en) Structure of reactor shield wall
JPH0138280B2 (en)
JPS6024437B2 (en) Pedestal structure of reactor pressure vessel
JPH0741494U (en) Containment vessel
JPS6317495U (en)
JPH04327100A (en) Method of constructing double shell low temperature tank