JPS59133491A - Discharging tube device for main steam escape safety valve - Google Patents
Discharging tube device for main steam escape safety valveInfo
- Publication number
- JPS59133491A JPS59133491A JP58007293A JP729383A JPS59133491A JP S59133491 A JPS59133491 A JP S59133491A JP 58007293 A JP58007293 A JP 58007293A JP 729383 A JP729383 A JP 729383A JP S59133491 A JPS59133491 A JP S59133491A
- Authority
- JP
- Japan
- Prior art keywords
- safety valve
- main steam
- steam
- exhaust pipe
- containment vessel
- 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.)
- Pending
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は逃し安全弁排気管装置に於いて、蒸気放出部の
改善によシ、ドライウェル壁に加わる気泡脈動荷重を低
減し、かつ、サプレッションプール内の配置をコンパク
トにすることを可能とした主蒸気逃し安全弁排気管装置
に関する。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention provides a relief safety valve exhaust pipe device that improves the steam release section, reduces the bubble pulsating load applied to the dry well wall, and improves the suppression pool. This invention relates to a main steam relief safety valve exhaust pipe device that allows for a compact internal arrangement.
第1図は地下式原子力発電所原子炉空洞の断面図、第2
図は第1図のA−A断面、第3図は主蒸気逃し安全弁排
気管装置廻りを示す図、第4図は主蒸気逃し安全弁排気
管の蒸気放出導管部詳細図を示す。Figure 1 is a cross-sectional view of the reactor cavity of an underground nuclear power plant, Figure 2
The figure shows a cross section taken along the line AA in FIG. 1, FIG. 3 shows the main steam safety relief valve exhaust pipe device and its surroundings, and FIG. 4 shows a detailed view of the steam release conduit section of the main steam safety safety valve exhaust pipe.
原子炉6の異常な圧力上昇を防止するために主蒸気管に
逃し安全弁が設置されておシ、その排気管10はサプレ
ッションプール4の中までのび、蒸気放出導管14を介
して蒸気を水中に放出するようになっている。In order to prevent an abnormal pressure rise in the reactor 6, a relief safety valve is installed in the main steam pipe, and its exhaust pipe 10 extends into the suppression pool 4, and the steam is discharged into the water via a steam release conduit 14. It is designed to be released.
蒸気放出導管14としては第4図に示すように多数の開
口を有し、水平方向に向い合っている。As shown in FIG. 4, the steam discharge conduit 14 has a large number of openings, which face each other in the horizontal direction.
この様な構造では、蒸気凝縮時に於ける気泡圧力脈動が
大きいという欠点を有している。This structure has the disadvantage that bubble pressure pulsations are large during vapor condensation.
プラント寿命中に於ける逃し安全弁の作動による繰り返
し振動は4000〜5000回となシ、気泡圧力脈動に
より、水面下の構造材の設計条件は著しく苛酷なものと
なる。このような荷重条件を和らげ、構造物の健全性に
対する余裕を増すとともに、設計条件を低減する必要が
ある。The repeated vibrations due to the activation of the relief safety valve during the life of the plant are 4,000 to 5,000 times, and the design conditions for the structural materials below the water surface are extremely severe due to the bubble pressure pulsations. It is necessary to soften such load conditions, increase margin for structural integrity, and reduce design conditions.
本発明は、上記の持つ問題点をなくし、プール水中の構
造材に加わる気泡脈動荷重を低減することによシ、プー
ル水中の構造材の設計荷重を低減することを可能とした
主蒸気逃し安全弁排気管装置を提供することにある。The present invention eliminates the above-mentioned problems and reduces the bubble pulsating load applied to the structural members in the pool, thereby reducing the design load of the structural members in the pool. The purpose of the present invention is to provide an exhaust pipe device.
主蒸気逃し安全弁排気管に関し、各々の蒸気放出導管部
は水中内に於いてヘッダーを組み、周囲を強固な岩盤に
よ多支持された原子炉格納容器に取り付け、かつ、ドラ
イウェル壁には蒸気流出方向制限板を設けた主蒸気逃し
安全弁排気管装置。Regarding the main steam relief safety valve exhaust pipe, each steam release conduit section is assembled with a header underwater, and attached to the reactor containment vessel which is surrounded by solid rock. Main steam relief safety valve exhaust pipe device equipped with an outflow direction restriction plate.
以下、本発明の一実施例を図面に基づいて詳細に説明す
る。第5図は本発明の一実施例を示す平面図、第6図は
第5図のB−B断面図である。Hereinafter, one embodiment of the present invention will be described in detail based on the drawings. FIG. 5 is a plan view showing one embodiment of the present invention, and FIG. 6 is a sectional view taken along line BB in FIG.
図に於いて、10は排気管、11は水中部で組み合せた
ヘッダー管、12はヘッダーとドライウェル壁3が最も
近接した所に於けるドライウェル壁3に取シ付けである
蒸気流出方向制限板である。In the figure, 10 is an exhaust pipe, 11 is a header pipe that is combined in the underwater part, and 12 is a steam outflow direction restriction that is attached to the dry well wall 3 at the point where the header and the dry well wall 3 are closest. It is a board.
図に示すように、主蒸気逃し安全弁は水中部に於いてヘ
ッダー11を組み、そのヘッダ一部11に於いては多数
の蒸気放出開口を有するものとし、そのサボー)Bは周
囲を強固な岩盤により支持された原子炉格納容器に取り
付け、逃し安全弁が作動し、蒸気が水中に放出された際
の気泡脈動荷重を岩盤にて受ける構造とする。又、ヘッ
ダー11とドライウェル壁3が最も近接した部分に於い
て、放出蒸気が直接、ドライウェル3に衝突しないよう
に蒸気流出方向制限板を設置する。As shown in the figure, the main steam relief safety valve is constructed with a header 11 in the underwater part, and the header part 11 has a large number of steam release openings. It is installed in the reactor containment vessel supported by the rock, and the rock is designed to absorb the bubble pulsation load when the relief safety valve is activated and steam is released into the water. Further, a steam outflow direction restriction plate is installed at a portion where the header 11 and the dry well wall 3 are closest to each other so that the released steam does not directly collide with the dry well 3.
以上の様に構成されるので、逃がし安全弁が作動し、蒸
気が水中に放出された際に於いて、気泡脈動荷重は原子
炉格納容器と一体となった岩盤で受は止め、ドライウェ
ル壁3には蒸気流出方向制限板12によシ、直接、ドラ
イウェル壁には衝突しない。又、ドライウェル壁3は円
形をなしている為、ヘッダー管は、原子炉空洞の長手方
向に沿って配置するので、ドライウェルと距離が離れる
為、圧力荷重が減衰し、荷重値そのものが低減される。With the above structure, when the relief safety valve operates and steam is released into the water, the bubble pulsation load is stopped by the rock that is integrated with the reactor containment vessel, and the dry well wall 3 Due to the vapor outflow direction restriction plate 12, the vapor does not collide directly with the dry well wall. In addition, since the dry well wall 3 is circular, the header pipe is placed along the longitudinal direction of the reactor cavity, so it is separated from the dry well, so the pressure load is attenuated and the load value itself is reduced. be done.
本発明は第5図に示す如く、サプレッションプール4の
配置がコンパクトとなり、機器の設計。As shown in FIG. 5, the present invention allows the suppression pool 4 to be arranged compactly, thereby improving the equipment design.
据付、メインテナンスが容易となる。又、気泡脈動荷重
が低減される。Installation and maintenance are easy. Moreover, bubble pulsation load is reduced.
本発明は上記の様に構成されるので、次の効果が挙げら
れる。Since the present invention is configured as described above, it has the following effects.
(1) ドライウェル壁に作用する荷重が低減出来る
。(1) The load acting on the dry well wall can be reduced.
(H) サプレッションプール内の配置カコンパクト
になり、設計、据付、施工性等が容易になる。(H) The arrangement within the suppression pool becomes compact, making design, installation, workability, etc. easier.
(+++> 格納容器内機器の設計荷重が低減出来る
。(+++> The design load of the equipment inside the containment vessel can be reduced.
第1図は地下式原子力発電所原子炉空洞の説明図、第2
図は第1図のA−A部説明図、第3図は主蒸気逃し安全
弁排気管装置廻シを示す図、第4図は主蒸気逃し安全弁
排気管の蒸気放出等管部詳細図、第5図は本発明の一実
施例を示す平面図、第6図は第5図のB−B部説明図で
ある。
1・・・岩盤、2・・・原子炉格納容器、3・・・ドラ
イウェル、4・・・サプレッションプール、5・・・ベ
ント管、6・・・原子炉圧力容器、7・・・サポート材
、8・・・原子炉空洞、9・・・逃がし安全弁排気管装
置、10・・・排気管、11・・・ヘッダー管、12・
・・蒸気流出方向制限板、13・・・蒸気放出導管。
代理人 弁理士 高橋明夫
専 2図
茅30
芽4区
茅S図Figure 1 is an explanatory diagram of the reactor cavity of an underground nuclear power plant, Figure 2
The figure is an explanatory diagram of the A-A section in Figure 1, Figure 3 is a diagram showing the main steam relief safety valve exhaust pipe system, Figure 4 is a detailed diagram of the steam release pipe section of the main steam safety safety valve exhaust pipe, FIG. 5 is a plan view showing an embodiment of the present invention, and FIG. 6 is an explanatory view of section BB in FIG. 1... Bedrock, 2... Reactor containment vessel, 3... Dry well, 4... Suppression pool, 5... Vent pipe, 6... Reactor pressure vessel, 7... Support Material, 8... Reactor cavity, 9... Relief safety valve exhaust pipe device, 10... Exhaust pipe, 11... Header pipe, 12...
...Steam outflow direction restriction plate, 13...Steam release conduit. Agent: Patent Attorney Akio Takahashi 2 illustrations, 30 grass, 4 wards, grass, S map
Claims (1)
両脇に原子炉格納容器サプレッションプールを配置した
格納容器内の主蒸気逃し安全弁排気管装置に関し、蒸気
放出導管部を周囲を強固な岩盤により支持された原子炉
格納容器に取り付け、逃し安全弁作動時の気泡脈動荷重
に関し、ドライウェル壁に作用する荷重を低減すること
を特徴とした主蒸気逃し安全弁排気管装置。 2、特許請求の範囲第1項において、各々の蒸気放出導
管は水中内に於いて、ヘッダーを組み、かつ、ドライウ
ェル壁には蒸気流出方向制限板を取り付け、蒸気流出方
向がドライウェル壁に直接、衝突しないようにし、ヘッ
ダーを原子炉格納容器に沿って配置することによ多サプ
レッションプール内の配置をコンパクトにした事を特徴
とする主蒸気逃し安全弁排気管装置。[Scope of Claims] 1. In an underground nuclear power plant, a main steam relief safety valve exhaust pipe device in a containment vessel in which containment vessel suppression pools are arranged on both sides of a dry well; A main steam relief safety valve exhaust pipe device is installed in a reactor containment vessel whose surroundings are supported by solid rock, and is characterized by reducing the load acting on the drywell wall in relation to the bubble pulsation load when the relief safety valve is activated. 2. In claim 1, each steam discharge conduit is submerged with a header, and a steam outflow direction restriction plate is attached to the dry well wall, so that the steam outflow direction is directed toward the dry well wall. A main steam relief safety valve exhaust pipe device characterized by preventing direct collision and by arranging the header along the reactor containment vessel to make the arrangement in the multi-suppression pool compact.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58007293A JPS59133491A (en) | 1983-01-21 | 1983-01-21 | Discharging tube device for main steam escape safety valve |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58007293A JPS59133491A (en) | 1983-01-21 | 1983-01-21 | Discharging tube device for main steam escape safety valve |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS59133491A true JPS59133491A (en) | 1984-07-31 |
Family
ID=11661980
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP58007293A Pending JPS59133491A (en) | 1983-01-21 | 1983-01-21 | Discharging tube device for main steam escape safety valve |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS59133491A (en) |
-
1983
- 1983-01-21 JP JP58007293A patent/JPS59133491A/en active Pending
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