JP2635856B2 - Protective equipment inside the PCV - Google Patents

Protective equipment inside the PCV

Info

Publication number
JP2635856B2
JP2635856B2 JP3173822A JP17382291A JP2635856B2 JP 2635856 B2 JP2635856 B2 JP 2635856B2 JP 3173822 A JP3173822 A JP 3173822A JP 17382291 A JP17382291 A JP 17382291A JP 2635856 B2 JP2635856 B2 JP 2635856B2
Authority
JP
Japan
Prior art keywords
communication hole
containment vessel
dry well
reactor
support structure
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
JP3173822A
Other languages
Japanese (ja)
Other versions
JPH0519085A (en
Inventor
俊博 船橋
中丸  哲也
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 Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
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 Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP3173822A priority Critical patent/JP2635856B2/en
Publication of JPH0519085A publication Critical patent/JPH0519085A/en
Application granted granted Critical
Publication of JP2635856B2 publication Critical patent/JP2635856B2/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】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【産業上の利用分野】本発明は沸騰水型原子炉の原子炉
格納容器内に立設されたペデスタルの連通孔内がたとえ
ば配管破断時の落下物により閉塞されるのを防止する原
子炉格納容器内の防護装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor containment for preventing a communication hole of a pedestal erected in a containment vessel of a boiling water reactor from being blocked by, for example, a fallen object when a pipe breaks. It relates to a protective device in a container.

【0002】[0002]

【従来の技術】改良型沸騰水型原子炉の原子炉格納容器
の形状は図3に示したように角形形状を呈しており、こ
の原子炉格納容器1内には中央部に筒状ペデスタル2
と、このペデスタル2に立設された原子炉圧力容器3
と、下部にサプレッションチェンバ4が設けられてい
る。
2. Description of the Related Art A reactor containment vessel of an improved boiling water reactor has a rectangular shape as shown in FIG.
And the reactor pressure vessel 3 erected on the pedestal 2
And a suppression chamber 4 is provided below.

【0003】サプレッションチェンバ4内にはベント管
5が設けられており、このベント管5はペデスタル2に
形成された連通孔6と連通している。連通孔6は上辺が
約2m,下辺が1.5m,高さが約1mの土台に近似し
た横断面が扇形をしており、その長さが約8mで、原子
炉圧力容器3を支持するペデスタル2の上下方向に設け
られている。また、原子炉格納容器1内はドライウェル
8とウエットウェル9に区画され、ドライウェル8は上
部ドライウェル8aと下部ドライウェル8bに二分さ
れ、両者は連通孔6によって連通している。ウエットウ
ェル9内にはサプレッションチェンバ4に没入する吐出
管7が設けられている。
[0003] A vent pipe 5 is provided in the suppression chamber 4, and the vent pipe 5 communicates with a communication hole 6 formed in the pedestal 2. The communication hole 6 has a fan-shaped cross section similar to a base having an upper side of about 2 m, a lower side of 1.5 m, and a height of about 1 m, and has a length of about 8 m and supports the reactor pressure vessel 3. The pedestal 2 is provided vertically. The inside of the reactor containment vessel 1 is divided into a dry well 8 and a wet well 9, and the dry well 8 is divided into an upper dry well 8 a and a lower dry well 8 b, and both are communicated by a communication hole 6. A discharge pipe 7 immersed in the suppression chamber 4 is provided in the wet well 9.

【0004】[0004]

【発明が解決しようとする課題】原子炉格納容器1内の
配管破断時のジェットは改良型沸騰水型原子炉のベント
管5と連通する連通孔6へ直接作用することはない。し
かしながら、このジェットによって破損した原子炉格納
容器1内の設備が連通孔6を塞ぐ可能性は残っている。
The jet at the time of a pipe break in the containment vessel 1 does not directly act on the communication hole 6 communicating with the vent pipe 5 of the improved boiling water reactor. However, there is a possibility that facilities in the containment vessel 1 damaged by the jet may block the communication hole 6.

【0005】改良型沸騰水型原子炉格納容器の連通孔6
の周辺部は原子炉格納容器内の配置設備によって非常に
狭隘な箇所となっており、連通孔6に防護構造体を設置
するにしても非常に困難を伴っている。また、上部ドラ
イウェル8aから下部ドライウェル8bへ連絡する配
管、ケーブル,ダクト等は連通孔6内を挿通しており、
これらの設置は連通孔6の入口部分で支持する必要があ
る。さらに、上部ドライウェル8aと下部ドライウェル
8bは内蔵する配管の破断時に放出されるエネルギを一
時的に吸収する役割がある。通常は上部ドライウェル8
aと下部ドライウェル8bは連通孔6で連接されてお
り、放出されたエネルギは両者の空間に吸収される。
[0005] The communication hole 6 of the improved boiling water reactor containment vessel
Is very narrow due to the arrangement equipment in the containment vessel, and it is very difficult to install a protective structure in the communication hole 6. In addition, pipes, cables, ducts, and the like communicating from the upper dry well 8a to the lower dry well 8b pass through the communication hole 6, and
These installations need to be supported at the entrance of the communication hole 6. Further, the upper dry well 8a and the lower dry well 8b have a role of temporarily absorbing energy released when the built-in piping is broken. Normally upper dry well 8
a and the lower dry well 8b are connected by the communication hole 6, and the released energy is absorbed in both spaces.

【0006】しかしながら、上部ドライウェル8a内で
配管破断を想定し、この影響で連通孔6が閉塞された場
合はエネルギを吸収する空間が上部ドライウェル8aの
みとなり、エネルギ吸収効率上不利となる課題がある。
However, assuming that the pipe is broken in the upper dry well 8a and the communication hole 6 is closed due to this effect, only the upper dry well 8a has a space for absorbing energy, which is disadvantageous in energy absorption efficiency. There is.

【0007】本発明は上記課題を解決するためになされ
たもので、想定した事故時においても連通孔の閉塞を回
避することができる原子炉格納容器内の防護装置を提供
することにある。
SUMMARY OF THE INVENTION The present invention has been made to solve the above problems, and it is an object of the present invention to provide a protection device in a reactor containment vessel capable of avoiding blockage of a communication hole even in an assumed accident.

【0008】[0008]

【課題を解決するための手段】本発明は沸騰水型原子炉
格納容器内に立設されたペデスタルの連通孔内に支持構
造ユニットを設け、この支持構造ユニット上に上部ドラ
イウェル内に突出して防護構造体を設置してなることを
特徴とする。
According to the present invention, a support structure unit is provided in a communication hole of a pedestal erected in a containment vessel of a boiling water reactor, and the support structure unit projects on the support structure unit into an upper dry well. A protective structure is provided.

【0009】[0009]

【作用】原子炉格納容器内の配管破断ジェットで破損し
た原子炉格納容器内設備の落下により連通孔が閉塞した
場合、配管破断口からの蒸気をサプレッションプールへ
導き凝縮させて圧力を低減させる原子炉格納容器の機能
確保が困難となるが、防護構造体を設けることによりこ
の機能が確保される。また、防護構造体は支持構造ユニ
ットと一体化することによって現地での防護構造体の設
置作業を大幅に低減できる。防護構造体の設置に際して
は配管破断ジェットを避けた配置にすることによってこ
の防護構造体の構造を簡素化にできる。
[Action] When the communication hole is closed due to the fall of the reactor containment vessel damaged by the pipe break jet in the reactor containment vessel, the atom from the pipe break port guides the vapor to the suppression pool to condense and reduce the pressure. Although it becomes difficult to secure the function of the furnace containment vessel, this function is secured by providing a protective structure. In addition, by integrating the protection structure with the support structure unit, installation work of the protection structure on site can be significantly reduced. When the protection structure is installed, the structure of the protection structure can be simplified by disposing the piping break jet.

【0010】[0010]

【実施例】図1および図2を参照しながら本発明に係る
原子炉格納容器内の防護装置の一実施例を説明する。図
1は本発明の要部のみを示しており、原子炉格納容器1
内の構造は図3と同様であるので省略している。また、
図2は図1の要部を拡大して斜視図で示している。すな
わち、上部ドライウェル8aと下部ドライウェル8bと
を有し、この両ドライウェル8a,8bを連通する連通
孔6を有する原子炉格納容器1において図1に示したよ
うにペデスタル2内に設けられた連通孔6内には脚立状
支持構造ユニット10が設けられており、この支持構造ユ
ニット10上に防護構造体11が設置されている。防護構造
体11は配管ケーブル,ダクト等の支持装置として利用で
きるように構成されている。すなわち、防護構造体11に
はサポート12を介して配管ケーブル13等が取着されてお
り、また、防護構造体11は格納容器内設備14および配管
破断ジェット15の影響を受けない配置レベルとなってい
る。なお、支持構造ユニット10は図2に示したように防
護構造体11との間に鋼板16および水平梁17を有してお
り、防護構造体11の先端部は上部ドライウェル8a側の
連通孔6の入口部位に突出している。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of a protection device in a containment vessel according to the present invention will be described with reference to FIGS. FIG. 1 shows only a main part of the present invention, and a primary containment vessel 1 is shown.
The structure inside is the same as that of FIG. Also,
FIG. 2 is an enlarged perspective view of a main part of FIG. That is, as shown in FIG. 1, the reactor containment vessel 1 having the upper dry well 8a and the lower dry well 8b and having the communication hole 6 communicating the dry wells 8a and 8b is provided in the pedestal 2 as shown in FIG. A stepladder-like support structure unit 10 is provided in the communication hole 6, and a protection structure 11 is installed on the support structure unit 10. The protection structure 11 is configured to be used as a support device for piping cables, ducts, and the like. That is, the piping cable 13 and the like are attached to the protective structure 11 via the support 12, and the protective structure 11 has an arrangement level that is not affected by the equipment 14 in the containment vessel and the pipe break jet 15. ing. The support structure unit 10 has a steel plate 16 and a horizontal beam 17 between the support structure unit 10 and the protection structure 11 as shown in FIG. 2, and the distal end of the protection structure 11 has a communication hole on the upper dry well 8a side. 6 project at the entrance site.

【0011】しかして、上記実施例によれば、想定した
事故時において連通孔6の閉塞を回避することができ
る。すなわち、連通孔6の入口部は狭隘な箇所となって
いるため、連通孔6を突設した防護構造体11はすでに設
置されている原子炉格納容器内構造材の一部を利用して
固定されている。そして、防護構造体11により原子炉格
納容器1の圧力低減機能を確保し、その構造をきわめて
簡素化でき、現地での据付作業を低減することができ
る。なお、防護構造体11の上面に鋼板16によりプラット
ホームを形成することによって連通孔6の上部に設置さ
れた設置へのアクセスが容易になる。また、防護構造体
11の設置に際しては配管破断ジェット15を避けて設置す
ることにより防護構造体11の構造を簡素化できる。
Thus, according to the above embodiment, it is possible to prevent the communication hole 6 from being blocked at the time of an assumed accident. That is, since the entrance of the communication hole 6 is narrow, the protective structure 11 having the communication hole 6 protruded is fixed by using a part of the structural material inside the reactor containment vessel already installed. Have been. Further, the pressure reducing function of the containment vessel 1 is secured by the protection structure 11, the structure can be extremely simplified, and the installation work on site can be reduced. In addition, by forming the platform by the steel plate 16 on the upper surface of the protection structure 11, access to the installation installed above the communication hole 6 becomes easy. Also, the protective structure
When installing the protection structure 11, the structure of the protection structure 11 can be simplified by avoiding the pipe break jet 15.

【0012】[0012]

【発明の効果】本発明によれば防護構造体を設けること
により原子炉格納容器の圧力低減機能を確保し、その構
造の簡素化が可能となり、それに加えて現地での据付作
業を低減することができる。
According to the present invention, by providing a protective structure, the pressure reducing function of the containment vessel can be secured, the structure can be simplified, and in addition, the installation work on site can be reduced. Can be.

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

【図1】本発明に係る原子炉格納容器内の防護装置の一
実施例を示す縦断面図。
FIG. 1 is a longitudinal sectional view showing one embodiment of a protection device in a containment vessel according to the present invention.

【図2】図1における要部を示す斜視図。FIG. 2 is a perspective view showing a main part in FIG. 1;

【図3】従来の原子炉格納容器内を概略的に示す縦断面
図。
FIG. 3 is a longitudinal sectional view schematically showing the inside of a conventional reactor containment vessel.

【符号の説明】[Explanation of symbols]

1…原子炉格納容器、2…ペデスタル、3…原子炉圧力
容器、4…サプレッションチェンバ、5…ベント管、6
…連通孔、7…吐出管、8…ドライウェル、9…ウエッ
トウェル、10…支持構造ユニット、11…防護構造体、12
…サポート、13…配管ケーブル、14…格納容器内設備、
15…ジェット、16…鋼板、17…水平梁。
DESCRIPTION OF SYMBOLS 1 ... Containment vessel, 2 ... Pedestal, 3 ... Reactor pressure vessel, 4 ... Suppression chamber, 5 ... Vent pipe, 6
... communication hole, 7 ... discharge pipe, 8 ... dry well, 9 ... wet well, 10 ... support structure unit, 11 ... protective structure, 12
… Support, 13… Piping cable, 14… Containment equipment,
15 ... jet, 16 ... steel plate, 17 ... horizontal beam.

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】 沸騰水型原子炉格納容器内に立設された
ペデスタルの連通孔内に支持構造ユニットを設け、この
支持構造ユニット上に上部ドライウェル内に突出して防
護構造体を設置してなることを特徴とする原子炉格納容
器内の防護装置。
1. A support structure unit is provided in a communication hole of a pedestal erected in a boiling water reactor containment vessel, and a protection structure is provided on the support structure unit so as to protrude into an upper dry well. A protection device in a containment vessel, characterized in that:
JP3173822A 1991-07-15 1991-07-15 Protective equipment inside the PCV Expired - Fee Related JP2635856B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3173822A JP2635856B2 (en) 1991-07-15 1991-07-15 Protective equipment inside the PCV

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3173822A JP2635856B2 (en) 1991-07-15 1991-07-15 Protective equipment inside the PCV

Publications (2)

Publication Number Publication Date
JPH0519085A JPH0519085A (en) 1993-01-26
JP2635856B2 true JP2635856B2 (en) 1997-07-30

Family

ID=15967796

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3173822A Expired - Fee Related JP2635856B2 (en) 1991-07-15 1991-07-15 Protective equipment inside the PCV

Country Status (1)

Country Link
JP (1) JP2635856B2 (en)

Also Published As

Publication number Publication date
JPH0519085A (en) 1993-01-26

Similar Documents

Publication Publication Date Title
US3168445A (en) Safety equipment for nuclear powerreactor plants
US10290379B2 (en) Passive containment cooling and filtered venting system, and nuclear power plant
JPH08511102A (en) Device for collecting and cooling core melt and method thereof
KR930011015B1 (en) Fission product scrubbing system
JP2635856B2 (en) Protective equipment inside the PCV
JP2007163204A (en) Reactor building and method for renovating it
JP2016044483A (en) Building
JP2004061276A (en) Reactor containment vessel
JPH07128485A (en) Fuel pool equipment
JPH06222179A (en) Building for nuclear reactor
US5232308A (en) Emergency spill basin
JPH0334835B2 (en)
JPS6017076B2 (en) nuclear fuel storage device
RU2107342C1 (en) Shielding system of water-moderated reactor unit containment
CN212210025U (en) Power station orifice protection piece
JPS63221291A (en) Nuclear reactor facility
JP2635829B2 (en) Support structure inside the PCV
JP2017203743A (en) Nuclear reactor facility and filter vent system thereof
JPH06185077A (en) Prevention device for preventing rise of groundwater level around basement
TWI352361B (en) Trash rack arrangement for drywell connecting vent
JP2002168985A (en) Reactor container
JPS62215893A (en) Spent fuel storage pool
US5415197A (en) Equalizing reservoir configuration, especially for cooling circuits in nuclear power stations
JPS642231B2 (en)
JPS6330785A (en) Reactor pressure-vessel support structure

Legal Events

Date Code Title Description
S111 Request for change of ownership or part of ownership

Free format text: JAPANESE INTERMEDIATE CODE: R313115

R360 Written notification for declining of transfer of rights

Free format text: JAPANESE INTERMEDIATE CODE: R360

R350 Written notification of registration of transfer

Free format text: JAPANESE INTERMEDIATE CODE: R350

LAPS Cancellation because of no payment of annual fees