JPS6325312B2 - - Google Patents
Info
- Publication number
- JPS6325312B2 JPS6325312B2 JP57063417A JP6341782A JPS6325312B2 JP S6325312 B2 JPS6325312 B2 JP S6325312B2 JP 57063417 A JP57063417 A JP 57063417A JP 6341782 A JP6341782 A JP 6341782A JP S6325312 B2 JPS6325312 B2 JP S6325312B2
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- reactor
- building
- shielding wall
- stabilizer
- 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
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
- Buildings Adapted To Withstand Abnormal External Influences (AREA)
Description
【発明の詳細な説明】
本発明は、原子炉建屋の内部構造に関するもの
である。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to the internal structure of a nuclear reactor building.
第１図に従来型原子炉建屋の内部構造を示す。
同図において、１は原子炉建屋全体を総括的に示
しており、２は原子炉建屋遮へい壁である。３は
原子炉格納容器、４は格納容器ドライウエル、５
はドライウエル４内に配置された原子炉圧力容
器、６は圧力容器５を支持する圧力容器ペデスタ
ル、７はペデスタル６上に位置するガンマー線遮
へい体であり、８はサプレツシヨンプール、９は
プール水、１０は格納容器ドライウエル４とサプ
レツシヨンプール８とを接続するベント管、１１
は建屋１の基礎マツトである。１２は圧力容器５
とガンマー線遮へい体７との間に位置する原子炉
圧力容器スタビライザ、１３はガンマー線遮へい
体７と格納容器３との間に位置する第一の原子炉
格納容器スタビライザ、１４は格納容器３と建屋
遮へい壁２との間に位置する第二の原子炉格納容
器スタビライザを示す。 Figure 1 shows the internal structure of a conventional reactor building.
In the figure, 1 generally shows the entire reactor building, and 2 is a shielding wall for the reactor building. 3 is the reactor containment vessel, 4 is the containment vessel dry well, 5
6 is a pressure vessel pedestal that supports the pressure vessel 5; 7 is a gamma ray shield located on the pedestal 6; 8 is a suppression pool; 9 is a suppression pool; Pool water, 10 is a vent pipe connecting the containment vessel dry well 4 and the suppression pool 8, 11
is the foundation pine of building 1. 12 is the pressure vessel 5
13 is a first reactor containment vessel stabilizer located between the gamma ray shield 7 and the containment vessel 3; 14 is a first reactor containment vessel stabilizer located between the gamma ray shield 7 and the containment vessel 3; The second reactor containment vessel stabilizer located between the building shielding wall 2 is shown.
従来型原子炉建屋の内部構造は以上のとおりで
あるが、この構造によれば、第２図および第３図
に示すように、原子炉建屋遮へい壁２と格納容器
３との間のギヤツプＧが、約50mmと非常に小さ
い。したがつて、上記建屋遮へい壁２の立上げ
は、格納容器３の建設、さらには当該格納容器３
の耐圧試験後におこなわれる結果、建屋１の構築
完了までに長期間を必要としていた。 The internal structure of the conventional reactor building is as described above. According to this structure, as shown in FIGS. 2 and 3, the gap G between the reactor building shielding wall 2 and the containment vessel 3 is However, it is very small at about 50mm. Therefore, the erection of the building shielding wall 2 involves the construction of the containment vessel 3, and also the construction of the containment vessel 3.
As a result, it took a long time to complete the construction of Building 1.
以上の点を考慮して、原子炉格納容器と建屋遮
へい壁との間のスペースを広くとることにより、
上記両構造物を同時進行的に立上げるようにした
原子炉建屋が最近提案されるに至つた。 Considering the above points, by widening the space between the reactor containment vessel and the building shielding wall,
Recently, a nuclear reactor building has been proposed in which both of the above structures are erected simultaneously.
本発明は、上記した構造の原子炉建屋、すなわ
ち、原子炉格納容器と建屋遮へい壁との間のスペ
ースを広くとつた構造の原子炉建屋にさらに改良
を加えたものであり、その目的とするところは、
格納容器と建屋遮へい壁との間のスペースを有効
に利用することにより、格納容器の耐震性をより
一層向上させるようにした点にある。 The present invention is a reactor building with the above-described structure, that is, a reactor building with a structure in which the space between the reactor containment vessel and the building shielding wall is widened, and its purpose is to further improve the reactor building. However,
The seismic resistance of the containment vessel is further improved by effectively utilizing the space between the containment vessel and the building shielding wall.
上記目的を達成するため、本発明は、原子炉格
納容器と原子炉建屋遮へい壁との間に、これら両
構築物を同時進行的に立上げることのできるスペ
ースを確保した構造の原子炉建屋において、一端
を建屋遮へい壁に取付け、他端を格納容器に取付
けた原子炉格納容器スタビライザを、上記スペー
ス部分に配置し、さらに上記格納容器スタビライ
ザを、建屋遮へい壁の上部床で支持してなること
を特徴とするものである。 In order to achieve the above object, the present invention provides a reactor building having a structure in which a space is secured between the reactor containment vessel and the reactor building shielding wall in which both these structures can be set up simultaneously. A reactor containment vessel stabilizer with one end attached to the building shielding wall and the other end attached to the containment vessel is arranged in the space, and the containment vessel stabilizer is further supported by the upper floor of the building shielding wall. This is a characteristic feature.
以下、本発明を、第４図ないし第６図の一実施
例にもとづいて説明すると、第４図は本発明に係
る原子炉建屋の内部構造説明図、第５図は第４図
の一部を拡大して示す図、第６図は第５図のＢ−
Ｂ断面図を示し、第１図ないし第３図と同一部分
には同一符号を付してその説明を省略する。符号
Ｓは原子炉建屋遮へい壁２と原子炉格納容器３と
の間に確保したスペースで、このスペースＳは、
上記建屋遮へい壁２と格納容器３とを同時進行的
に立上げるに十分な間隔、すなわち、建屋遮へい
壁２のコンクリート打設用型枠の設置スペース
と、格納容器３の工事用スペースとを考慮して、
800mm程度とするのがよい。１４′は建屋遮へい壁
２と格納容器３との間のスペースＳ部分に位置す
る原子炉格納容器スタビライザで、本発明におい
て、この格納容器スタビライザ１４′の上部には、
第５図に示すように、耐震サポート１５の一端が
取付けられており、耐震サポート１５の他端は、
建屋遮へい壁２の上部床２ａに取付けられてい
る。また、第６図に示すように、格納容器スタビ
ライザ１４′の側部には、耐震サポート１６の一
端が取付けられており、耐震サポート１６の他端
は、建屋遮へい壁２に取付けられている。１７は
原子炉格納容器廻りの付帯設備、たとえば格納容
器３の頂部付近に配置されている配管１８を支持
する付帯設備支持用ブラケツトで、このブラケツ
ト１７は、格納容器スタビライザ１４′に取付け
られている。すなわち、図示実施例において、格
納容器スタビライザ１４′は、格納容器廻りの付
帯設備支持部材としての機能をも兼ね備えてお
り、建屋遮へい壁２と格納容器３との間のスペー
スＳ部分に位置する配管１８の類は、上記格納容
器スタビライザ１４′を利用して支持され、格納
容器廻りの付帯設備支持部材を新たに設けなくて
も、格納容器３の頂部付近に位置する付帯設備を
確固と支持することができる。 Hereinafter, the present invention will be explained based on an embodiment shown in FIGS. 4 to 6. FIG. 4 is an explanatory diagram of the internal structure of the reactor building according to the present invention, and FIG. 5 is a part of FIG. 4. Figure 6 is an enlarged view of Figure 5.
A cross-sectional view is shown in FIG. The symbol S is the space secured between the reactor building shielding wall 2 and the reactor containment vessel 3, and this space S is
Sufficient spacing is required to simultaneously erect the building shielding wall 2 and the containment vessel 3, that is, the installation space for concrete pouring formwork for the building shielding wall 2 and the construction space for the containment vessel 3. do,
It is best to set it to around 800mm. Reference numeral 14' denotes a reactor containment vessel stabilizer located in a space S portion between the building shielding wall 2 and the containment vessel 3. In the present invention, the upper part of this containment vessel stabilizer 14' includes:
As shown in FIG. 5, one end of the seismic support 15 is attached, and the other end of the seismic support 15 is
It is attached to the upper floor 2a of the building shielding wall 2. Further, as shown in FIG. 6, one end of an earthquake-resistant support 16 is attached to the side of the containment vessel stabilizer 14', and the other end of the earthquake-resistant support 16 is attached to the building shielding wall 2. Reference numeral 17 denotes a bracket for supporting auxiliary equipment around the reactor containment vessel, for example, a pipe 18 placed near the top of the containment vessel 3. This bracket 17 is attached to the containment vessel stabilizer 14'. . That is, in the illustrated embodiment, the containment vessel stabilizer 14' also has the function of a support member for incidental equipment around the containment vessel, and the containment vessel stabilizer 14' also serves as a supporting member for the incidental equipment around the containment vessel, and the stabilizer 14' serves as a support member for supporting the incidental equipment around the containment vessel. Type 18 is supported using the containment vessel stabilizer 14' and firmly supports the incidental equipment located near the top of the containment vessel 3 without the need to newly provide ancillary equipment support members around the containment vessel. be able to.
本発明は以上のごとき構成よりなり、本発明に
よれば、原子炉格納容器３と原子炉建屋遮へい壁
２とを同時進行的に立上げ、原子炉プラントの建
設工期を短縮し得ることは勿論、格納容器３と建
屋遮へい壁２との間のスペースＳ部分に位置する
原子炉格納容器スタビライザ１４′は、建屋遮へ
い壁２のみならず、当該建屋遮へい壁２の上部床
２ａでも支持されているから、地震発生に際し、
格納容器３に加えられる水平方向の地震力は、格
納容器スタビライザ１４′および耐震サポート１
６を介して原子炉建屋遮へい壁２に伝えられる。
また、格納容器３に加えられる垂直方向の地震力
は、格納容器スタビライザ１４′および耐震サポ
ート１５を介して建屋遮へい壁２の上部床２ａに
伝えられ、水平、垂直いずれの方向の地震力に対
しても、原子炉格納容器３の安定性は良好に維持
される。 The present invention has the above configuration, and according to the present invention, the reactor containment vessel 3 and the reactor building shielding wall 2 can be erected simultaneously, and the construction period of the nuclear reactor plant can of course be shortened. , the reactor containment vessel stabilizer 14' located in the space S between the containment vessel 3 and the building shielding wall 2 is supported not only by the building shielding wall 2 but also by the upper floor 2a of the building shielding wall 2. Therefore, when an earthquake occurs,
The horizontal seismic force applied to the containment vessel 3 is caused by the containment vessel stabilizer 14' and seismic support 1.
6 to the reactor building shielding wall 2.
In addition, the vertical seismic force applied to the containment vessel 3 is transmitted to the upper floor 2a of the building shielding wall 2 via the containment vessel stabilizer 14' and the seismic support 15, and the seismic force in either the horizontal or vertical direction is transmitted to the upper floor 2a of the building shielding wall 2. However, the stability of the reactor containment vessel 3 is maintained well.
以上詳述したように本発明によれば、原子炉格
納容器３と原子炉建屋遮へい壁２との間のスペー
スＳを有効に利用することにより、格納容器３の
耐震性向上化をはかることのできる、改良された
原子炉建屋を得ることができる。 As detailed above, according to the present invention, it is possible to improve the earthquake resistance of the containment vessel 3 by effectively utilizing the space S between the reactor containment vessel 3 and the reactor building shielding wall 2. It is possible to obtain an improved reactor building.
第１図は従来型原子炉建屋の内部構造説明図、
第２図は第１図の一部を拡大して示す図、第３図
は第２図のＡ−Ａ断面図、第４図は本発明に係る
原子炉建屋の一実施例を示す内部構造説明図、第
５図は第４図の一部を拡大して示す図、第６図は
第５図のＢ−Ｂ断面図である。
１……原子炉建屋、２……原子炉建屋遮へい
壁、２ａ……原子炉建屋遮へい壁２の上部床、３
……原子炉格納容器、１４′……原子炉格納容器
スタビライザ、１５および１６……耐震サポー
ト、１７……原子炉格納容器廻りの付帯設備支持
用ブラケツト、１８……配管。
Figure 1 is an explanatory diagram of the internal structure of a conventional reactor building.
FIG. 2 is an enlarged view of a part of FIG. 1, FIG. 3 is a sectional view taken along line A-A in FIG. 2, and FIG. 4 is an internal structure showing an embodiment of the reactor building according to the present invention. 5 is an enlarged view of a part of FIG. 4, and FIG. 6 is a sectional view taken along line BB in FIG. 5. 1... Reactor building, 2... Reactor building shielding wall, 2a... Upper floor of reactor building shielding wall 2, 3
...Reactor containment vessel, 14'...Reactor containment vessel stabilizer, 15 and 16...Earthquake support, 17...Bracket for supporting incidental equipment around the reactor containment vessel, 18...Piping.
Claims (1)
に、これら両構築物を同時進行的に立上げること
のできるスペースを確保した構造の原子炉建屋に
おいて、一端を建屋遮へい壁に取付け、他端を格
納容器に取付けた原子炉格納容器スタビライザ
を、上記スペース部分に配置し、さらに上記格納
容器スタビライザを、建屋遮へい壁の上部床で支
持してなることを特徴とする原子炉建屋。 ２ 原子炉格納容器と原子炉建屋遮へい壁との間
に位置する原子炉格納容器スタビライザは、原子
炉格納容器廻りの付帯設備支持部材を兼ねている
特許請求の範囲第１項記載の原子炉建屋。[Scope of Claims] 1. In a reactor building having a structure in which a space is secured between the reactor containment vessel and the reactor building shielding wall so that both these structures can be set up simultaneously, one end of the reactor building is shielded by the building shielding wall. A reactor containment vessel stabilizer attached to a wall and the other end attached to a containment vessel is disposed in the space, and the containment vessel stabilizer is further supported by an upper floor of a building shielding wall. Furnace building. 2. The reactor building according to claim 1, wherein the reactor containment vessel stabilizer located between the reactor containment vessel and the reactor building shielding wall also serves as ancillary equipment support member around the reactor containment vessel. .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57063417A JPS58179393A (en) | 1982-04-15 | 1982-04-15 | Reactor building |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57063417A JPS58179393A (en) | 1982-04-15 | 1982-04-15 | Reactor building |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58179393A JPS58179393A (en) | 1983-10-20 |
| JPS6325312B2 true JPS6325312B2 (en) | 1988-05-25 |
Family
ID=13228688
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57063417A Granted JPS58179393A (en) | 1982-04-15 | 1982-04-15 | Reactor building |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58179393A (en) |
-
1982
- 1982-04-15 JP JP57063417A patent/JPS58179393A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS58179393A (en) | 1983-10-20 |
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