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JP2945706B2 - Reactor pressure vessel support base - Google Patents
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JP2945706B2 - Reactor pressure vessel support base - Google Patents

Reactor pressure vessel support base

Info

Publication number
JP2945706B2
JP2945706B2 JP2076985A JP7698590A JP2945706B2 JP 2945706 B2 JP2945706 B2 JP 2945706B2 JP 2076985 A JP2076985 A JP 2076985A JP 7698590 A JP7698590 A JP 7698590A JP 2945706 B2 JP2945706 B2 JP 2945706B2
Authority
JP
Japan
Prior art keywords
pressure vessel
support base
reactor pressure
rpv
opening
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 - Fee Related
Application number
JP2076985A
Other languages
Japanese (ja)
Other versions
JPH03277993A (en
Inventor
泉 米川
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 JP2076985A priority Critical patent/JP2945706B2/en
Publication of JPH03277993A publication Critical patent/JPH03277993A/en
Application granted granted Critical
Publication of JP2945706B2 publication Critical patent/JP2945706B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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】 〔発明の目的〕 (産業上の利用分野) 本発明は沸騰水形原子力発電設備における原子炉圧力
容器支持架台構造に係り、特に原子炉圧力容器支持架台
に配管、ダクト、ベント、ケーブル等を収納した原子炉
圧力容器支持架台に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Field of Industrial Application) The present invention relates to a structure for supporting a reactor pressure vessel in a boiling water nuclear power plant, and in particular, pipes and ducts for the reactor pressure vessel supporting platform. The invention relates to a reactor pressure vessel support pedestal that accommodates reactors, vents, cables and the like.

(従来の技術) 沸騰水形原子力発電設備では原子炉建屋内に原子炉格
納容器が格納され、この原子炉格納容器内に収納された
原子炉圧力容器(以下、RPVという。)が原子炉圧力容
器支持架台(以下、RPV支持架台という。)上に支持さ
れる。従来このRPV支持架台の構造は、特開昭63−28449
3号公報にも開示されており、第4図の横断面図に示す
ように、同心円状に配設された複数の円筒形の鉄板1と
放射状に配設された複数の鉄板2とを一体に結合して組
み立て、この円筒組立体に複数の開口部3を残してコン
クリート4を注入してRPV支持架台5を構成している。
このRPV支持架台5の開口部3に、配管、ケーブル等を
案内する構成部材6を挿通し、この構成部材6内に配管
やケーブル等を挿通案内している。このようにして、RP
V支持架台5内に配管、ケーブルボックス(シュート)
等が収納可能な構造となっている。
(Conventional technology) In a boiling water nuclear power plant, a reactor containment vessel is housed in a reactor building, and a reactor pressure vessel (hereinafter referred to as an RPV) housed in the reactor containment vessel has a reactor pressure. It is supported on a container support base (hereinafter, referred to as an RPV support base). Conventionally, the structure of this RPV support base is disclosed in JP-A-63-28449.
As shown in FIG. 4, a plurality of cylindrical iron plates 1 arranged concentrically and a plurality of iron plates 2 arranged radially are also disclosed in Japanese Patent Publication No. Then, concrete 4 is poured into this cylindrical assembly while leaving a plurality of openings 3 to form an RPV support base 5.
A component member 6 for guiding pipes, cables, and the like is inserted into the opening 3 of the RPV support base 5, and pipes, cables, and the like are inserted and guided in the component member 6. In this way, RP
Piping and cable box (chute) in V support base 5
Etc. can be stored.

(発明が解決しようとする課題) 従来のRPV支持架台は、一般にはRPV支持架台完成後に
配管やケーブル等の構成部材6を開口部3内に挿通させ
て据え付ける据付工事を行なっており、このためRPV支
持架台5の狭い開口部3内で配管等を案内する構成部材
6の据付工事が必要であった。
(Problems to be Solved by the Invention) The conventional RPV support gantry is generally installed after the RPV support gantry is completed by inserting the component members 6 such as pipes and cables into the opening 3 for installation. The installation work of the component member 6 for guiding the pipes and the like in the narrow opening 3 of the RPV support base 5 was required.

本発明は上述した事情を考慮してなされたもので、ケ
ーブルボックスやダクト等の据付工事を不要にする一
方、据付工事を不要にしても、多数の配管、ケーブル、
ダクト、ベント等をRPV支持架台に貫通させて収納可能
なRPV支持架台を提供することを目的とする。
The present invention has been made in view of the above circumstances, and while eliminating the need for installation work such as cable boxes and ducts, even if installation work is not required, a large number of pipes, cables,
It is an object of the present invention to provide an RPV support gantry in which a duct, a vent, and the like can be housed by penetrating the RPV support gantry.

〔発明の構成〕[Configuration of the invention]

(課題を解決するための手段) 本発明に係るRPV支持架台は、上述した課題を解決す
るために、原子炉圧力容器の下部を支持する原子炉圧力
容器支持架台が上部のドライウェルと下部の圧力抑制室
との境界を形成する一方、上記原子炉圧力容器支持架台
は、同心円状に配設した複数の円筒形の鉄板と放射状に
配設した複数の鉄板とを一体に組立て、この円筒組立て
体に前記ドライウェルと圧力抑制室とを連通する複数の
開口部を残してコンクリートを注入して構成されたもの
において、前記原子炉圧力容器支持架台の各開口部は、
空気調和用ダクト、ケーブルボックスおよびベント用の
予め設定された寸法形状に製作され、上記原子炉圧力容
器支持架台の構築後にそのまま空気調和用ダクト、ケー
ブルボックスおよびベントとして使用可能な構造とした
ものである。
(Means for Solving the Problems) In order to solve the above-mentioned problems, the RPV support pedestal according to the present invention has a reactor pressure vessel support pedestal supporting a lower part of a reactor pressure vessel, and an upper dry well and a lower dry well. While forming the boundary with the pressure suppression chamber, the reactor pressure vessel support pedestal integrally assembles a plurality of concentrically arranged cylindrical iron plates and a plurality of radially arranged iron plates, and assembles this cylinder. In what is configured by injecting concrete leaving a plurality of openings communicating the dry well and the pressure suppression chamber to the body, each opening of the reactor pressure vessel support pedestal,
The air conditioning duct, cable box and vent are manufactured to have predetermined dimensions and shapes, and can be used as air conditioning duct, cable box and vent as they are after the construction of the reactor pressure vessel support base. is there.

(作用) このRPV支持架台は、多重円筒形の鉄板と放射状の鉄
板とを一体に組み立てた円筒組立体に、複数の開口部を
残してコンクリートを注入してRPV支持架台を構成し、
このRPV支持架台の開口部を配管貫通孔部やダクト、ケ
ーブルボックス、ベントとして利用したので、原子炉格
納容器内の上部空間と下部空間とを連絡する配管やケー
ブル、ダクト等を多数必要とする原子炉発電設備に有効
であり、RPV支持架台の構造体としての機能を損うこと
もない。
(Operation) This RPV support gantry is composed of a cylindrical assembly in which a multi-cylindrical iron plate and a radial iron plate are integrally assembled, and concrete is poured into the cylindrical assembly leaving a plurality of openings to form an RPV support gantry.
Since the opening of the RPV support base is used as a pipe through-hole, duct, cable box, and vent, many pipes, cables, ducts, etc., are required to connect the upper and lower spaces in the PCV. It is effective for nuclear power plants and does not impair the function of the RPV support base structure.

また、RPV支持架台の開口部を配管貫通孔部やダク
ト、ケーブルボックス、ベントとして直接利用できるの
で、ケーブルボックスやダクト等の据付工事が不要とな
る一方、開口部への配管やケーブル等をガイドする構成
部材の据付けが必要となる。また、配管も配管サポート
や据付具を介しての取付けが不要で、配管貫通部へのコ
ンクリートの注入、硬化による簡単な配管の仮設定で配
管を据付、保持させることができる。
In addition, since the opening of the RPV support base can be directly used as a pipe through-hole, duct, cable box, and vent, installation work for cable boxes and ducts is not required, while guides for piping and cables to the opening are provided. It is necessary to install the constituent members. In addition, the pipe does not need to be mounted via a pipe support or an installation tool, and the pipe can be installed and held by a simple temporary setting of the pipe by injecting concrete into the pipe penetration part and hardening.

(実施例) 以下、本発明に係るRPV支持架台の一実施例について
添付図面を参照して説明する。
(Example) Hereinafter, an example of an RPV support base according to the present invention will be described with reference to the accompanying drawings.

第2図は本発明のRPV支持架台を有する沸騰水型原子
炉設備を示すものであり、この原子炉設備は原子炉建屋
10内に原子炉格納容器11が格納されている。この原子炉
格納容器11内には原子炉圧力容器(RPV)12が収納さ
れ、このRPV12は原子炉建屋マット13上に構築され、立
設されたRPV支持架台14により支持される。
FIG. 2 shows a boiling water reactor system having an RPV support base according to the present invention. The reactor system is a reactor building.
A reactor containment vessel 11 is stored in 10. A reactor pressure vessel (RPV) 12 is accommodated in the reactor containment vessel 11, and the RPV 12 is constructed on a reactor building mat 13 and supported by an upright RPV support base 14.

このRPV支持架台14は、第1図および第3図に示すよ
うに同心円状に配設された複数の円筒形の鉄板15と放射
状に配設された複数の鉄板16とを一体に結合して組み立
てた円筒組立体17を有し、この円筒組立体17に複数の開
口部18を残してコンクリート19を注入することにより構
成される。
As shown in FIGS. 1 and 3, the RPV support base 14 integrally connects a plurality of cylindrical iron plates 15 arranged concentrically and a plurality of iron plates 16 arranged radially. It has an assembled cylindrical assembly 17, and is constituted by injecting concrete 19 into the cylindrical assembly 17 while leaving a plurality of openings 18.

また、原子炉格納容器11内は、第2図に示すように、
上部のドライウェル20と下部のウェットウェルとしての
圧力抑制室21とに区画される。この圧力抑制室21はRPV
支持架台14の外側に位置される。圧力抑制室21は、サプ
レッションチャンバとして機能し、原子炉運転中はプー
ル水を溜め、事故時には原子炉格納容器11内に発生した
蒸気を凝縮させるチャンバである。
Further, as shown in FIG.
It is divided into an upper dry well 20 and a lower pressure suppression chamber 21 as a wet well. This pressure suppression chamber 21 is an RPV
It is located outside the support base 14. The pressure suppression chamber 21 functions as a suppression chamber, and is a chamber that stores pool water during operation of the reactor and condenses steam generated in the containment vessel 11 during an accident.

一方、RPV支持架台14に形成される複数の開口部18
は、事故時に原子炉格納容器11内で発生する蒸気を圧力
抑制室21に導く開口であったり、原子炉格納容器11内の
温度を調整する空気調和用ダクト22連絡用開口、RPV12
の下方機器へのケーブル23配線用開口である。また、原
子炉格納容器11の上部および下部を連絡する配管24は、
RPV支持架台14の開口部18に挿通された後、コンクリー
ト25を注入することにより埋設されて仮固定され、開口
部18内に貫通保持される。
On the other hand, a plurality of openings 18 formed in the RPV support
Is an opening for guiding steam generated in the containment vessel 11 during the accident to the pressure suppression chamber 21, an opening for communicating with the air conditioning duct 22 for adjusting the temperature in the containment vessel 11, and an RPV 12
This is an opening for wiring the cable 23 to the equipment below. In addition, a pipe 24 connecting the upper and lower parts of the reactor containment vessel 11 is
After being inserted into the opening 18 of the RPV support base 14, the concrete 25 is buried and temporarily fixed by injecting concrete 25, and is penetrated and held in the opening 18.

次に、RPV支持架台14の構築および作用について述べ
る。
Next, the construction and operation of the RPV support base 14 will be described.

RPV支持架台14は原子炉建屋マット13上に多重円筒形
鉄板15と放射状鉄板16とを一体に結合して円筒組立体17
を組み立て、この円筒組立体17に複数の開口部18を残し
てコンクリート19を注入することにより構成される。各
鉄板15,16によって円筒組立体17を構築する際に、各開
口部18をそれぞれの目的に応じた寸法形状に設定する。
The RPV support base 14 is formed by integrally combining a multi-cylindrical iron plate 15 and a radial iron plate 16 on a reactor building mat 13 and a cylindrical assembly 17.
Is assembled, and concrete 19 is poured into the cylindrical assembly 17 while leaving a plurality of openings 18. When the cylindrical assembly 17 is constructed from the iron plates 15 and 16, each opening 18 is set to a dimensional shape according to each purpose.

RPV支持架台14に形成される各開口部18は、空気調和
用ダクト22、ケーブル23を案内するケーブルボックス、
蒸気を導く開口としてのベント、あるいは配管挿通用開
口としての配管貫通孔部として構成され、RPV12下の原
子炉格納容器11内の圧力抑制室21とドライウェル20とを
多数の開口部18を介して連絡している。このうち、開口
部18内に挿通される配管24は、開口部18に挿通され、貫
通設定(仮設定)後に、コンクリート25を注入すること
により固定され、開口部18内に固定保持される。この配
管保持(据付)作業は、RPV支持架台14の対応する開口
部18にコンクリート25を注入するだけでよいので、開口
部18の狭い空間内での複雑な作業を省略でき、配管保持
固定作業が簡素化される。
Each opening 18 formed in the RPV support base 14 has an air conditioning duct 22, a cable box for guiding a cable 23,
It is configured as a vent as an opening for introducing steam or a pipe through hole as a pipe insertion opening, and connects the pressure suppression chamber 21 and the dry well 20 in the reactor containment vessel 11 below the RPV 12 through a number of openings 18. Contact. Among these, the pipe 24 inserted into the opening 18 is inserted into the opening 18, and after the penetration setting (temporary setting), is fixed by pouring concrete 25, and is fixed and held in the opening 18. This pipe holding (installation) work only needs to inject concrete 25 into the corresponding opening 18 of the RPV support base 14, so that complicated work in the narrow space of the opening 18 can be omitted, and the pipe holding and fixing work can be omitted. Is simplified.

〔発明の効果〕〔The invention's effect〕

以上に述べたように本発明に係る原子炉圧力容器支持
架台においては、原子炉圧力容器支持架台に形成される
開口部をダクト、ケーブルボックス、ベントあるいは配
管貫通孔部として構成したので、原子炉圧力容器支持架
台の開口部を直ちに空気調和用ダクト、ケーブルボック
ス(ケーブルダクト)、ベントとして利用することがで
き、原子炉格納容器内上部空間と下部空間とを連絡する
配管やケーブル、ダクト等を多数必要とする原子力発電
設備に特に有効で適したものとなる。
As described above, in the reactor pressure vessel supporting pedestal according to the present invention, the opening formed in the reactor pressure vessel supporting pedestal is configured as a duct, a cable box, a vent, or a pipe through-hole, so that the reactor The opening of the pressure vessel support base can be used immediately as an air conditioning duct, cable box (cable duct), or vent, and pipes, cables, and ducts that connect the upper space and lower space inside the containment vessel can be used. It is particularly effective and suitable for nuclear power plants that require a large number.

また、原子炉圧力容器支持架台の開口部をケーブルボ
ックスやダクト等としてそのまま利用したので、ケーブ
ルボックスやダクトを別途据付ける据付工事が不要とな
る一方、原子炉圧力容器支持架台を構築した後の支持架
台内部工事は開口部内への配管の仮設定だけとなるの
で、現地での建設工事期間を大幅に短縮させることがで
きる。
In addition, since the opening of the reactor pressure vessel support base was used as it was as a cable box or duct, installation work to separately install the cable box and duct was not required, but after the reactor pressure vessel support base was constructed Since the work inside the support gantry is only temporary setting of pipes in the opening, the construction work period on site can be greatly reduced.

さらに、原子炉圧力容器支持架台は各開口部を残して
他の部分にコンクリートを充填させるRPV支持架台構築
構造を援用したので開口部以外は物理的・機械的強度を
充分に維持することができ、開口部自身はRPV支持架台
構築後に空気調和用ダクト、ケーブルボックス、ベント
としてそのまま使用できる。
In addition, the reactor pressure vessel support base uses an RPV support base construction structure that fills the other parts with concrete while leaving each opening, so that physical and mechanical strength can be sufficiently maintained except for the openings. The opening itself can be used as it is as an air conditioning duct, cable box, and vent after the RPV support base is built.

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

第1図は本発明に係る原子炉圧力容器支持架台の一実施
例を示す部分的な縦断面図、第2図は本発明の原子炉圧
力容器支持架台を適用した沸騰水型原子力発電設備の縦
断面図、第3図は本発明の原子炉圧力容器支持架台を示
す平断面図、第4図は従来の原子炉圧力容器支持架台を
示す平断面図である。 10……原子炉建屋、11……原子炉格納容器、12……原子
炉圧力容器(RPV)、13……原子炉建屋マット、14……
原子炉圧力容器支持架台(RPV支持架台)、15,16……鉄
板、17……円筒組立体、18……開口部、19,25……コン
クリート、22……ダクト、23……ケーブル、24……配
管。
FIG. 1 is a partial longitudinal sectional view showing an embodiment of a reactor pressure vessel support base according to the present invention, and FIG. 2 is a boiling water nuclear power generation facility to which the reactor pressure vessel support base of the present invention is applied. FIG. 3 is a plan sectional view showing a reactor pressure vessel support gantry of the present invention, and FIG. 4 is a plan sectional view showing a conventional reactor pressure vessel support gantry of the present invention. 10 Reactor building, 11 Reactor containment vessel, 12 Reactor pressure vessel (RPV), 13 Reactor building mat, 14
Reactor pressure vessel support gantry (RPV support gantry), 15, 16… Iron plate, 17… Cylindrical assembly, 18… Opening, 19, 25… Concrete, 22… Duct, 23… Cable, 24 ……Piping.

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】原子炉圧力容器の下部を支持する原子炉圧
力容器支持架台が上部のドライウェルと下部の圧力抑制
室との境界を形成する一方、上記原子炉圧力容器支持架
台は、同心円状に配設した複数の円筒形の鉄板と放射状
に配設した複数の鉄板とを一体に組立て、この円筒組立
て体に前記ドライウェルと圧力抑制室とを連通する複数
の開口部を残してコンクリートを注入して構成されたも
のにおいて、前記原子炉圧力容器支持架台の各開口部
は、空気調和用ダクト、ケーブルボックスおよびベント
用の予め設定された寸法形状に製作され、上記原子炉圧
力容器支持架台の構築後にそのまま空気調和用ダクト、
ケーブルボックスおよびベントとして使用可能な構造と
したことを特徴とする原子炉圧力容器支持架台。
1. A reactor pressure vessel support base for supporting a lower part of a reactor pressure vessel forms a boundary between an upper dry well and a lower pressure suppression chamber, while the reactor pressure vessel support base has a concentric shape. A plurality of cylindrical iron plates and a plurality of radially arranged iron plates are integrally assembled, and concrete is left in this cylindrical assembly while leaving a plurality of openings communicating the drywell and the pressure suppression chamber. In the one constructed by injection, each opening of the reactor pressure vessel support pedestal is manufactured in a predetermined size and shape for an air conditioning duct, a cable box and a vent, and the reactor pressure vessel support pedestal is After the construction of the air conditioning duct,
A reactor pressure vessel support base having a structure usable as a cable box and a vent.
JP2076985A 1990-03-28 1990-03-28 Reactor pressure vessel support base Expired - Fee Related JP2945706B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2076985A JP2945706B2 (en) 1990-03-28 1990-03-28 Reactor pressure vessel support base

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2076985A JP2945706B2 (en) 1990-03-28 1990-03-28 Reactor pressure vessel support base

Publications (2)

Publication Number Publication Date
JPH03277993A JPH03277993A (en) 1991-12-09
JP2945706B2 true JP2945706B2 (en) 1999-09-06

Family

ID=13621074

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2076985A Expired - Fee Related JP2945706B2 (en) 1990-03-28 1990-03-28 Reactor pressure vessel support base

Country Status (1)

Country Link
JP (1) JP2945706B2 (en)

Also Published As

Publication number Publication date
JPH03277993A (en) 1991-12-09

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