JP3146050B2 - Reactor containment vessel - Google Patents
Reactor containment vesselInfo
- Publication number
- JP3146050B2 JP3146050B2 JP02964392A JP2964392A JP3146050B2 JP 3146050 B2 JP3146050 B2 JP 3146050B2 JP 02964392 A JP02964392 A JP 02964392A JP 2964392 A JP2964392 A JP 2964392A JP 3146050 B2 JP3146050 B2 JP 3146050B2
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- cable
- isi
- reactor
- reactor containment
- 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
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
-
- 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
- Installation Of Indoor Wiring (AREA)
Description
【0001】[0001]
【産業上の利用分野】本発明は沸騰水型原子炉の鉄筋コ
ンクリート製原子炉格納容器に係り、特に供用検査装置
等のケーブル架設等に好適な原子炉格納容器に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reinforced concrete reactor containment vessel of a boiling water reactor, and more particularly to a reactor containment vessel suitable for erection of a cable for a service inspection device or the like.
【0002】[0002]
【従来の技術】いわゆる改良型の沸騰水型原子炉では、
例えば図2に示すように、原子炉格納容器1が鉄筋コン
クリートにより円筒形に構成されている。2. Description of the Related Art In a so-called improved boiling water reactor,
For example, as shown in FIG. 2, the reactor containment vessel 1 is formed of a reinforced concrete into a cylindrical shape.
【0003】この原子炉格納容器1の中心部に設置され
た原子炉圧力容器2の近傍に供用検査装置(ISI装
置)3が取付けられ、このISI装置3から引出された
供用検査用電気ケーブル(ISIケーブル)4が、上部
ドライウェル5上方のアクセススペース6を横断する状
態で引出され、縦壁7を貫通した後その縦壁7の外側で
上方に折曲されて、トップスラブ8の外径側を貫通して
上方の供用検査室(ISI室)9まで導かれている。A service inspection device (ISI device) 3 is mounted near a reactor pressure vessel 2 installed at the center of the reactor containment vessel 1, and a service inspection electrical cable (ISI device) drawn from the ISI device 3 is used. An ISI cable 4 is drawn out across the access space 6 above the upper drywell 5, penetrates the vertical wall 7, is bent upward outside the vertical wall 7, and has an outer diameter of the top slab 8. It is guided to the upper service inspection room (ISI room) 9 through the side.
【0004】[0004]
【発明が解決しようとする課題】上述した構成の原子炉
格納容器においては、ISIケーブル4がアクセススペ
ース6を横断して縦壁7内の貫通部10まで延在してい
るため、アクセス性が低下する可能性がある。また、I
SIケーブル4がアクセス通路部を避ける配置となるよ
うに引回すと、原子炉格納容器1内での配線の引回しが
長くなり、作業性を低下させる等の不具合が生じる。In the reactor containment vessel having the above-described structure, the ISI cable 4 extends to the penetrating portion 10 in the vertical wall 7 across the access space 6, so that accessibility is improved. May decrease. Also, I
If the SI cable 4 is routed so as to avoid the access passage portion, the length of the wiring in the reactor containment vessel 1 becomes long, which causes problems such as a reduction in workability.
【0005】なお、同様のことは、ケーブル被覆管その
他の配管引回し等についてもいえることである。[0005] The same can be said for a cable cladding tube and other piping routes.
【0006】本発明はこのような事情に鑑みてなされた
もので、原子炉格納容器内でのケーブルまたは配管の引
回し長さの短縮が図れるとともに、それらがアクセスス
ペース内で邪魔になることを防止して格納容器内の作業
性およびアクセス性等の向上も図れる原子炉格納容器を
提供することを目的とする。[0006] The present invention has been made in view of such circumstances, and it is possible to reduce the length of the cable or piping routed inside the reactor containment vessel and to prevent them from obstructing the access space. It is an object of the present invention to provide a reactor containment vessel that can be prevented from improving the workability and accessibility in the containment vessel.
【0007】[0007]
【課題を解決するための手段】前記の目的を達成するた
め、本発明は、鉄筋コンクリートにより円筒形に構成さ
れた原子炉格納容器であって、原子炉圧力容器側から引
出されるケーブルまたは配管を上部ドライウェルを介し
て、トップスラブの、上部ドライウェル内アクセススペ
ースよりも原子炉圧力容器側に位置する部位に上下方向
に沿う貫通孔を開け、この貫通孔を通して前記ケーブル
または配管を前記トップスラブ上方の室に導いたことを
特徴とする。SUMMARY OF THE INVENTION In order to achieve the above object, the present invention relates to a nuclear reactor containment vessel made of reinforced concrete and having a cylindrical shape. Through a top dry slab, a through hole is formed in the top slab in a portion of the top slab located closer to the reactor pressure vessel than the access space in the upper dry well, and the cable or piping is connected to the top slab through the through hole. It is characterized by being led to the upper chamber.
【0008】[0008]
【作用】本発明によると、原子炉圧力容器側から引出さ
れるケーブルがアクセススペースの手前で上方に折曲
し、トップスラブを貫通する構造であるから、例えば供
用検査ケーブル等の架設について、アクセススペースを
横断する従来構造のような面倒な引回しを行わなくて
も、アクセス性を阻害することがない。したがって格納
容器内の作業性およびアクセス性等の向上が図れるよう
になる。According to the present invention, the cable drawn from the reactor pressure vessel side is bent upward in front of the access space and penetrates the top slab. Accessability is not hindered even if troublesome routing such as the conventional structure that crosses a space is not performed. Therefore, the workability and accessibility in the storage container can be improved.
【0009】しかも、ケーブルが原子炉圧力容器側から
近い位置で上方に導かれるので、従来構造に比較して、
原子炉格納容器内で引回されるケーブル長さも短縮でき
るようになる。Moreover, since the cable is guided upward at a position close to the reactor pressure vessel side, compared with the conventional structure,
The length of the cable routed in the containment vessel can also be reduced.
【0010】[0010]
【実施例】以下、本発明の一実施例を図1を参照して説
明する。An embodiment of the present invention will be described below with reference to FIG.
【0011】本実施例では、上部ドライウェル内のIS
I装置とISI室とを結ぶケーブルの架設について適用
したものである。In this embodiment, the IS in the upper dry well is
This is applied to the construction of a cable connecting the I apparatus and the ISI room.
【0012】すなわち図1に示すように、本実施例の原
子炉格納容器11は、鉄筋コンクリートにより円筒形に
構成され内部壁は縦横方向に配設されている。この原子
炉格納容器11の中心部に設置された原子炉圧力容器1
2の近傍にISI装置13が取付けられている。That is, as shown in FIG. 1, the containment vessel 11 of the present embodiment is formed in a cylindrical shape by reinforced concrete, and the inner walls are arranged in the vertical and horizontal directions. The reactor pressure vessel 1 installed at the center of the containment vessel 11
2, an ISI device 13 is attached.
【0013】ISI装置13から引出されたISIケー
ブル14は、上部ドライウェル15上方のアクセススペ
ース16に向って引出されているが、そのアクセススペ
ース16の手前で上方に折曲している。The ISI cable 14 drawn out of the ISI device 13 is drawn out toward an access space 16 above the upper dry well 15 and is bent upward just before the access space 16.
【0014】すなわち、トップスラブ17の、アクセス
スペース16よりも原子炉圧力容器12側に位置する部
位に、上下方向に沿う貫通孔18が開けられ、この貫通
孔18を通してISIケーブル14がISI室19に導
かれている。That is, a through hole 18 is formed in the top slab 17 at a position located closer to the reactor pressure vessel 12 than the access space 16, and the ISI cable 14 is passed through the through hole 18 through the ISI chamber 19. Is led to.
【0015】このような構成によると、原子炉圧力容器
12側から引出されるISIケーブル14がアクセスス
ペース16の手前で上方に折曲し、トップスラブ17を
貫通する構造であるから、供用検査ケーブル14の架設
について、アクセススペース16を横断する従来構造の
ような面倒な引回しを行わなくても、格納容器内の作業
性およびアクセス性を阻害することがない。According to such a configuration, the ISI cable 14 drawn from the reactor pressure vessel 12 is bent upward in front of the access space 16 and penetrates through the top slab 17, so that the service inspection cable is used. Regarding the erection of 14, the workability and accessibility in the containment vessel are not hindered even if the troublesome routing like the conventional structure crossing the access space 16 is not performed.
【0016】しかも、ISIケーブル14が原子炉圧力
容器12側から近い位置で上方に導かれるので、従来構
造に比較して、ISIケーブル14の長さも短縮できる
ようになる。Moreover, since the ISI cable 14 is guided upward at a position close to the reactor pressure vessel 12, the length of the ISI cable 14 can be reduced as compared with the conventional structure.
【0017】なお、以上の実施例では本発明をISIケ
ーブルの架設について適用したが、本発明はISIケー
ブル以外の種々のケーブル、または各種配管の架設等に
ついても適用できることは勿論である。In the above embodiment, the present invention is applied to the installation of an ISI cable. However, it goes without saying that the present invention can be applied to the installation of various cables other than the ISI cable or the installation of various pipes.
【0018】[0018]
【発明の効果】以上のように本発明によれば、鉄筋コン
クリート製原子炉格納容器のトップスラブに貫通部を設
けることにより、格納容器内のケーブルまたは配管の短
縮が図れるとともに、格納容器内の作業性およびアクセ
ス性の向上が図れ、ひいては被曝低減等にも大きい効果
が奏される。As described above, according to the present invention, by providing a penetrating portion in the top slab of the reinforced concrete containment vessel, the cables or pipes in the containment vessel can be shortened and the work in the containment vessel can be shortened. Thus, it is possible to improve the accessibility and the accessibility, and also to have a great effect in reducing the exposure.
【図1】本発明の一実施例を示す断面図。FIG. 1 is a sectional view showing an embodiment of the present invention.
【図2】従来例を示す断面図。FIG. 2 is a sectional view showing a conventional example.
11 原子炉格納容器 12 原子炉圧力容器 13 ISI装置(供用検査装置) 14 ISIケーブル 15 上部ドライウェル 16 アクセススペース 17 トップスラブ 18 貫通孔 19 ISI室 11 Reactor Containment Vessel 12 Reactor Pressure Vessel 13 ISI Device (In-Service Inspection Device) 14 ISI Cable 15 Upper Dry Well 16 Access Space 17 Top Slab 18 Through Hole 19 ISI Room
Claims (1)
れた原子炉格納容器であって、原子炉圧力容器側から引
出されるケーブルまたは配管を上部ドライウェルを介し
て、トップスラブの、上部ドライウェル内アクセススペ
ースよりも原子炉圧力容器側に位置する部位に上下方向
に沿う貫通孔を開け、この貫通孔を通して前記ケーブル
または配管を前記トップスラブ上方の室に導いたことを
特徴とする原子炉格納容器。1. A reactor containment vessel formed of reinforced concrete in a cylindrical shape, wherein a cable or a pipe drawn from a reactor pressure vessel side is accessed through an upper dry well of a top slab in the upper dry well. A reactor containment vessel characterized in that a vertical through-hole is formed in a portion located on the side of the reactor pressure vessel relative to a space, and the cable or pipe is led to a chamber above the top slab through the through-hole.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP02964392A JP3146050B2 (en) | 1992-02-17 | 1992-02-17 | Reactor containment vessel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP02964392A JP3146050B2 (en) | 1992-02-17 | 1992-02-17 | Reactor containment vessel |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH05223976A JPH05223976A (en) | 1993-09-03 |
JP3146050B2 true JP3146050B2 (en) | 2001-03-12 |
Family
ID=12281776
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP02964392A Expired - Fee Related JP3146050B2 (en) | 1992-02-17 | 1992-02-17 | Reactor containment vessel |
Country Status (1)
Country | Link |
---|---|
JP (1) | JP3146050B2 (en) |
-
1992
- 1992-02-17 JP JP02964392A patent/JP3146050B2/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
JPH05223976A (en) | 1993-09-03 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
LAPS | Cancellation because of no payment of annual fees |