JPS58155386A - Reactor pressure vessel pedestal - Google Patents

Reactor pressure vessel pedestal

Info

Publication number
JPS58155386A
JPS58155386A JP57039052A JP3905282A JPS58155386A JP S58155386 A JPS58155386 A JP S58155386A JP 57039052 A JP57039052 A JP 57039052A JP 3905282 A JP3905282 A JP 3905282A JP S58155386 A JPS58155386 A JP S58155386A
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor pressure
vessel pedestal
cylindrical steel
pedestal
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
JP57039052A
Other languages
Japanese (ja)
Inventor
佐波 和久
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 JP57039052A priority Critical patent/JPS58155386A/en
Publication of JPS58155386A publication Critical patent/JPS58155386A/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

  • Auxiliary Devices For And Details Of Packaging Control (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] 本発明は原子炉圧力容器ペデスタルに係わり、特に制作
備え付は工程の短縮化および工事の安全性の向上を図っ
た原子炉圧力容器ペデスタルに閤する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a reactor pressure vessel pedestal, and in particular, to a reactor pressure vessel pedestal that is designed to shorten the manufacturing process and improve construction safety. do.

[発明の技術的背景コ 第1図は従来の沸騰水形原子炉を示すもので、図におい
て符号1は原子炉建[12内に収容される原子炉格納容
器を示している。この原子炉格納容器1はダイヤフラム
フロア3により、ドライウェル4とウェットウェル5に
2分割され、ウェットウェル5の底面を構成する基礎コ
ンクリートマツトロにはドライウェル4内に上部を配設
される原子炉f1h容器ペデスタル7が立設されている
。ドライウェル内にはこの原子炉圧力容器ペデスタル7
上に載置支持される原子炉圧力容器8が収容され、この
原子炉圧力容器8は、原子炉圧力容器ペデスタル7上に
載置される原子炉遮蔽19に囲繞されている。またダイ
ヤフラムフロア3にはウェットウェル5に向けて多数の
ベント管10が植設されている。
[Technical Background of the Invention] Fig. 1 shows a conventional boiling water nuclear reactor, and in the figure, reference numeral 1 indicates a reactor containment vessel housed within a reactor building [12]. This reactor containment vessel 1 is divided into two by a diaphragm floor 3 into a dry well 4 and a wet well 5, and the base concrete Matsutoro that forms the bottom of the wet well 5 has an upper part arranged inside the dry well 4. A furnace f1h container pedestal 7 is erected. Inside the dry well is this reactor pressure vessel pedestal 7.
A reactor pressure vessel 8 mounted and supported thereon is accommodated, which is surrounded by a reactor shield 19 which rests on the reactor pressure vessel pedestal 7 . Further, a large number of vent pipes 10 are installed in the diaphragm floor 3 toward the wet well 5.

このように構成された沸騰水形原子炉では、原子炉圧力
容器ペデスタル7は原子炉圧力容器8等の重要かつ重曇
物を支えているため鉄筋量の非常に多い鉄筋コンクリー
ト類とされ、すべて現地作業により備え付けられている
In a boiling water reactor configured in this way, the reactor pressure vessel pedestal 7 supports important and heavy objects such as the reactor pressure vessel 8, so it is made of reinforced concrete with a very large amount of reinforcing steel, and all of it is constructed on-site. Equipped with work.

しかしながら、この原子炉圧力容器ペデスタル7の完成
はダイヤフラムフロア3を搭載するための必要条件であ
り、またダイヤフラムフロア3の搭載は原子炉格納容器
1の上部の現地備え付けの必要条件となっている。
However, the completion of the reactor pressure vessel pedestal 7 is a necessary condition for installing the diaphragm floor 3, and the installation of the diaphragm floor 3 is also a necessary condition for the on-site installation of the upper part of the reactor containment vessel 1.

また、原子炉圧力容器ペデスタル7の完成後、原子炉遮
蔽壁9の備え付け、原子炉圧力容器1の備え付け、原子
炉格納容器1内の構造物、配管等の備え付けが行なわれ
るため、この原子炉圧力容器ペデスタル7の備え付は工
程の短縮は、発電所建設工程を短縮するための重要な要
素となってる。
In addition, after the reactor pressure vessel pedestal 7 is completed, the reactor shielding wall 9, the reactor pressure vessel 1, and the structures and piping inside the reactor containment vessel 1 will be installed. The shortening of the process for installing the pressure vessel pedestal 7 is an important element for shortening the power plant construction process.

そこで、この原子炉圧力容器ペデスタル7の備え付は工
程を短縮化するために、例えば、原子炉圧力容器ペデス
タル7の主体構造を鋼製とし、従来現地において行われ
ていた鉄筋組立作業をなくし、かつ鋼製部を工場にて分
割制作して、現地においてこれを溶接により組立てるこ
とが行われている。
Therefore, in order to shorten the installation process of the reactor pressure vessel pedestal 7, for example, the main structure of the reactor pressure vessel pedestal 7 is made of steel, eliminating the reinforcing steel assembly work that was conventionally done on site. In addition, the steel parts are produced in parts at a factory and then assembled on-site by welding.

しかしながら、この溶接作業は、主に原子炉圧力容器ペ
デスタル7の構成する閉空間での作業となるため、この
溶接作業にがなりの時間が費され、また作業員の安全管
理上望ましくない。
However, this welding work is mainly performed in the closed space constituted by the reactor pressure vessel pedestal 7, and therefore a considerable amount of time is consumed in this welding work, which is not desirable in terms of safety management of the workers.

[発明の目的] 本発明はかかる従来の事情に対処してなされたもので、
工期の短縮化を計ることができるとともに、作業員の安
全性を高めることのできる原子炉圧力容器ペデスタルを
提供しようとするものである。
[Object of the invention] The present invention has been made in response to such conventional circumstances,
The objective is to provide a reactor pressure vessel pedestal that can shorten the construction period and improve worker safety.

[発明の概要] すなわち本発明は、同心円状の複数の円筒鋼板と、これ
を補強する平板とから構成される原子炉圧力容器ペデス
タルにおいて、前記円筒鋼板は接合部材を介して相互に
ボルト接合されていることを特徴とする原子炉圧力容器
ペデスタルである。
[Summary of the Invention] That is, the present invention provides a reactor pressure vessel pedestal comprising a plurality of concentric cylindrical steel plates and a flat plate reinforcing the cylindrical steel plates, in which the cylindrical steel plates are bolted to each other via a joining member. This is a reactor pressure vessel pedestal that is characterized by:

[発明の実施例] 以下本発明の詳細を図面に示す一実施例について説明す
る。
[Embodiment of the Invention] The details of the present invention will be described below with reference to an embodiment shown in the drawings.

第2図は本発明の一実施例の原子炉圧力容器ぺfスタル
を示すもので、図において符号11は原子炉圧力容器ペ
デスタルを示している。この原子炉圧力容器ペデスタル
11は4つの円筒鋼板a1b、c1dから構成されてお
り、基礎コンクリ−[・マット12の支柱13上に立設
されている。そしてこの原子炉圧力容器ペデスタル11
は内壁を構成する内筒14と、この内筒14を一定間隔
で囲繞する外筒15とから構成されており、外筒15と
内筒14との闇には、この原子炉圧力容器ペデスタル1
1を補強するための平板からなる縦リブ16が介挿され
ている。
FIG. 2 shows a reactor pressure vessel pedestal according to an embodiment of the present invention, and in the figure, reference numeral 11 indicates the reactor pressure vessel pedestal. This reactor pressure vessel pedestal 11 is composed of four cylindrical steel plates a1b and c1d, and is erected on supports 13 of a foundation concrete mat 12. And this reactor pressure vessel pedestal 11
The reactor pressure vessel pedestal 1 is composed of an inner cylinder 14 that forms an inner wall, and an outer cylinder 15 that surrounds the inner cylinder 14 at regular intervals.
A vertical rib 16 made of a flat plate is inserted to reinforce the structure 1.

すなわち、それぞれの円筒鋼板a、b1c、dは、原子
炉圧力容器ペデスタル11を軸に垂直に切断して得られ
る円環形状とされており、基礎コンクリートマット12
の上に直接載置される円筒鋼板aの上には円筒鋼板すが
載置され、この円筒鋼板すの上には円筒鋼板Cが載置さ
れ、この円筒鋼板Cの上には円筒鋼板dが順に載置され
ている。
That is, each of the cylindrical steel plates a, b1c, and d has an annular shape obtained by cutting the reactor pressure vessel pedestal 11 perpendicularly to the axis, and the base concrete mat 12
A cylindrical steel plate a is placed on top of the cylindrical steel plate a, a cylindrical steel plate C is placed on this cylindrical steel plate, and a cylindrical steel plate d is placed on top of this cylindrical steel plate C. are listed in order.

そして、円筒鋼板aには原子炉圧力容器ペデスタル11
の剛性をあげるための中817が挿入されており、円筒
鋼板すの上部には補強部材18が橋設されている。円筒
鋼板a、bの側面には、それぞれ4個の貫通孔19が穿
設されている。
The cylindrical steel plate a has a reactor pressure vessel pedestal 11.
A reinforcing member 18 is installed on the top of the cylindrical steel plate. Four through holes 19 are bored in each side of the cylindrical steel plates a and b.

そして、それぞれの円筒鋼板a、b、c、dは、第3図
に示すようにして接合されている。すなわち第3図にお
いて符号16は内1114と外筒15の間に介挿される
縦リブ16を示しており、縦す116はそれぞれその上
端および下端において当接している。そして縦リブ16
は同一垂直平面内に位置している。この縦リブ16は接
合部材20により第4図に示すようにボルト接合されて
いる。
The respective cylindrical steel plates a, b, c, and d are joined as shown in FIG. That is, in FIG. 3, reference numeral 16 indicates a vertical rib 16 inserted between the inner cylinder 1114 and the outer cylinder 15, and the vertical ribs 116 are in contact with each other at their upper and lower ends. and vertical rib 16
are located in the same vertical plane. The vertical ribs 16 are bolted together by a joining member 20, as shown in FIG.

すなわち第4図において符号20は、接合部材を示して
おり、この接合部材20は縦リブ16を跨いで縦リブ1
6の両面からこの縦リブ16に当接されている。この接
合部材20、縦リブ16、接合部材20を貫通して多数
の貫通孔21が穿設されており、この貫通孔21にはボ
ルト22が先端を突出させて挿入されている。ボルト2
2の先端に形成されるねじにはナツト23が螺合され、
接合部4120は縦リブ16に締付けられている。
That is, in FIG. 4, the reference numeral 20 indicates a joining member, and this joining member 20 straddles the vertical rib 16 and
6 is in contact with this vertical rib 16 from both sides. A large number of through holes 21 are bored through the joining member 20, the vertical rib 16, and the joining member 20, and bolts 22 are inserted into the through holes 21 with their tips protruding. bolt 2
A nut 23 is screwed into the screw formed at the tip of 2,
The joint portion 4120 is fastened to the vertical rib 16.

なお円筒鋼板a、b1c、dの内筒14と内筒14の当
接部24および外筒15と外筒15の当接部25は比較
的溶接作業が容易であるので第3図に示すように溶接接
合されている。
Note that the abutting portions 24 between the inner tubes 14 and the abutting portions 25 between the outer tubes 15 and the outer tubes 15 of the cylindrical steel plates a, b1c, and d are relatively easy to weld, so weld them as shown in Fig. 3. are welded together.

以上のように構成された原子炉圧力容器ペデスタルでは
、縦リブ16の接合は内筒14と外筒15で囲まれた密
閉空間で行なわれることとなるが、この作業は貫通孔2
1にボルト22を挿入し反対側からナツト23で締付け
るだけで済むため、作業性および安全性が従来の溶接に
よる場合に比較して大幅に向上する。
In the reactor pressure vessel pedestal configured as described above, the vertical ribs 16 are joined in a closed space surrounded by the inner cylinder 14 and the outer cylinder 15, but this work is performed in the through hole 2.
Since it is only necessary to insert the bolt 22 into the bolt 1 and tighten it with the nut 23 from the opposite side, workability and safety are greatly improved compared to conventional welding.

し発明の効果] 以上述べたように、本発明の原子炉圧力容器ペデスタル
によれば、原子炉圧力容器ペデスタルの建設工期を大幅
に短縮することができるとともに、作業者の安全性を向
上することができる。
[Effects of the Invention] As described above, according to the reactor pressure vessel pedestal of the present invention, the construction period of the reactor pressure vessel pedestal can be significantly shortened, and the safety of workers can be improved. I can do it.

なお以上述べた実施例では、円筒鋼板a、b1cSdの
内筒14および外筒15の当接部24.25を溶接によ
り接合した例について述べたが、曲面状に形成された接
合部材を用いてボルト接合してもよいことは勿論である
In addition, in the embodiment described above, an example was described in which the contact parts 24 and 25 of the inner cylinder 14 and the outer cylinder 15 of the cylindrical steel plates a and b1cSd were joined by welding. Of course, bolted connection may also be used.

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

第1図は従来の沸騰水形原子炉を示す縦断面図、第2図
は本発明の一実施例の原子炉圧力容器ペデスタルを示す
縦断面図、第3図は第2図の接合部の詳細を示す縦断面
図、第4図は第3図のIV−IV線に沿う縦断面図であ
る。 11・・・・・・・・・・・・原子炉圧力容器ペデスタ
ル20・・・・・・・・・・・・接合部材22・・・・
・・・・・・・・ボルト a、blc、d・・・・・・・・・・・・円筒鋼板代理
人弁理士   須 山 佐 − 第1図 第2図 第3図 16 第4図
FIG. 1 is a longitudinal sectional view showing a conventional boiling water reactor, FIG. 2 is a longitudinal sectional view showing a reactor pressure vessel pedestal according to an embodiment of the present invention, and FIG. FIG. 4 is a vertical sectional view taken along the line IV--IV in FIG. 3, showing details. 11......Reactor pressure vessel pedestal 20......Joint member 22...
・・・・・・Bolts a, blc, d・・・・・・・・・Cylindrical steel plate representative Patent attorney Sa Suyama - Figure 1 Figure 2 Figure 3 Figure 16 Figure 4

Claims (1)

【特許請求の範囲】[Claims] (1)同心円状の複数の円筒鋼板と、これを補強する平
板とから構成される原子炉圧力容器ペデスタルにおいて
、前記円筒鋼板は接合部材を介して相互にボルト接合さ
れていることを特徴とする原子炉圧力容器ペデスタル。
(1) A reactor pressure vessel pedestal consisting of a plurality of concentric cylindrical steel plates and a flat plate reinforcing the same, characterized in that the cylindrical steel plates are bolted to each other via a joining member. Reactor pressure vessel pedestal.
JP57039052A 1982-03-12 1982-03-12 Reactor pressure vessel pedestal Pending JPS58155386A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57039052A JPS58155386A (en) 1982-03-12 1982-03-12 Reactor pressure vessel pedestal

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57039052A JPS58155386A (en) 1982-03-12 1982-03-12 Reactor pressure vessel pedestal

Publications (1)

Publication Number Publication Date
JPS58155386A true JPS58155386A (en) 1983-09-16

Family

ID=12542352

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57039052A Pending JPS58155386A (en) 1982-03-12 1982-03-12 Reactor pressure vessel pedestal

Country Status (1)

Country Link
JP (1) JPS58155386A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS546308A (en) * 1977-06-16 1979-01-18 Ishikawajima Harima Heavy Ind Pedestal in steel
JPS56157895A (en) * 1980-05-09 1981-12-05 Hitachi Ltd Method of installing nuclear reactor pressure vessel pedestal

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS546308A (en) * 1977-06-16 1979-01-18 Ishikawajima Harima Heavy Ind Pedestal in steel
JPS56157895A (en) * 1980-05-09 1981-12-05 Hitachi Ltd Method of installing nuclear reactor pressure vessel pedestal

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