JPH0519085A - Protective device inside containment vessel - Google Patents
Protective device inside containment vesselInfo
- Publication number
- JPH0519085A JPH0519085A JP3173822A JP17382291A JPH0519085A JP H0519085 A JPH0519085 A JP H0519085A JP 3173822 A JP3173822 A JP 3173822A JP 17382291 A JP17382291 A JP 17382291A JP H0519085 A JPH0519085 A JP H0519085A
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- communication hole
- reactor containment
- protective structure
- dry well
- 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.)
- Granted
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
(57)【要約】
【目的】沸騰水型原子炉格納容器内に立設されたペデス
タルの連通孔が事故時などに落下物によって閉塞されな
いようにして原子炉格納容器の機能が損なわれないよう
にする。
【構成】原子炉格納容器1内に立設されたペデスタル2
の連通孔6内に支持構造ユニット10を設け、この支持構
造ユニット10上に防護構造体11を設置する。防護構造体
11の上部は上部ドライウェル8a内に突出している。
(57) [Summary] [Purpose] The communication hole of the pedestal erected in the boiling water reactor containment vessel should not be blocked by falling objects in case of an accident so that the function of the reactor containment vessel is not impaired. To [Structure] Pedestal 2 installed upright in containment vessel 1
The support structure unit 10 is provided in the communication hole 6 of the above, and the protective structure 11 is installed on the support structure unit 10. Protective structure
The upper part of 11 projects into the upper dry well 8a.
Description
【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 the inside of a communication hole of a pedestal installed upright in the reactor containment vessel of a boiling water reactor from being blocked by a fallen object, for example, when a pipe breaks. Concerning the protective device inside the 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 The reactor containment vessel of an improved boiling water reactor has a prismatic shape as shown in FIG. 3, and in this reactor containment vessel 1, a cylindrical pedestal 2 is provided at the center.
And the reactor pressure vessel 3 erected on this pedestal 2.
And a suppression chamber 4 is provided at the bottom.
【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。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 to support the reactor pressure vessel 3. It is provided above and below the pedestal 2. Further, 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 connected by a communication hole 6. In the wet well 9, a discharge pipe 7 that is immersed in the suppression chamber 4 is provided.
【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 pipe breakage in the reactor containment vessel 1 does not directly act on the communication hole 6 which communicates with the vent pipe 5 of the improved boiling water reactor. However, there is still a possibility that the equipment inside the reactor containment vessel 1 damaged by this 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。Communication hole 6 of improved boiling water reactor containment vessel
The peripheral portion is extremely narrow due to the arrangement equipment in the reactor containment vessel, and it is very difficult to install a protective structure in the communication hole 6. Further, the pipes, cables, ducts, etc. connecting the upper dry well 8a to the lower dry well 8b are inserted through the communication hole 6,
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 the energy released when the built-in pipe is broken. Usually upper dry well 8
The 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, when pipe breakage is assumed in the upper dry well 8a and the communication hole 6 is blocked due to this effect, the energy absorbing space is limited to the upper dry well 8a, which is disadvantageous in terms of 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。The present invention has been made to solve the above problems, and it is an object of the present invention to provide a protective device in a reactor containment vessel capable of avoiding the blockage of the communication hole even in the case of an expected 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 boiling water reactor containment vessel, and the support structure unit is projected onto the upper dry well. It is characterized by installing a protective structure.
【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。[Operation] When the communication hole is closed due to the fall of the equipment inside the reactor containment vessel that is damaged by the pipe breakage jet in the reactor containment vessel, the vapor from the pipe breakage port is led to the suppression pool and condensed to reduce the pressure. It is difficult to secure the function of the reactor containment vessel, but this function is secured by providing a protective structure. Further, by integrating the protective structure with the support structure unit, it is possible to significantly reduce the work of installing the protective structure on site. When installing the protective structure, the structure of the protective structure can be simplified by arranging it so as to avoid the pipe breakage 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 for a reactor 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.
The internal structure is the same as that shown in FIG. Also,
FIG. 2 is an enlarged perspective view of the main part of FIG. That is, in the reactor containment vessel 1 having the upper dry well 8a and the lower dry well 8b, and having the communication hole 6 that communicates the both dry wells 8a and 8b, it is provided in the pedestal 2 as shown in FIG. A step-like support structure unit 10 is provided in the communication hole 6, and a protective structure 11 is installed on the support structure unit 10. The protective structure 11 is configured so that it can be used as a supporting 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 is at an arrangement level that is not affected by the facility 14 inside the containment vessel and the pipe breaking jet 15. ing. As shown in FIG. 2, the support structure unit 10 has a steel plate 16 and a horizontal beam 17 between itself and the protective structure 11, and the tip of the protective structure 11 has a communication hole on the side of the upper dry well 8a. 6 is projected 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。Therefore, according to the above-mentioned embodiment, it is possible to avoid the blockage of the communication hole 6 in the event of an expected accident. That is, since the entrance of the communication hole 6 is a narrow place, the protective structure 11 projecting the communication hole 6 is fixed by using a part of the structural material inside the reactor containment vessel already installed. Has been done. The protective structure 11 ensures the pressure reducing function of the reactor containment vessel 1, the structure can be extremely simplified, and the on-site installation work can be reduced. By forming the platform with the steel plate 16 on the upper surface of the protective structure 11, it becomes easy to access the installation installed above the communication hole 6. Also a protective structure
When installing 11, the protection structure 11 can be simplified by avoiding the pipe breaking 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 the protective structure, the function of reducing the pressure of the reactor containment vessel can be secured and the structure thereof can be simplified, and in addition, the on-site installation work can be reduced. You can
【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 vertical cross-sectional view showing an embodiment of a protective device in a reactor 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.
【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 vertical cross-sectional view schematically showing the inside of a conventional reactor containment vessel.
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。1 ... Reactor 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… Plumbing cable, 14… PCV equipment,
15… Jet, 16… Steel plate, 17… Horizontal beam.
Claims (1)
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。Claim: What is claimed is: 1. A support structure unit is provided in a communication hole of a pedestal provided upright in a boiling water reactor containment vessel, and the support structure unit is protruded into the upper dry well for protection. A protective device in a containment vessel characterized by having a structure installed.
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 true JPH0519085A (en) | 1993-01-26 |
| JP2635856B2 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) |
-
1991
- 1991-07-15 JP JP3173822A patent/JP2635856B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JP2635856B2 (en) | 1997-07-30 |
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