JPS5987396A - Steam leakage suppression device of main steam isolation valve - Google Patents

Steam leakage suppression device of main steam isolation valve

Info

Publication number
JPS5987396A
JPS5987396A JP57196761A JP19676182A JPS5987396A JP S5987396 A JPS5987396 A JP S5987396A JP 57196761 A JP57196761 A JP 57196761A JP 19676182 A JP19676182 A JP 19676182A JP S5987396 A JPS5987396 A JP S5987396A
Authority
JP
Japan
Prior art keywords
main steam
steam
isolation valve
cooling
main
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
JP57196761A
Other languages
Japanese (ja)
Inventor
玄 小林
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP57196761A priority Critical patent/JPS5987396A/en
Publication of JPS5987396A publication Critical patent/JPS5987396A/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

Landscapes

  • Lift Valve (AREA)
  • Pipeline Systems (AREA)
  • Control Of Turbines (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】 〔発明の技術分野〕 沸騰水形原子力発電プラントの主蒸気隔離弁閉鎖時に、
その主蒸気隔離弁からの蒸気漏れを抑制する主蒸気隔離
弁の蒸気漏れ抑制装置に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] When the main steam isolation valve of a boiling water nuclear power plant is closed,
The present invention relates to a steam leak suppression device for a main steam isolation valve that suppresses steam leakage from the main steam isolation valve.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

沸騰水形原子力発電プラントにおいては、原子炉圧力容
器内で発生した蒸気は主蒸気管を通って直接タービンに
導かれ、タービンを駆動して発電を行っている。従って
、原子炉−次冷却材がそのまま蒸気となってタービンに
導かれていて、蒸気中には微量の核分裂生成物や腐食生
成物などによる放射性物質が含まれるので、主蒸気管が
原子炉格納容器の外で破断した場合に、放射能が外部に
放出されるのを防ぎ、また、原子炉冷却材が流出するの
を防ぐために、主蒸気管が原子炉格納容器の外壁を貫通
する部分の内側と外側にそれぞれ主蒸気隔離弁が設けら
れている。主蒸気隔離弁は、通常4本並列に設けられて
いる主蒸気管にそれぞ(2) れ2個ずつ設けられ、空気又は窒素ガス作動式で、主蒸
気管破断事故時など非常の際は短時間で閉じられるよう
になっていて、その機能上、動作の確実性と、閉鎖時の
低い蒸気漏れ率が特に厳しく要求される。
In a boiling water nuclear power plant, steam generated in a reactor pressure vessel is led directly to a turbine through a main steam pipe, and drives the turbine to generate electricity. Therefore, the sub-reactor coolant is directly converted to steam and guided to the turbine, and since the steam contains minute amounts of radioactive materials such as fission products and corrosion products, the main steam pipe is used to store the reactor. In order to prevent radioactivity from being released to the outside and to prevent reactor coolant from flowing out in the event of a rupture outside the vessel, the section where the main steam pipe penetrates the outer wall of the reactor containment vessel is Main steam isolation valves are provided on the inside and outside, respectively. Main steam isolation valves are installed in each of the four main steam pipes (2) in parallel, and are air or nitrogen gas operated. They are intended to be closed within a short period of time, and their functionality places particularly stringent demands on reliability of operation and low steam leakage rates upon closure.

主蒸気隔離弁は、内部流体が高温で乾燥した蒸気である
ため、水のような比較的高密度で高粘性を有する液体の
場合と比較して、その弁体と弁箱とが接触しているシー
ト面のシール性を1. OO%確実にすることは技術的
に困難で、シート面の極めて僅かな隙間からでも容易に
蒸気漏れが発生する可能性があり、更に、シート面に微
細なごみが付着するなどして、その密層性が損なわれる
と、許容限度以上の蒸気漏れが発生する恐れがある。
Because the main steam isolation valve uses high-temperature, dry internal fluid as steam, the valve body and valve body are less likely to come into contact with each other than when the internal fluid is a relatively high-density, high-viscosity liquid such as water. The sealing performance of the sheet surface is 1. It is technically difficult to ensure 00%, and steam leakage can easily occur even from extremely small gaps on the sheet surface.Furthermore, minute dust may adhere to the sheet surface, causing the seal to deteriorate. If the layering properties are impaired, there is a risk that steam leakage beyond the permissible limit will occur.

史に、主蒸気隔離弁に導かれる蒸気には放射性物質が含
まれていて、主蒸気隔離弁閉鎖時に蒸気が漏れると放射
能汚染が起こる危険性があるので、沸騰水形原子力発電
プラントの主蒸気隔離弁に対しては、非常の際閉鎖され
た時、その主蒸気隔離弁からの蒸気漏れ防止策が強く要
求されてきた。
Historically, the steam led to the main steam isolation valve contains radioactive materials, and if the steam leaks when the main steam isolation valve is closed, there is a risk of radioactive contamination. For steam isolation valves, there has been a strong demand for measures to prevent steam leakage from the main steam isolation valve when it is closed in an emergency.

〔発明の目的〕[Purpose of the invention]

この発明は上記の事情にかんがみてなされたもので、沸
騰水形原子力発電プラントの主蒸気隔離弁において、そ
の弁体と弁箱とが接触するシート面のシール性が100
%確実でなくても、内部の高温蒸気の密度を増し、粘性
を高めることによって、そのシート面からの漏れを可能
な限り抑制しようとする主蒸気隔離弁の蒸気漏れ抑制装
置を提供することを目的とするっ 〔発明の概要〕 沸騰水形原子力発電プラントの主蒸気隔離弁のような隔
離弁は、閉鎖された時、内部流体が密度が低くて、粘性
も小さい乾燥した高温蒸気のような場合はその弁からの
漏れが発生し易く、蒸気と比較してはるかに高密度で高
粘性な水の場合は、弁のシール性が同じ程度であっても
、漏れは発生しにくいので、この発明による主蒸気隔離
弁の蒸気漏れ抑制装置は、主蒸気隔離弁が閉鎖された時
、その主蒸気隔離弁の上流側の蒸気を冷却用水で直接冷
却して水の状態ζこし、それを主蒸気隔離弁に導くよう
にして漏れを極力抑制するようにしたのが特徴である。
This invention was made in view of the above-mentioned circumstances, and the sealing performance of the seat surface where the valve body and the valve body come into contact with each other in the main steam isolation valve of a boiling water nuclear power plant is 100%.
To provide a steam leak suppression device for a main steam isolation valve that attempts to suppress leakage from its seat surface as much as possible by increasing the density and viscosity of internal high-temperature steam, even if it is not certain. [Summary of the Invention] When an isolation valve, such as the main steam isolation valve of a boiling water nuclear power plant, is closed, the internal fluid has low density and low viscosity, such as dry high-temperature steam. In the case of water, which is much denser and more viscous than steam, leakage is less likely to occur even if the sealing performance of the valve is the same. The steam leak suppression device for a main steam isolation valve according to the invention directly cools the steam on the upstream side of the main steam isolation valve with cooling water to strain the state of the water, and then The feature is that the leakage is suppressed as much as possible by guiding it to the steam isolation valve.

この発明による主蒸気隔離弁の蒸気漏れ抑制装置では、
沸騰水形原子力発電プラントにおいて4本の主蒸気管が
原子炉格納容器の外壁を貫通する部分の内側と外側にそ
れぞれ設けられた主蒸気隔離弁の内、原子炉格納容器の
内側にある主蒸気隔離弁の上流側の主蒸気管内の蒸気を
冷却して水の状態にするため、主蒸気隔離弁が閉鎖され
ると同時に、ポンプによって圧力抑制プールなどから冷
却用水を吸い上げ、それを冷却管路を経由して、前記主
蒸気隔離弁の上流側でその冷却管路が接続された主蒸気
管の内壁面に、前記冷却管路に連通して設けられたスプ
レーノズルに導いて、その付近の主蒸気管内の蒸気に直
接スプレーするようにしている。
In the steam leak suppression device for the main steam isolation valve according to this invention,
In a boiling water nuclear power plant, main steam isolation valves are installed on the inside and outside of the part where the four main steam pipes penetrate the outer wall of the reactor containment vessel, respectively. In order to cool the steam in the main steam pipe upstream of the isolation valve and turn it into water, the main steam isolation valve is closed, and at the same time a pump sucks up cooling water from a pressure suppression pool, etc., and transfers it to the cooling pipe. through the main steam isolation valve to a spray nozzle provided in communication with the cooling pipe on the inner wall surface of the main steam pipe to which the cooling pipe is connected on the upstream side of the main steam isolation valve. The spray is applied directly to the steam in the main steam pipe.

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

この発明による沸騰水形原子力発電プラントにおける主
蒸気隔離弁の蒸気漏れ抑制装置の一実施例を第1図及び
第2図によって説明する。
An embodiment of the steam leak suppression device for a main steam isolation valve in a boiling water nuclear power plant according to the present invention will be described with reference to FIGS. 1 and 2.

(5) 第1図はこの発明による主蒸気隔離弁の蒸気漏れ抑制装
置の管路系統図で、沸騰水形原子力発電プラントにおい
ては原子炉圧力容器1内で発生した蒸気は通常4本並列
に設けられた主蒸気管2を通って直接タービン(図面で
は省略)に導かれているが、それら主蒸気管2が原子炉
格納容器3の外壁を貫通する部分の内側と外側にそれぞ
れ主蒸気隔離弁4A、4Bが設けられている。また、原
子炉格納容器3には圧力抑制プール5が付設されていて
、大量の水が常に蓄えられている。
(5) Figure 1 is a pipe system diagram of the steam leak suppression device for the main steam isolation valve according to the present invention. In a boiling water nuclear power plant, the steam generated in the reactor pressure vessel 1 is normally connected in four lines in parallel. The main steam pipes 2 are directly led to the turbine (not shown in the drawing) through the provided main steam pipes 2, but the main steam is isolated on the inside and outside of the part where the main steam pipes 2 penetrate the outer wall of the reactor containment vessel 3. Valves 4A and 4B are provided. Further, a pressure suppression pool 5 is attached to the reactor containment vessel 3, and a large amount of water is always stored therein.

上記の従来からの沸騰水形原子力発電プラントの主蒸気
系に対して、新たに設ける、この発明による主蒸気隔離
弁の蒸気漏れ抑制装置では、圧力抑制プール5内の水を
吸い上げるポンプ6と、前記ポンプ6の出口側を、冷却
系用弁7と逆上弁8とを介して、原子炉格納容器3の内
側に設けた主蒸気隔離弁4Aの上流側において各主蒸気
管2にそれぞれ接続する冷却管路9とが追加されている
The steam leak suppression device for the main steam isolation valve according to the present invention, which is newly provided for the main steam system of the conventional boiling water nuclear power plant described above, includes a pump 6 that sucks up water in the pressure suppression pool 5; The outlet side of the pump 6 is connected to each main steam pipe 2 on the upstream side of the main steam isolation valve 4A provided inside the reactor containment vessel 3 via a cooling system valve 7 and a reversal valve 8. A cooling pipe line 9 is added.

更に、第2図による、冷却管路9と主蒸気管2との接続
部分の一部破砕側面図で示すように、冷却(6) 管路9が接続されている部分の主蒸気管2の管壁に貫通
孔10を設け、その貫通孔10が主蒸気管2の内壁面に
開口する箇所にスプレーノズル11が、冷却管路9に連
通して取り付けられ、冷却管路9を通って導かれた冷却
用水が主蒸気管2の内部に直接スプレーされるようにし
ている。
Furthermore, as shown in the partially exploded side view of the connecting portion between the cooling pipe line 9 and the main steam pipe 2 in FIG. A through hole 10 is provided in the pipe wall, and a spray nozzle 11 is attached to the location where the through hole 10 opens to the inner wall surface of the main steam pipe 2 so as to communicate with the cooling pipe line 9, and the spray nozzle 11 is installed to communicate with the cooling pipe line 9. The cooled water is sprayed directly into the main steam pipe 2.

沸騰水形原子力発電プラントの主蒸気系に新たに追加さ
れた、この発明による主蒸気隔離弁の蒸気漏れ抑制装置
は、発電プラントが正常に運転されている時は、ポンプ
6は停止し、冷却系用弁7及び逆止弁8は閉ざされて、
主蒸気管2には圧力抑制プール5からの冷却用水が流入
するようなことはなく、原子炉圧力容器1内で発生した
蒸気は、新たに追加されたこの発明による蒸気漏れ抑制
装置によって影響を受けることなく、主蒸気隔離弁4A
、4Bを通ってタービン(図面では省略)に導かれる。
The main steam isolation valve steam leak suppression device according to the present invention, which has been newly added to the main steam system of a boiling water nuclear power plant, is designed to stop the pump 6 and prevent cooling when the power plant is operating normally. The system valve 7 and the check valve 8 are closed,
Cooling water from the pressure suppression pool 5 does not flow into the main steam pipe 2, and the steam generated in the reactor pressure vessel 1 is not affected by the newly added steam leak suppression device of the present invention. Main steam isolation valve 4A without receiving
, 4B to a turbine (not shown in the drawing).

主蒸気管2破断事故など非常事態が発生すると、主蒸気
隔離弁4A、4Bは短時間で閉鎖され、同時に、ポンプ
6が起動され、冷却系用弁7が開かれて、圧力抑制プー
ル5内の冷却用水が、冷却管路9を経て、主蒸気管2の
内面に開口しているスプレーノズル11に導かれ、原子
炉格納容器3の内側にある主蒸気隔離弁4Aの上流側の
主蒸気管2の内部の蒸気中にスプレーされる。冷却用水
が主蒸気管2内の高温の蒸気中にスプレーされると、そ
の蒸気は冷却されて水の状態になって、既に閉鎖されて
いる主蒸気隔離弁4Aに導かれる。水は蒸気と比較して
その物理的性質がはるかに高密度で高粘性なので、主蒸
気隔離弁4Aの弁体と弁箱とが接触しているシート面が
、低密度で粘性の小さい蒸気であれば漏れが発生するか
も知れないようなシール状態であっても、水の状態で導
かれると漏れは十分抑制されて、主蒸気隔離弁4A。
When an emergency situation such as a rupture of the main steam pipe 2 occurs, the main steam isolation valves 4A and 4B are closed in a short period of time, and at the same time, the pump 6 is started and the cooling system valve 7 is opened, causing the inside of the pressure suppression pool 5 to be closed. The cooling water of It is sprayed into the steam inside the tube 2. When the cooling water is sprayed into the high temperature steam in the main steam pipe 2, the steam is cooled into water and guided to the already closed main steam isolation valve 4A. Water has physical properties that are much denser and more viscous than steam, so the seat surface where the valve body of the main steam isolation valve 4A is in contact with the valve body is covered with steam, which has a low density and low viscosity. Even if the seal is in such a state that leakage may occur, leakage is sufficiently suppressed when water is introduced into the main steam isolation valve 4A.

4Bのシール性は向上する。The sealing performance of 4B is improved.

なお、第2図に示す実施例においてはスプレーノズル1
1は1個の場合を示しているが、これを複数個にしたり
、あるいは主蒸気管2の内面に沿って全周に設けるよう
にすれば、蒸気への冷却効果は更に向上する。
In addition, in the embodiment shown in FIG.
1 shows the case of one, but if a plurality of these are provided or if they are provided all around the inner surface of the main steam pipe 2, the cooling effect on the steam will be further improved.

また、第1図においては、冷却用水を圧力抑制プール5
から吸い上げているが、これは他の系統例えば復水貯蔵
タンクなどから引き込むことも可能である。
In addition, in FIG. 1, the cooling water is transferred to the pressure suppression pool 5.
However, this can also be drawn from other systems, such as a condensate storage tank.

〔発明の効果〕〔Effect of the invention〕

この発明による主蒸気隔離弁の蒸気漏れ抑制装置は、そ
の実施例について前項に詳述したように、対象の主蒸気
隔離弁が閉鎖された時その隔離弁の上流側の主蒸気管の
内壁面に設けたスプレーノズルに、圧力抑制プールなど
から冷却用水を導いて、その付近の主蒸気管内の蒸気に
直接スプレーして冷却し、蒸気と比較してはるかに高密
度で高粘性な水の状態にして対象とする主蒸気隔離弁に
導くようにしているので、主蒸気隔離弁は、閉鎖時に、
その隔離弁からの漏れは抑制されて、シール性が向上し
、主蒸気隔離弁が閉鎖されるような非常時に、放射性物
質を含んだ蒸気が外部に漏れて放射能汚染を起こすよう
なこともなくなり、沸騰水形原子力発電プラント全体の
安全性、信頼性が向上する効果がある。
As described in detail in the previous section regarding the embodiment of the steam leakage suppressing device for a main steam isolation valve according to the present invention, when the target main steam isolation valve is closed, the inner wall surface of the main steam pipe on the upstream side of the isolation valve is Cooling water is guided from a pressure suppression pool etc. to a spray nozzle installed in the main steam pipe, and is sprayed directly onto the steam in the main steam pipe in the vicinity to cool the water, which is much denser and more viscous than steam. When the main steam isolation valve is closed, the main steam isolation valve
Leakage from the isolation valve is suppressed and the sealing performance is improved, preventing steam containing radioactive materials from leaking outside and causing radioactive contamination in the event of an emergency when the main steam isolation valve is closed. This has the effect of improving the safety and reliability of the entire boiling water nuclear power plant.

(9)(9)

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

第1図はこの発明の一実施例における主蒸気隔離弁の蒸
気漏れ抑制装置の管路系統図、第2図は第1図における
主蒸気管(2)と冷却管路(9)との接続部付近の一部
破砕側面図である。 2・・・主蒸気管、4A、4B・・・主蒸気隔離弁、5
・・・圧力抑制プール、6・・・ポンプ、7・・・冷却
系用弁、8・・・逆止弁、9・・・冷却管路、11・・
・スプレーノズル。 (7317)  代理人 弁理士 則近憲佑(ほか1名
) (10)
Fig. 1 is a pipe line system diagram of a steam leak suppression device for a main steam isolation valve in an embodiment of the present invention, and Fig. 2 is a connection between the main steam pipe (2) and the cooling pipe line (9) in Fig. 1. FIG. 2... Main steam pipe, 4A, 4B... Main steam isolation valve, 5
... Pressure suppression pool, 6... Pump, 7... Cooling system valve, 8... Check valve, 9... Cooling pipe line, 11...
·spray nozzle. (7317) Agent Patent attorney Kensuke Norichika (and 1 other person) (10)

Claims (2)

【特許請求の範囲】[Claims] (1)沸騰水形原子力発電プラントの主蒸気管が原子炉
格納容器の外壁を貫通する部分の内側と外側にそれぞれ
主蒸気隔離弁が設けられている主蒸気系において、原子
炉格納容器の内側にある前記主蒸気隔離弁の上流側で主
蒸気管に接続された冷却管路と、前記冷却管路が接続さ
れている部分の主蒸気管の内壁に前記冷却管路に連通し
て設けられたスプレーノズルと、前記冷却管路に冷却系
用弁を経由して冷却用水を供給し、前記スプレーノズル
から前記原子炉格納容器の内側にある主蒸気隔離弁の上
流側の主蒸気管内の蒸気中に直接冷却用水をスプレーす
るようにするポンプとからなる主蒸気隔離弁の蒸気漏れ
抑制装置。
(1) In the main steam system of a boiling water nuclear power plant where main steam isolation valves are installed on the inside and outside of the part where the main steam pipe penetrates the outer wall of the reactor containment vessel, inside the reactor containment vessel. A cooling pipe line connected to the main steam pipe on the upstream side of the main steam isolation valve located at cooling water is supplied to the cooling pipe line via a cooling system valve, and the steam in the main steam pipe on the upstream side of the main steam isolation valve inside the reactor containment vessel is supplied from the spray nozzle to the cooling pipe line via a cooling system valve. A steam leak suppression device for a main steam isolation valve consisting of a pump that sprays cooling water directly into the main steam isolation valve.
(2)  ポンプによって供給される冷却用水が圧力抑
制プールから導かれることを特徴とする特許請求の範囲
第1項記載の主蒸気隔離弁の蒸気漏れ抑(1) 制装置。
(2) A steam leakage control device for a main steam isolation valve according to claim 1, wherein the cooling water supplied by the pump is guided from a pressure suppression pool.
JP57196761A 1982-11-11 1982-11-11 Steam leakage suppression device of main steam isolation valve Pending JPS5987396A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57196761A JPS5987396A (en) 1982-11-11 1982-11-11 Steam leakage suppression device of main steam isolation valve

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57196761A JPS5987396A (en) 1982-11-11 1982-11-11 Steam leakage suppression device of main steam isolation valve

Publications (1)

Publication Number Publication Date
JPS5987396A true JPS5987396A (en) 1984-05-19

Family

ID=16363177

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57196761A Pending JPS5987396A (en) 1982-11-11 1982-11-11 Steam leakage suppression device of main steam isolation valve

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60230304A (en) * 1984-04-27 1985-11-15 株式会社ネオス Electrically insulating composition

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60230304A (en) * 1984-04-27 1985-11-15 株式会社ネオス Electrically insulating composition

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