JPS6085391A - Main steam relief safety valve exhaust system - Google Patents

Main steam relief safety valve exhaust system

Info

Publication number
JPS6085391A
JPS6085391A JP58192323A JP19232383A JPS6085391A JP S6085391 A JPS6085391 A JP S6085391A JP 58192323 A JP58192323 A JP 58192323A JP 19232383 A JP19232383 A JP 19232383A JP S6085391 A JPS6085391 A JP S6085391A
Authority
JP
Japan
Prior art keywords
safety valve
main steam
exhaust
relief safety
water
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
Application number
JP58192323A
Other languages
Japanese (ja)
Inventor
早雲 直
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP58192323A priority Critical patent/JPS6085391A/en
Publication of JPS6085391A publication Critical patent/JPS6085391A/en
Pending 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

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おいて、主蒸気放出
部の改善により、気泡脈動撮動を防止し、かつ、サプレ
ッションプール内の配置をコンノくクトにした逃し安全
弁排気り装置に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention provides a relief safety valve exhaust pipe device that prevents bubble pulsation by improving the main steam discharge section and also improves the arrangement within the suppression pool. Relating to a safety relief valve exhaust system that has been designed to

〔発明の背景〕[Background of the invention]

従来、第1図、第2図、第3図に示すように、原子炉l
の異常な圧力上昇を防止するために、主蒸気管2に逃し
安全弁3が設置されており、その排気管4は圧力抑制室
5のサプレッションプール6の水中にのび、蒸気放出導
管7を介して蒸気を水中に放出するようになっている。
Conventionally, as shown in Fig. 1, Fig. 2, and Fig. 3, a nuclear reactor l
In order to prevent an abnormal pressure rise in the main steam pipe 2, a relief safety valve 3 is installed in the main steam pipe 2, and its exhaust pipe 4 extends into the water of the suppression pool 6 of the pressure suppression chamber 5, and the steam discharge conduit 7 It is designed to release steam into the water.

蒸気放出導管7としては、水平に向いた2個の開口を有
するものが用いられていた。しかし、このような構造で
は、後述する気泡圧力脈動が大きいという欠点ケ有して
いた。
The vapor discharge conduit 7 used had two horizontally oriented openings. However, such a structure has the disadvantage that bubble pressure pulsations, which will be described later, are large.

ここで、気泡圧力脈動ケ第4図を用いて説明する。逃し
安全弁3が開く前は、排気管内4は空気で満されており
、水柱はブール6水面位置にある。
Here, bubble pressure pulsation will be explained using FIG. 4. Before the relief safety valve 3 is opened, the inside of the exhaust pipe 4 is filled with air, and the water column is at the water level of the boule 6.

逃し安全弁3が開くと、原子炉l内の蒸気?逃し、安全
弁排気管4内に放出され、管内の空気を圧縮しながら管
内の水柱ケ下方に押しやる。蒸気は音速で放出されるの
で、空気と蒸気はほとんど混合せず、空気は蒸気放出導
管7から気泡となってブール水6中に放出される。この
間、空気は20〜30Kg/crn2g に加圧される
ので、水中で急膨張する。この時、周囲の水を押しやる
ので、気泡の圧力が水中圧力オで下っても、水の慣性で
気泡は更に膨張し、気泡圧力は負圧になる。慣性がなく
なると、気泡の負圧により周囲の水が引きよせらし、気
泡は逆に圧縮され、水の慣性により今度は加圧されるの
で、気泡圧力は初めに放出された時の圧力より高くなる
。このように膨張・圧縮金繰り返しながら、気泡が水面
に上昇する。この状態全気泡圧力脈動といい、この脈動
は第5図に示されるように、気泡が水面に上昇するまで
続く。なお、第5図中のA、B、C,Dは第4因のA、
B。
When the relief safety valve 3 opens, steam inside the reactor l? It is released into the safety valve exhaust pipe 4, compressing the air inside the pipe and forcing it downward into the water column inside the pipe. Since the steam is discharged at the speed of sound, there is little mixing between air and steam, and the air is discharged from the steam discharge conduit 7 into the boule water 6 in the form of bubbles. During this time, the air is pressurized to 20-30 kg/crn2g, so it expands rapidly in the water. At this time, the surrounding water is pushed away, so even if the pressure of the bubble falls due to the underwater pressure, the bubble expands further due to the inertia of the water, and the bubble pressure becomes negative pressure. When the inertia disappears, the surrounding water is pulled away by the negative pressure of the bubble, and the bubble is compressed in the opposite direction, and the inertia of the water pressurizes the bubble, so the bubble pressure is higher than the pressure when it was first released. Become. As the gas expands and compresses in this way, the bubbles rise to the surface of the water. This state is called total bubble pressure pulsation, and this pulsation continues until the bubble rises to the water surface, as shown in FIG. In addition, A, B, C, and D in Fig. 5 are the fourth factor A,
B.

C,Dに対応している。It corresponds to C and D.

気泡圧力脈動は、水中波となり、ブール6中の構造物に
加わり、動的な荷重として作用する。この荷重は排気管
内の空気圧力に比例すると考えられる。米国等の実機プ
ラントでの測定結果によると、この水中波は5−15H
zで、正圧3Kg/C1n”g 。
The bubble pressure pulsations become underwater waves and are added to the structure in the boule 6, acting as a dynamic load. This load is considered to be proportional to the air pressure inside the exhaust pipe. According to measurement results at actual plants in the United States and other countries, this underwater wave is 5-15H.
z, positive pressure 3Kg/C1n"g.

負圧−1,s Kg/z ’ g位になり、気泡が水面
で破裂するまで約1秒程度続く。
The negative pressure reaches -1,s Kg/z'g, which lasts about 1 second until the bubble bursts on the water surface.

プラント寿命中における逃し安全弁3の作動による繰り
返[2嵌動は、40000〜50000 回となり、上
記気泡圧力脈動により、水面下の構造材及び逃し安全弁
排気管4に疲労応力ゲ加えるので、構造物の設計条件は
著しく苛酷なものとなる。
The repeated operation of the relief safety valve 3 during the life of the plant will be 40,000 to 50,000 times, and the bubble pressure pulsations will add fatigue stress to the structural members under the water surface and the relief safety valve exhaust pipe 4. The design conditions are extremely severe.

このような苛酷な荷重条件を和らり、構造物の健全性に
対する余裕ケ増すとともに、設計条件の低減により、構
造材の製作時の経済負担を低減する必要がある。
It is necessary to alleviate such severe load conditions, increase the margin for the soundness of the structure, and reduce the economic burden during the production of structural materials by reducing design conditions.

〔発明の目的〕[Purpose of the invention]

本発明は、逃し安全弁排気管装置を隔離することにより
、プール水中に放出された排気管内の空気による気泡圧
力脈動?軽減し、プール水中の構造材の設計荷重を軽減
した逃し安全弁排気管装置ケ提供することを目的とする
The present invention eliminates bubble pressure pulsation due to air in the exhaust pipe released into the pool water by isolating the relief safety valve exhaust pipe device. The purpose of the present invention is to provide a relief safety valve exhaust pipe device that reduces the design load of structural materials in swimming pool water.

〔発明の概要〕[Summary of the invention]

サプレッションプール部に円筒状でかつ円周状に配置さ
れた排気装置エリア金設置し、その中に排気管を導びき
、連結管にて組合せた構造に必る。
This requires a structure in which a cylindrical and circumferentially arranged exhaust system area is installed in the suppression pool area, an exhaust pipe is led into the area, and the exhaust pipes are connected together with a connecting pipe.

〔発明の実施例〕[Embodiments of the invention]

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6図、第7図、第8図に示すように、サプレッシ
ョンプール部6において、円筒状で、かつ、円周状に設
置された蒸気放出エリアを設置し、その中に排気管7を
導びき、連結管12(ヘッダー状)に組み合せるものと
する。水中の円筒状排気装置は、多数の開口11Th有
し、そこから放出した蒸気が凝縮しうるに充分な深さに
配置されている。
Hereinafter, one embodiment of the present invention will be described in detail based on the drawings. As shown in FIGS. 6, 7, and 8, a cylindrical and circumferential steam release area is installed in the suppression pool section 6, and an exhaust pipe 7 is introduced into it. It shall be combined into a connecting pipe 12 (header type). The submersible cylindrical exhaust device has a number of openings 11Th and is placed at a sufficient depth so that the steam released therefrom can condense.

本発明によると、円筒状の排気装置が設置され、かつ、
その中に排気管7が導ひかれるので、従来の如く、分散
配置された排気管が不要となり、第7図に示す如く、サ
プレッションプール部の配置がコンパクトになり、機器
の設計・据付・メンテナンスが非常に容易となる。
According to the present invention, a cylindrical exhaust device is installed, and
Since the exhaust pipe 7 is guided through it, there is no need for exhaust pipes that are distributed in a conventional manner, and as shown in Fig. 7, the arrangement of the suppression pool section can be made compact, and the design, installation, and maintenance of equipment can be improved. becomes very easy.

さらに、本発明によると動的荷重の低減が可能となる。Furthermore, according to the present invention, dynamic loads can be reduced.

以下、詳細に説明する。本発明の蒸気放出装置を介して
、空気が水中に放出された場合の空気泡脈動のプロセス
、及び、圧力変化は第8図に示されている。この場合も
、従来と同じく、A。
This will be explained in detail below. The process of air bubble pulsation and pressure change when air is released into water through the steam release device of the present invention is shown in FIG. In this case, as before, A.

B、C,Dのプロセスを紅て、空気泡が水中に放出され
、かつ、この空気泡が膨張・圧縮ケ繰り返しながら上昇
するものである。しかしながら、本発明によると、排気
装置部は任意の位置に設定出来、サブレツショングール
中央部は、原子炉格納容器136るいはRPVペデスタ
ル14に加わる荷重が、放出量の減衰により大幅に低減
可能となり、又、例えば原子炉格納容器13に近い場合
は、吹出しロkRPVペデスタル14側にのみ向けるこ
とにより、RPVペデスタル14及び原子炉格納容器1
3に加わる動荷重は、大幅に低減される。
By repeating processes B, C, and D, air bubbles are released into the water, and these air bubbles rise while repeatedly expanding and compressing. However, according to the present invention, the exhaust system part can be set at any position, and the load applied to the subreaction guru central part can be significantly reduced by attenuating the amount of discharge. For example, if it is close to the reactor containment vessel 13, by directing the air outlet only toward the RPV pedestal 14 side, the RPV pedestal 14 and the reactor containment vessel 1 can be
The dynamic loads applied to 3 are significantly reduced.

〔発明の効果〕〔Effect of the invention〕

本発明は、上記のように構成され作用するので、次の効
果が挙けられる。
Since the present invention is configured and operates as described above, it has the following effects.

(1) サプレッションプール内の配置がコンパクトに
なり、設計・施工等が容易になる。
(1) The layout inside the suppression pool becomes more compact, making design and construction easier.

(2)排気装置全任意の位置に設定可能とし、サプレツ
7ヨングール水中の構造材に5加わる動荷重ケ大幅に軽
減することが出来る。
(2) The exhaust system can be set in any position, and the dynamic loads applied to structural materials underwater can be significantly reduced.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図はM A RK−II型原子炉格納容器部の説四
回、第2図は従来型の逃し安全弁蒸気放出導管部分図、
第3図は格納容器内サプレッションプール部平面図、第
4図は第2図に示す逃し安全弁排気による空気泡圧力脈
動のプロセスを示す説明図、第5図は第4図のプロセス
における空気泡圧力と時間の関係を示すグラフ、第6図
は本発明の一実施例を示す図、第7図は同平面図、第8
図は本発明によるプロセスにおける空気泡圧力と時間の
関係を示すグラフである。 l・・・原子炉、2・・・主蒸気管、3・・・逃し安全
弁、4・・・排気管、5・・・圧力抑制室、6・・・サ
プレッションプール、7・・・蒸気放出導管、8・・・
パーティカルカラム、9・・・ダイヤフラムフロア−,
1(1・・・円筒状排気装置、11・・・開0.12・
・・連結管、13・・・原子炉格納容器、14・・・I
(PVペデスタル。 代理人 弁理士 高橋明夫 # 1区 第3区 〆 #4カ (A> (B) (c) CD) 陀もの $、、7 図 8 $8 図 碕旬
Figure 1 is a partial view of the M A RK-II type reactor containment vessel, Figure 2 is a partial view of the conventional relief safety valve steam release conduit,
Figure 3 is a plan view of the suppression pool inside the containment vessel, Figure 4 is an explanatory diagram showing the process of air bubble pressure pulsation due to relief safety valve exhaust shown in Figure 2, and Figure 5 is the air bubble pressure in the process of Figure 4. FIG. 6 is a diagram showing an embodiment of the present invention, FIG. 7 is a plan view of the same, and FIG.
The figure is a graph showing the relationship between air bubble pressure and time in the process according to the invention. l... Nuclear reactor, 2... Main steam pipe, 3... Safety relief valve, 4... Exhaust pipe, 5... Pressure suppression chamber, 6... Suppression pool, 7... Steam release Conduit, 8...
Particle column, 9... diaphragm floor,
1 (1... cylindrical exhaust device, 11... open 0.12.
...Connecting pipe, 13...Reactor containment vessel, 14...I
(PV Pedestal. Agent Patent Attorney Akio Takahashi #1 Ward 3rd Ward #4 Ka (A> (B) (c) CD) Accessories $, 7 Figure 8 $8 Shun Zusaki

Claims (1)

【特許請求の範囲】 1、主蒸気管に逃し安全弁を介して接続する排気管全圧
力抑制室内のサプレッションプール中に開口した原子炉
格納容器において、サプレッションプール内の円周に沿
って排気エリアを設置しその中に排気管?設置したこと
全特徴とする主蒸気逃し安全弁排気装置。 2、特許請求の範凹第1項において、上記の円周状排気
管装置部で水中内の蒸気放出部に蒸気放出部を連結管に
組み込んだこ(!:ニラ徴とする主蒸気逃し安全弁排気
装置。
[Claims] 1. In a reactor containment vessel that opens into a suppression pool in an exhaust pipe full pressure suppression chamber connected to the main steam pipe via a safety relief valve, an exhaust area is defined along the circumference of the suppression pool. Install it and put an exhaust pipe in it? Installed a main steam relief safety valve exhaust system that is fully featured. 2. Claims No. 1 provides that in the circumferential exhaust pipe device part, a steam discharge part is incorporated into a connecting pipe to a steam discharge part in water (!: main steam relief safety valve exhaust Device.
JP58192323A 1983-10-17 1983-10-17 Main steam relief safety valve exhaust system Pending JPS6085391A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58192323A JPS6085391A (en) 1983-10-17 1983-10-17 Main steam relief safety valve exhaust system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58192323A JPS6085391A (en) 1983-10-17 1983-10-17 Main steam relief safety valve exhaust system

Publications (1)

Publication Number Publication Date
JPS6085391A true JPS6085391A (en) 1985-05-14

Family

ID=16289365

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58192323A Pending JPS6085391A (en) 1983-10-17 1983-10-17 Main steam relief safety valve exhaust system

Country Status (1)

Country Link
JP (1) JPS6085391A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0820067A1 (en) * 1996-07-19 1998-01-21 Commissariat A L'energie Atomique Steam relief system with an internal condenser

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0820067A1 (en) * 1996-07-19 1998-01-21 Commissariat A L'energie Atomique Steam relief system with an internal condenser
FR2751401A1 (en) * 1996-07-19 1998-01-23 Commissariat Energie Atomique INTERNAL CONDENSER VAPOR DISCHARGE SYSTEM

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