JPH0580191A - Air operated valve - Google Patents
Air operated valveInfo
- Publication number
- JPH0580191A JPH0580191A JP3239895A JP23989591A JPH0580191A JP H0580191 A JPH0580191 A JP H0580191A JP 3239895 A JP3239895 A JP 3239895A JP 23989591 A JP23989591 A JP 23989591A JP H0580191 A JPH0580191 A JP H0580191A
- Authority
- JP
- Japan
- Prior art keywords
- air
- containment vessel
- reactor containment
- valve
- reactor
- 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.)
- Granted
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
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、沸騰水型原子炉の原子
炉格納容器内に設置される空気作動弁に係り、とくに原
子路格納容器内に圧力の影響を受けることなく安定した
作動特性を得るのに好適な空気作動弁に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an air operated valve installed in a reactor containment vessel of a boiling water reactor, and particularly to stable operation characteristics without being affected by pressure in the reactor containment vessel. And an air actuated valve suitable for obtaining
【０００２】[0002]
【従来の技術】従来の沸騰水型原子炉の原子炉格納容器
内に設置される空気作動弁は、たとえば第８図に示すよ
うに、弁３を駆動させる空気シリンダ４により弁を開閉
させている。この空気シリンダ４を駆動させる空気源は
原子炉格納容器２外から駆動用供給ライン１２により供
給されており、アキュムレータ６を介し駆動空気切替回
路５をへて空気シリンダ４へ接続されている。また、空
気シリンダ４からの空気の排出にも、同様に駆動空気切
替回路５を介し原子炉格納容器２内に排出されている。
駆動空気切替回路５は電磁弁等で構成されており、原子
路格納容器２外の作動信号１４により作動し、弁の開閉
を制御している。2. Description of the Related Art An air-operated valve installed in a reactor containment vessel of a conventional boiling water nuclear reactor is, for example, as shown in FIG. There is. An air source for driving the air cylinder 4 is supplied from the outside of the reactor containment vessel 2 by a drive supply line 12, and is connected to the air cylinder 4 via a drive air switching circuit 5 via an accumulator 6. Further, when the air is discharged from the air cylinder 4, it is similarly discharged into the reactor containment vessel 2 via the drive air switching circuit 5.
The drive air switching circuit 5 is composed of an electromagnetic valve or the like, and is operated by an operation signal 14 outside the atomic path storage container 2 to control opening / closing of the valve.
【０００３】しかるに上記従来技術では、原子炉格納容
器２内の圧力が駆動切換回路５の背圧として作用するた
め、従来技術の原子炉格納容器２の内圧が過大に上回る
条件に対しては、駆動空気回路５が作動遅れまたは作動
不良を発生し、空気作動弁３の動的機能が達成できない
可能性があった。この点についてさらに詳述するとつぎ
のとおりである。However, in the above-mentioned conventional technique, the pressure in the reactor containment vessel 2 acts as the back pressure of the drive switching circuit 5, so that the condition in which the internal pressure of the reactor containment vessel 2 in the conventional technique exceeds excessively is: There is a possibility that the driving air circuit 5 may be delayed in operation or may malfunction, and the dynamic function of the air operated valve 3 may not be achieved. This point will be described in more detail below.
【０００４】今原子炉格納容器内に設置される工学的安
全上重要な空気作動弁として主蒸気隔離弁（以下ＭＳＩ
Ｖと略す）および主蒸気逃がし安全弁（以下ＳＲＶと略
す）を用いた場合の動作はつぎのとおりである。The main steam isolation valve (hereinafter referred to as MSI) is installed in the reactor containment vessel as an air operated valve which is important for engineering safety.
The operation when using a V) and a main steam relief safety valve (hereinafter abbreviated as SRV) is as follows.
【０００５】図１５は沸騰水型原子炉の炉心冷却・除熱
システムの概略図であるが、同図には原子炉格納容器２
内にＭＳＩＶ２０とＳＲＶ２１が示されている。また、
図１０はＭＳＩＶの駆動空気切換回路を示し、図１３は
ＳＲＶの機能作動状態を示し、図１４は自動減圧系機能
作動状態を示す。上記図１０に示すＭＳＩＶ２０の駆動
空気切換回路は２個の常時励磁のメインコントロール用
電磁弁２４、２５により開になっており、２個のメイン
コントロール用電磁弁２４、２５が無励磁になることに
より第１切換弁２６、第３切換弁２９および第切換弁３
０が作動し、空気シリンダ４の上部に駆動空気を供給
し、空気シリンダ４の下部の空気を原子炉格納容器内に
排出することにより上記ＭＳＩＶ２０を急閉作動させ
る。一方図１３に示すＳＲＶの駆動空気回路は、該ＳＲ
Ｖ２１の機能が要求される場合であり、ＳＲＶ２１の機
能用電磁弁３５が励磁し、駆動空気を空気シリンダ４の
下部に供給する。同時に、空気シリンダ４上部の空気は
原子炉格納容器内に排出され、ＳＲＶ２１は開となり、
原子炉を減圧する。上記自動減圧系（以下ＡＤＳと略
す）の機能が要求される場合は図１４に示すように、Ａ
ＤＳ機能用電磁弁３７が励磁し同様に空気シリンダ４が
作動する。FIG. 15 is a schematic diagram of a core cooling and heat removal system for a boiling water reactor. In FIG. 15, the reactor containment vessel 2 is shown.
MSIV20 and SRV21 are shown in the figure. Also,
10 shows the MSIV drive air switching circuit, FIG. 13 shows the SRV functional operating state, and FIG. 14 shows the automatic depressurizing system functional operating state. The drive air switching circuit of the MSIV 20 shown in FIG. 10 is opened by the two main excitation solenoid valves 24 and 25 which are always excited, and the two main control solenoid valves 24 and 25 are not excited. Accordingly, the first switching valve 26, the third switching valve 29, and the third switching valve 3
0 operates, the driving air is supplied to the upper part of the air cylinder 4, and the air at the lower part of the air cylinder 4 is discharged into the reactor containment vessel, whereby the MSIV 20 is rapidly closed. On the other hand, the SRV drive air circuit shown in FIG.
This is the case where the function of V21 is required, and the solenoid valve 35 for function of SRV21 is excited to supply drive air to the lower portion of the air cylinder 4. At the same time, the air above the air cylinder 4 is discharged into the reactor containment vessel, and the SRV 21 opens,
Depressurize the reactor. When the function of the above automatic depressurization system (hereinafter abbreviated as ADS) is required, as shown in FIG.
The solenoid valve 37 for the DS function is excited and the air cylinder 4 operates in the same manner.
【０００６】そのため、ＭＳＩＶ２０およびＳＲＶ２１
の駆動空気回路は原子炉格納容器２の内圧を背圧として
受けるので、原子炉格納容器２の圧力上昇にともない、
ＭＳＩＶ２０、ＳＲＶ２１は動的作動不良を発生する。
そこでＭＳＩＶ２０，ＳＲＶ２１が原子炉格納容器２内
の圧力が高条件で動的作動要求に対応するため、従来実
施している炉心冷却と保熱システムを考慮した方法はつ
ぎのとおりである。Therefore, MSIV20 and SRV21
Since the driving air circuit of receives the internal pressure of the reactor containment vessel 2 as a back pressure, as the pressure of the reactor containment vessel 2 increases,
MSIV20 and SRV21 generate | occur | produce a dynamic malfunction.
Therefore, since the MSIV 20 and the SRV 21 respond to the dynamic operation request under the condition that the pressure inside the reactor containment vessel 2 is high, a method that takes into consideration the conventional core cooling and heat retention system is as follows.
【０００７】原子炉は、常用の炉心冷却・除熱サイクル
としてタービン系を有しており、図１５に示す如く原子
炉より発生した蒸気はタービン３８に導かれ仕事をし、
復水器３９にて循環水ポンプ４０からの海水で除熱され
冷却水となり、復水ポンプ４１、低圧給水加熱器４２、
給水ポンプ４３、高圧給水加熱器４４を介し、原子炉へ
給水されるシステムである。ただし、この常用系は原子
炉隔離信号によりＭＳＩＶ２０が閉となるため原子炉よ
り隔離される。この場合、炉心冷却としては図１５に示
す原子炉隔離時冷却系（以下ＲＣＩＣと略す。）が作動
し、原子炉蒸気により駆動するＲＣＩＣタービン４５に
よりＲＣＩＣポンプ４６が駆動し、復水貯蔵タンク４７
（以下ＣＳＴと略す。）水、又はサプレッションプール
９（以下Ｓ／Ｐと略す。）水を原子炉圧力容器１へ注入
し、ＲＣＩＣタービン排気はＳ／Ｐ９へ導かれている。
また、原子炉圧力を減圧するためＳＲＶ２１の逃がし弁
機能が作動する。逃がし弁機能は、設定された原子炉圧
力に到達するとＳＲＶ２１を開作動させる機能で、ＳＲ
Ｖ排気管はＳ／Ｐ９へ導かれており原子炉蒸気を凝縮さ
せる。The nuclear reactor has a turbine system as a routine core cooling / heat removal cycle. As shown in FIG. 15, steam generated from the nuclear reactor is guided to a turbine 38 to perform work.
The condenser 39 removes heat from seawater from the circulating water pump 40 to form cooling water, and the condensate pump 41, the low-pressure feed water heater 42,
It is a system for supplying water to a nuclear reactor via a water supply pump 43 and a high-pressure water heater 44. However, this normal system is isolated from the reactor because the MSIV 20 is closed by the reactor isolation signal. In this case, as the core cooling, the reactor isolation cooling system (hereinafter abbreviated as RCIC) shown in FIG. 15 operates, the RCIC turbine 45 driven by the reactor steam drives the RCIC pump 46, and the condensate storage tank 47.
Water (hereinafter abbreviated as CST) or suppression pool 9 (hereinafter abbreviated as S / P) water is injected into the reactor pressure vessel 1, and the RCIC turbine exhaust is guided to the S / P 9.
Further, the relief valve function of the SRV 21 operates to reduce the reactor pressure. The relief valve function is a function that opens the SRV 21 when the set reactor pressure is reached.
The V exhaust pipe is led to S / P 9 and condenses the reactor steam.
【０００８】以上より、原子炉隔離時には原子炉の冷却
後、崩壊熱は徐々にＳＲＶ２１によりＳ／Ｐ９へ移行す
る。この場合、残留熱除去系（以下ＲＨＲと略す。）の
Ｓ／Ｐ冷却モードにより、Ｓ／Ｐ水の崩壊熱を残留熱除
去ポンプ４８により残留熱除去熱交換器４９を介し冷却
する。残留熱除熱交換器４９は、残留熱除去中間冷却ポ
ンプ５０により冷却され、崩壊熱は残留熱除却海水熱交
換器５１を介し海水へ導かれる。残留熱除去海水熱交換
器５１への海水は、残留熱除却海水ポンプ５２により供
給される。そして、このＲＨＲシステムはＡ系、Ｂ系２
系統で構成されている。From the above, after the reactor is cooled at the time of reactor isolation, the decay heat gradually shifts to S / P9 by SRV21. In this case, the decay heat of the S / P water is cooled by the residual heat removal pump 48 via the residual heat removal heat exchanger 49 by the S / P cooling mode of the residual heat removal system (hereinafter abbreviated as RHR). The residual heat removal heat exchanger 49 is cooled by the residual heat removal intermediate cooling pump 50, and the decay heat is guided to seawater through the residual heat removal seawater heat exchanger 51. Seawater to the residual heat removal seawater heat exchanger 51 is supplied by the residual heat removal seawater pump 52. And this RHR system is A system, B system 2
It is composed of a system.
【０００９】なお、この種の装置として関連するものに
は、たとえば特開昭５９−４６５９６号公報および特開
昭５８−１１７４９６号公報が挙げられる。Examples of devices related to this type include, for example, JP-A-59-46596 and JP-A-58-117496.
【００１０】[0010]
【発明が解決しようとする課題】上記従来技術は、炉心
冷却・除熱システムにおいても、原子炉格納容器では、
ＲＨＲによる崩壊熱除去の機能を要求される時点を超え
ると、Ｓ／Ｐ９水の温度が上昇し、図１５に示す原子炉
格納容器（ウエットウェル）７の圧力が上昇し、真空破
壊弁８が作動し原子炉格納容器（ドライウェル）１３の
圧力が同様に上昇するため、従来装置の原子炉格納容器
内の空気作動弁は排圧の影響を受けるので、動的な作動
が困難となる。この場合、この条件下におけるＭＳＩＶ
２０、ＳＲＶ２１の動的作動要求としては、原子炉隔離
解除後であればＭＳＩＶ２０を開作動させ、タービン系
を崩壊熱除去の機能で使用すること、またＳＲＶ２１の
逃がし弁機能及びＡＤＳ機能によりＳ／Ｐ９へ崩壊熱を
移行することが困難となる。図１６に仮想的に崩壊熱除
去の作動を遅らした条件での原子炉格納器内圧力の時間
変化と、ＭＳＩＶ、ＳＲＶの動的作動不良の関係を示
す。ＭＳＩＶの場合は、Ｔ1 からＴ2 間では原子炉格納
容器内圧の影響で作動時間が遅れ、Ｔ2 以降では原子炉
格納容器内圧が弁駆動空気圧以上となるため作動不良を
発生する。ＳＲＶでは、Ｔ2以降では逃がし弁機能用の
駆動空気圧力に原子炉格納器内圧が到達するため逃がし
弁機能が作動不良となる。同様に、Ｔ3 以降ではＡＤＳ
機能が作動不良となる。そのため、圧力上昇条件下の原
子炉格納容器内に従来の装置であるＭＳＩＶ，ＳＲＶを
設置した場合、原子炉隔離時等において原子炉格納容器
内の圧力が上昇すれば、空気作動弁の背圧として影響
し、その状態で動的作動要求のあるシステムの空気作動
弁であれば動的作動不良となり、空気作動弁の関連シス
テムも同様に機能を達成できない可能性があった。SUMMARY OF THE INVENTION The above-mentioned prior art is also related to the core cooling / heat removal system in the reactor containment vessel.
When the function of removing decay heat by RHR is exceeded, the temperature of the S / P9 water rises, the pressure of the reactor containment vessel (wet well) 7 shown in FIG. 15 rises, and the vacuum break valve 8 Since the pressure of the reactor containment vessel (dry well) 13 is similarly activated and rises, the air actuated valve in the reactor containment vessel of the conventional apparatus is affected by the exhaust pressure, which makes dynamic operation difficult. In this case, the MSIV under this condition
20, SRV21 dynamic operation request is to open MSIV20 after reactor isolation is released and use turbine system for decay heat removal function, and SRV21 relief valve function and ADS function for S / S It becomes difficult to transfer the decay heat to P9. FIG. 16 shows the relationship between the temporal change in the pressure inside the reactor containment and the dynamic malfunction of MSIV and SRV under the condition that the decay heat removal operation is virtually delayed. In the case of MSIV, the operating time is delayed between T 1 and T 2 due to the influence of the internal pressure of the reactor containment vessel, and after T 2 the internal pressure of the reactor containment vessel becomes equal to or higher than the valve drive air pressure, causing malfunction. In SRV, the internal pressure of the reactor containment reaches the drive air pressure for the relief valve function after T 2 , so that the relief valve function fails. Similarly, after T 3 , ADS
The function is malfunctioning. Therefore, if MSIV and SRV, which are conventional devices, are installed in the reactor containment vessel under the pressure increase condition, if the pressure in the reactor containment vessel rises at the time of reactor isolation, etc., the back pressure of the air operated valve will increase. As a result, if the air-operated valve of a system that requires a dynamic operation is in that state, the dynamic operation may be defective, and the related system of the air-operated valve may not be able to achieve the same function.
【００１１】本発明の目的は、原子炉格納容器内の圧力
上昇による背圧の影響を受けることなく常に安定した作
動特性を可能とする空気作動弁を提供することにある。An object of the present invention is to provide an air actuated valve which can always have stable operation characteristics without being affected by back pressure due to a pressure increase in the reactor containment vessel.
【００１２】[0012]
【課題を解決するための手段】上記目的を達成するため
に第１の発明は、沸騰水型原子炉の原子炉格納容器内に
設置し、供給側を駆動空気供給ラインを介して外部に設
置した空気供給源に接続するとともに、排出側を上記原
子炉格納容器内に開口する駆動空気切換回路と該駆動空
気切換回路に接続する空気シリンダによって駆動される
空気作動弁において、前記駆動空気切換回路の排出側に
一端部が接続し、他端部が前記原子炉格納容器外に開口
する空気排出ラインを設けたものである。In order to achieve the above object, a first invention is to install in a reactor containment vessel of a boiling water reactor, and to install the supply side outside through a drive air supply line. A drive air switching circuit which is connected to the above air supply source and whose discharge side is opened into the reactor containment vessel and an air operated valve which is driven by an air cylinder connected to the drive air switching circuit. An air discharge line is provided, one end of which is connected to the discharge side and the other end of which is open to the outside of the reactor containment vessel.
【００１３】また、上記目的を達成するために、第２の
発明は、沸騰水型原子炉の原子炉格納容器内に設置し、
供給側を駆動空気供給ラインを介して外部に設置した空
気供給源に接続するとともに、排出側を上記原子炉格納
容器内に開口する駆動空気切換回路と該駆動空気切換回
路に接続する空気シリンダによって駆動される空気作動
弁において、前記駆動空気切換回路の排出側に一端部が
接続し、他端部が前記原子炉格納容器外に開口する空気
排出ラインを設け、かつ上記空気排出ラインに、上記原
子炉格納容器内の圧力に応じて、上記駆動空気切換回路
からの排出空気を上記空気排出ラインを通って上記原子
炉格納容器外に排出するかもしくは上記排出ラインより
分岐して上記原子炉格納容器内に排出するかを切換える
切換手段を設けたものである。In order to achieve the above object, the second invention is to install the reactor in a reactor containment vessel of a boiling water reactor.
The supply side is connected to an air supply source installed outside through a drive air supply line, and the discharge side is opened by a drive air switching circuit opening into the reactor containment vessel and an air cylinder connected to the drive air switching circuit. In the driven air actuated valve, one end is connected to the discharge side of the drive air switching circuit, and the other end is provided with an air discharge line opening to the outside of the reactor containment vessel, and the air discharge line includes Depending on the pressure in the reactor containment vessel, the exhaust air from the drive air switching circuit is discharged to the outside of the reactor containment vessel through the air discharge line or is branched from the discharge line to contain the reactor. A switching means for switching whether to discharge into the container is provided.
【００１４】また、第３の発明の、前記切換手段は、前
記空気排出ラインの前記原子炉格納容器内に設置した三
方弁と、上記原子炉格納容器外に設置した止め弁を設
け、かつ上記三方弁には、先端部を上記原子炉格納容器
内に開口する検出路に圧力計とインターロックを設ける
とともに、該三方弁の一方端部には先端部を上記原子炉
格納容器内に開口する空気排出路に空気排出絞り弁を設
け、かつ上記止め弁には先端部を上記検出路に接続する
検出バイパス路を設けたものである。Further, the switching means of the third invention is provided with a three-way valve installed inside the reactor containment vessel of the air discharge line and a stop valve installed outside the reactor containment vessel, and The three-way valve is provided with a pressure gauge and an interlock in a detection path whose tip opens into the reactor containment vessel, and one end of the three-way valve has a tip open into the reactor containment vessel. An air exhaust throttle valve is provided in the air exhaust passage, and a detection bypass passage is connected to the stop valve at its tip end to the detection passage.
【００１５】また第４の発明の前記空気排出路は、逃し
弁を設けたものである。The air discharge passage of the fourth invention is provided with a relief valve.
【００１６】[0016]
【作用】第１の発明によれば、空気作動弁を駆動する駆
動空気切換回路の排出側に一端部が接続し、他端部が原
子炉格納容器外に開口する空気排出ラインを設けたの
で、空気作動弁は、上記原子炉格納容器内の圧力に影響
されることなく常に安定した作動特性で作動することが
できる。また原子炉格納容器内の圧力が上昇条件下で動
的作業が要求されるＭＳＩＶ，ＳＲＶについては、動的
作動の要求を満足することができ、ＭＳＩＶ，ＳＲＶの
関連システムについても機能を維持することができる。According to the first aspect of the invention, one end is connected to the discharge side of the drive air switching circuit that drives the air actuated valve, and the other end is provided with an air discharge line that opens outside the reactor containment vessel. The air operated valve can always operate with stable operation characteristics without being affected by the pressure in the reactor containment vessel. Further, for MSIVs and SRVs that require dynamic work under conditions where the pressure inside the reactor containment vessel rises, the requirements for dynamic operation can be satisfied, and the functions of the related systems of MSIVs and SRVs are maintained. be able to.
【００１７】第２の発明によれば、空気排出ラインに原
子炉格納容器内の圧力に応じて駆動空気切換回路からの
排出空気を上記空気排出ラインを通って上記原子炉格納
容器外に排出するかもしくは上記空気排出ラインより分
岐して上記原子炉格納容器内に排出するかを切換える切
換手段を設けたので、空気作動弁の定期試験時には駆動
空気源の窒素を原子炉格納容器内に排出することができ
る。According to the second invention, the exhaust air from the drive air switching circuit is discharged to the outside of the reactor containment vessel through the air discharge line according to the pressure inside the reactor containment vessel. Alternatively, since switching means is provided for switching between discharging from the air discharge line and discharging into the reactor containment vessel, nitrogen of the drive air source is discharged into the reactor containment vessel during a periodic test of the air operated valve. be able to.
【００１８】また第３の発明によれば切換手段は、前記
空気排出ラインの前記原子炉格納容器内に設置した三方
弁と、上記原子炉格納容器外に設置した止め弁を設け、
かつ上記三方弁には、先端部を上記原子炉格納容器内に
開口する検出通路に圧力計とインターロックを設けると
ともに、該三方弁の一方端部には先端部を上記原子炉格
納容器内に開口する空気排出路に空気排出絞り弁を設
け、かつ上記止め弁には先端部を上記検出路に接続する
検出バイパス路を設けたので、原子炉格納容器内に圧力
に応じて三方弁が切換えられ、駆動空気切換回路の排出
側から排出空気を原子炉格納容器外もしくは内に排出す
ることができ、かつ空気排出絞り弁によって原子炉格納
容器内に排出される作動抵抗を原子炉格納容器外に排出
されるときと等しくすることができる。According to the third invention, the switching means is provided with a three-way valve installed inside the reactor containment vessel of the air discharge line and a stop valve installed outside the reactor containment vessel.
Further, the three-way valve is provided with a pressure gauge and an interlock in a detection passage having a tip opening into the reactor containment vessel, and a tip part is provided at one end of the three-way valve into the reactor containment vessel. An air discharge throttle valve was provided in the open air discharge path, and a detection bypass path was connected to the stop valve to connect the tip to the detection path.Therefore, a three-way valve was switched in the reactor containment vessel according to the pressure. The exhaust air can be discharged to the outside or inside of the reactor containment vessel from the discharge side of the drive air switching circuit, and the operating resistance discharged to the inside of the reactor containment vessel by the air discharge throttle valve Can be equal to when discharged to.
【００１９】また、第４の発明によれば、空気排出路に
逃がし弁を設けたので、空気排出絞り弁の開け忘れを防
止することができる。According to the fourth aspect of the invention, since the relief valve is provided in the air discharge passage, it is possible to prevent forgetting to open the air discharge throttle valve.
【００２０】[0020]
【実施例】以下、本発明の一実施例を示す図１乃至図１
２について説明する。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENT An embodiment of the present invention will be described below with reference to FIGS.
2 will be described.
【００２１】図１に示すように、原子炉格納容器２内の
空気作動弁３は駆動空気切換回路５の原子炉格納容器２
内への駆動空気原子炉建屋内の排出出口から原子炉格納
容器２外への大気開放状態へと導く排気ライン１７に設
置している。As shown in FIG. 1, the air actuated valve 3 in the reactor containment vessel 2 is a drive air switching circuit 5 of the reactor containment vessel 2.
It is installed in the exhaust line 17 that leads from the discharge outlet inside the drive air inside the reactor building to the atmosphere open to the outside of the reactor containment vessel 2.
【００２２】また、排気ライン１７は原子炉格納容器２
を貫通した下流に止め弁１６を設置している。The exhaust line 17 is connected to the reactor containment vessel 2
A stop valve 16 is installed downstream of the valve.
【００２３】さらに、原子炉格納容器２が通常状態では
駆動空気が窒素ガスであるため、原子炉格納容器２内に
排出し、原子炉格納容器２の圧力が上昇した場合、原子
炉格納容器の圧力計１１からの圧力信号にてインタロッ
ク５９を介して排出ライン１７を、原子炉格納容器２外
へ切り替える。そのために、排出ライン１７の原子炉格
納容器２内側は三方弁１５を設置する。Further, when the reactor containment vessel 2 is in a normal state, the driving air is nitrogen gas. Therefore, when the reactor containment vessel 2 is discharged into the reactor containment vessel 2 and the pressure of the reactor containment vessel 2 increases, The discharge line 17 is switched to the outside of the reactor containment vessel 2 via the interlock 59 by the pressure signal from the pressure gauge 11. Therefore, a three-way valve 15 is installed inside the reactor containment vessel 2 of the discharge line 17.
【００２４】そして、排気ライン１７の接続が原子炉格
納容器２内または外であっても空気作動弁３の作動特性
を等しくするため、排気絞り弁１８を設置している。排
気ライン１７の設置については、作動抵抗を少なくする
ため、極力短いラインとし、空気作動弁３の空気シリン
ダ４の容量に合わせライン口径を選定する。また、排気
絞り弁１８の閉め忘れによる作動不良を防止する目的
で、逃がし弁１９を設置したものである。An exhaust throttle valve 18 is provided in order to equalize the operating characteristics of the air operated valve 3 even if the exhaust line 17 is connected inside or outside the reactor containment vessel 2. The exhaust line 17 is installed as short as possible in order to reduce the operating resistance, and the line diameter is selected according to the capacity of the air cylinder 4 of the air operated valve 3. A relief valve 19 is provided for the purpose of preventing malfunction due to forgetting to close the exhaust throttle valve 18.
【００２５】つぎに図２〜図１２に示す実施例は、本発
明をＭＳＩＶに適用したものである。ＭＳＩＶの閉動作
時には、駆動空気切換回路の急速閉回路とテスト閉（９
０％閉）回路を有している。ＭＳＩＶの駆動空気切換回
路の急速弁閉状態を図１０に示す。同図に示すように、
急速閉回路は、メインコントロール用電磁弁（１）２４
及び（２）２５を無励磁にすることにより、作動供給空
気源よりの窒素ガスが遮断され、空気切換弁（１）２６
及び空気切換弁（４）３０へ供給した窒素ガスも排出さ
れる。そのため、空気切換弁（１）２６が切り換えられ
空気シリンダ４下部の窒素ガスは排出される。同様に、
空気切換弁（４）３０が切り換えられ空気シリンダ４上
部に窒素ガスがアキュムレータ６より供給される。ま
た、空気切換弁（４）３０が切り換えられると空気切換
弁（３）２９が切り換わり、空気シリンダ４下部への窒
素ガスの供給を遮断し、逆に空気シリンダ４下部の窒素
ガスを排出する。つぎにテスト閉状態を示す。テスト閉
回路は、テストコントロール用電磁弁２３を励磁させる
ことにより、空気切換弁（２）２７が切り換わり空気シ
リンダ４下部の窒素ガスはニードル弁（１）３２を通り
排気される。ニードル弁（１）３２により絞られるた
め、微速閉作動となる。Next, the embodiment shown in FIGS. 2 to 12 is one in which the present invention is applied to MSIV. During the closing operation of the MSIV, the quick closing circuit of the drive air switching circuit and the test closing (9
0% closed) circuit. FIG. 10 shows a quick valve closed state of the drive air switching circuit of the MSIV. As shown in the figure,
The quick closing circuit is the solenoid valve (1) 24 for main control.
And (2) 25 are de-energized, the nitrogen gas from the working supply air source is shut off, and the air switching valve (1) 26
Also, the nitrogen gas supplied to the air switching valve (4) 30 is discharged. Therefore, the air switching valve (1) 26 is switched and the nitrogen gas under the air cylinder 4 is discharged. Similarly,
The air switching valve (4) 30 is switched and nitrogen gas is supplied from the accumulator 6 to the upper portion of the air cylinder 4. Further, when the air switching valve (4) 30 is switched, the air switching valve (3) 29 is switched to cut off the supply of nitrogen gas to the lower portion of the air cylinder 4, and conversely discharge the nitrogen gas at the lower portion of the air cylinder 4. .. Next, the test closed state is shown. In the test closed circuit, by exciting the test control solenoid valve 23, the air switching valve (2) 27 is switched and nitrogen gas under the air cylinder 4 is exhausted through the needle valve (1) 32. Since it is throttled by the needle valve (1) 32, it operates at a slow speed.
【００２６】そして、ＭＳＩＶの弁開状態を第９図に示
す。開作動時には、メインコントロール用電磁弁（１）
２４又は（２）２５が励磁することにより空気切換弁
（１）２６及び空気切換弁（４）３０へ窒素ガスが供給
される。空気切換弁（４）３０が切り換えられ空気シリ
ンダ４上部の窒素ガスはニードル弁（２）３３を通り排
気される。ニードル弁（２）３３により絞られるため、
開作動時間が制御される。また、空気切換弁（１）２６
が切り換えられ空気シリンダ４下部の排出ラインは遮断
され、空気切換弁（４）３０が切り換えられたことによ
り空気切換弁（５）２９が切り換わり、アキュムレータ
６より窒素ガスが空気シリンダ４下部へ供給されたＭＳ
ＩＶは開作動する。The open state of the MSIV valve is shown in FIG. Solenoid valve for main control (1) when opening
When 24 or (2) 25 is excited, nitrogen gas is supplied to the air switching valve (1) 26 and the air switching valve (4) 30. The air switching valve (4) 30 is switched and the nitrogen gas above the air cylinder 4 is exhausted through the needle valve (2) 33. Since it is throttled by the needle valve (2) 33,
The opening operation time is controlled. In addition, the air switching valve (1) 26
Is switched to shut off the discharge line below the air cylinder 4, and the air switching valve (4) 30 is switched to switch the air switching valve (5) 29, and nitrogen gas is supplied from the accumulator 6 to the lower portion of the air cylinder 4. MS
The IV opens.
【００２７】以上の駆動空気切換回路のうちテスト閉
（９０％閉）回路を除き原子炉格納容器圧力上昇時に作
動を要求されるため、及びに示すごとく原子炉格納容器
内に空気切換回路より窒素ガスを排出する出口には、排
気ライン１７を設置する。第２図は閉作動時、第３図は
開作動時を示す。この排気ライン１７は、原子炉格納容
器２内に三方弁５３、５４を２個原子炉格納容器２外に
止め弁５５、５６を２個、並列に設置し、排気ライン１
７は原子炉格納容器２外へ原子炉建屋内に開放される。
三方弁５３、５４は、第７図に示すごとく、原子炉格納
容器２の圧力計１１より圧力高信号を受けた場合のみ原
子炉格納容器２外へ接続され、それ以外は原子炉格納容
器２内へ排出ラインとなる。止め弁５５、５６は、原子
炉格納容器２の圧力計１１より原子炉格納容器圧力高信
号を受けた場合のみ開となり、原子炉建屋内に開放す
る。この原子炉格納容器２の圧力高信号による三方弁５
３、５４と止め弁５５、５６のインタロックを図１７に
示す、この制御は図１７に示すように、スイッチ６０を
通常入に設定し、原子炉格納容器２内の圧力高にて停止
して三方弁５３、５４、止め弁５５、５６が無励磁とな
り、原子炉格納容器２内もしくは容器外へと排出とな
る。また運転員がスイッチ６０を切とすれば、強制的に
排気ライン１７を原子炉格納容器２の外方に接続でき、
三方弁５３、５４、止め弁５５、５６の作動もテストで
きる。そして、三方弁５３、５４は、通常時には原子炉
格納容器２内の排気ライン１７に接続されており、この
原子炉格納容器２内の排気ラインは、原子炉格納容器２
外への排気ラインと作動抵抗を等しくする目的で排気絞
り弁１８を設置する。そして、排気絞り弁１８の開け忘
れを防止する目的で、逃がし弁１９を設置する。次に、
三方弁５３、５４及び止め弁５５、５６の電源について
は、工学的安全施設に関連するので三方弁５３と５４、
止め弁５５と５６のうち、三方弁５３と止め弁５５につ
いては非常用区分Ｉ、三方弁５４と止め弁５６について
は非常用区分ＩＩより受電する。Of the drive air switching circuits described above, except for the test closed (90% closed) circuit, operation is required when the reactor containment vessel pressure rises. An exhaust line 17 is installed at the outlet for discharging gas. 2 shows the closing operation, and FIG. 3 shows the opening operation. In this exhaust line 17, two three-way valves 53 and 54 are installed inside the reactor containment vessel 2 and two stop valves 55 and 56 are installed outside the reactor containment vessel 2 in parallel.
7 is opened to the outside of the PCV 2 and inside the reactor building.
As shown in FIG. 7, the three-way valves 53 and 54 are connected to the outside of the reactor containment vessel 2 only when a high pressure signal is received from the pressure gauge 11 of the reactor containment vessel 2, and otherwise the reactor containment vessel 2 is connected. It becomes an inward discharge line. The stop valves 55 and 56 are opened only when a high pressure signal of the reactor containment vessel is received from the pressure gauge 11 of the reactor containment vessel 2, and are opened in the reactor building. Three-way valve 5 based on the high pressure signal in the PCV 2
17, the interlocks of the stop valves 55 and 56 are shown in FIG. 17. This control is performed by setting the switch 60 to the normal ON state as shown in FIG. 17 and stopping at the high pressure in the reactor containment vessel 2. As a result, the three-way valves 53, 54 and the stop valves 55, 56 are de-energized and discharged into or out of the reactor containment vessel 2. If the operator turns off the switch 60, the exhaust line 17 can be forcibly connected to the outside of the reactor containment vessel 2,
The operation of the three-way valves 53, 54 and stop valves 55, 56 can also be tested. The three-way valves 53, 54 are normally connected to the exhaust line 17 in the reactor containment vessel 2, and the exhaust line in this reactor containment vessel 2 is
An exhaust throttle valve 18 is installed for the purpose of making the operating resistance equal to that of the exhaust line to the outside. A relief valve 19 is provided for the purpose of preventing the exhaust throttle valve 18 from being left open. next,
Regarding the power sources of the three-way valves 53, 54 and the stop valves 55, 56, the three-way valves 53 and 54, because they are related to engineering safety facilities,
Of the stop valves 55 and 56, the three-way valve 53 and the stop valve 55 receive power from the emergency section I, and the three-way valve 54 and the stop valve 56 receive power from the emergency section II.
【００２８】また、ＭＳＩＶの閉鎖時間はオイルシリン
ダ２２のニードル弁（３）３４にて、閉鎖時間を調整で
きるため、排気ライン１７を接続後には排気ライン１７
の作動抵抗により閉鎖時間が長くなるため、ニードル弁
（３）３４を調整し適切な閉鎖時間に設定する。Since the closing time of the MSIV can be adjusted by the needle valve (3) 34 of the oil cylinder 22, the exhaust line 17 can be adjusted after the exhaust line 17 is connected.
Since the closing time becomes longer due to the operation resistance of (3), the needle valve (3) 34 is adjusted and set to an appropriate closing time.
【００２９】したがって、上記の場合には、通常時、排
気ライン１７は図７に示すごとく、三方弁５３、５４に
より原子炉格納容器内に駆動用の窒素ガスを排出する。Therefore, in the above case, the exhaust line 17 normally discharges the driving nitrogen gas into the reactor containment vessel by the three-way valves 53 and 54 as shown in FIG.
【００３０】つぎに他の実施例を示す図１３および図１
４について説明する。本実施例は本発明をＳＲＶに適用
した場合を示す。ＳＲＶの開作動時には駆動切換回路は
逃がし弁機能用とＡＤＳ機能用を持っている。逃がし弁
機能用としてＳＲＶが作動する場合は、図１３に示すご
とく、逃がし弁機能用電磁弁３５が励磁し駆動用の窒素
ガスがアキュムレータ６より空気シリンダ４の下部へ供
給され、空気シリンダ４上部の窒素ガスは原子炉格納容
器内に排出される。つぎに、ＡＤＳ機能用としてＳＲＶ
が作動する場合は、図１４に示すごとく、ＡＤＳ機能用
電磁弁（１）３６またはＡＤＳ機能用電磁弁（２）３７
を励磁し駆動用の窒素ガスがアキュムレータ６より空気
シリンダ４の下部へ供給され、空気シリンダ４上部の窒
素ガスは原子炉格納容器内に排出される。Next, FIG. 13 and FIG. 1 showing another embodiment.
4 will be described. This embodiment shows a case where the present invention is applied to SRV. The drive switching circuit has a relief valve function and an ADS function when the SRV is opened. When the SRV operates for the relief valve function, as shown in FIG. 13, the relief valve function solenoid valve 35 is excited to supply the driving nitrogen gas from the accumulator 6 to the lower portion of the air cylinder 4 and the upper portion of the air cylinder 4. Nitrogen gas is discharged into the reactor containment vessel. Next, SRV for ADS function
14 operates, as shown in FIG. 14, the ADS function solenoid valve (1) 36 or the ADS function solenoid valve (2) 37.
The driving nitrogen gas is supplied from the accumulator 6 to the lower part of the air cylinder 4, and the nitrogen gas above the air cylinder 4 is discharged into the reactor containment vessel.
【００３１】ＳＲＶの閉作動時には、駆動切換回路は図
１２に示すごとく、逃がし弁機能用電磁弁３５、ＡＤＳ
機能用電磁弁（１）３６及びＡＤＳ機能用電磁弁（２）
３７は無励磁となり、空気シリンダ４下部の窒素ガスは
原子炉格納容器内へ排出され、空気シリンダ４はバネ５
７の力によりピストン５８を下部へ移動させる。When the SRV is closed, the drive switching circuit, as shown in FIG. 12, includes the relief valve function solenoid valve 35 and the ADS.
Solenoid valve for function (1) 36 and solenoid valve for ADS function (2)
37 is non-excited, the nitrogen gas under the air cylinder 4 is discharged into the reactor containment vessel, and the air cylinder 4 is replaced by the spring 5
The force of 7 moves the piston 58 downward.
【００３２】以上の駆動空気切換回路において図４〜図
６に示すように、原子炉格納容器への排出口並びに空気
シリンダ４上部出口に排気ライン１７を設定する。図４
は逃がし弁機能説明図、図５はＡＤＳ機能作動時、およ
び図６は閉作動時を示す。この排気ライン１７は、原子
炉格納容器２内に三方弁５３、５４を２個、原子炉格納
容器２外に止め弁５５、５６を２個、並列に設置し、排
気ライン１７は原子炉格納容器２外の原子炉建屋内に開
放される。この三方弁５３、５４と止め弁５５、５６
は、実施例１のＭＳＩＶと同様の構成、機能を有する。In the above drive air switching circuit, as shown in FIGS. 4 to 6, an exhaust line 17 is set at the exhaust port to the reactor containment vessel and the upper outlet of the air cylinder 4. Figure 4
Shows the relief valve function, FIG. 5 shows the ADS function operating, and FIG. 6 shows the closing operating. This exhaust line 17 is provided with two three-way valves 53, 54 inside the reactor containment vessel 2 and two stop valves 55, 56 outside the reactor containment vessel 2 in parallel. It is opened inside the reactor building outside the container 2. These three-way valves 53, 54 and stop valves 55, 56
Has the same configuration and function as the MSIV of the first embodiment.
【００３３】この実施例２によれば、通常時には排気ラ
イン１７は第７図に示すごとく、三方弁５３、５４によ
り原子炉格納容器内に駆動用の窒素ガスを排出する。つ
ぎに、原子炉格納容器の圧力が上昇した時点で図７に示
すごとく圧力計１１より原子炉格納容器圧力高信号が発
生し、ＳＲＶの排気ライン１７は原子炉格納容器外に切
り替えられるため、原子炉格納容器内圧による排圧は除
外される。よって、ＳＲＶは通常時の作動特性を有し原
子炉格納容器圧力高条件下で通常時と同等の機能を有す
る効果が期待できる。According to the second embodiment, the exhaust line 17 normally discharges the driving nitrogen gas into the reactor containment vessel by the three-way valves 53 and 54 as shown in FIG. Next, when the pressure of the reactor containment vessel rises, a pressure gauge 11 high pressure signal is generated from the pressure gauge 11 as shown in FIG. 7, and the SRV exhaust line 17 is switched to the outside of the reactor containment vessel. Exhaust pressure due to reactor internal pressure is excluded. Therefore, it is expected that the SRV has the operating characteristics under normal conditions and has the function equivalent to that under normal conditions under the high reactor containment vessel pressure conditions.
【００３４】[0034]
【発明の効果】第１の発明によれば、空気作動弁を駆動
する駆動空気切換回路の排出側に一端部が接続し、他端
部が原子炉格納容器外に開口する空気排出ラインを設け
たので、空気作動弁は、上記原子炉格納容器内の圧力に
影響されることなく常に安定した作動特性で作動するこ
とができる。また原子炉格納容器内の圧力が上昇条件下
で動的作業が要求されるＭＳＩＶ、ＳＲＶについては、
動的作動の要求を満足することができ、ＭＳＩＶ、ＳＲ
Ｖの関連システムについても機能を維持することができ
る。According to the first aspect of the invention, an air discharge line is provided, one end of which is connected to the discharge side of the drive air switching circuit that drives the air actuated valve, and the other end of which is open to the outside of the reactor containment vessel. Therefore, the air operated valve can always operate with stable operation characteristics without being affected by the pressure in the reactor containment vessel. Regarding MSIV and SRV, which require dynamic work under the condition that the pressure inside the PCV rises,
Can meet the requirements of dynamic operation, MSIV, SR
The function can be maintained for the V related system.
【００３５】第２の発明によれば、空気排出ラインに原
子炉格納容器内の圧力に応じて駆動空気切換回路からの
排出空気を上記空気排出ラインを通って上記原子炉格納
容器外に排出するか、もしくは上記空気排出ラインより
分岐して上記原子路格納容器内に排出するかを切換える
切換手段を設けたので、空気作動弁の定期試験時には駆
動空気源の窒素を原子路格納容器内に排出することがで
きる。According to the second aspect of the invention, the exhaust air from the drive air switching circuit is discharged to the outside of the reactor containment vessel through the air discharge line in accordance with the pressure inside the reactor containment vessel. Since a switching means is provided for switching between discharging from the air discharge line and discharging into the atomic path containment vessel, nitrogen of the driving air source is discharged into the atomic path containment vessel during a periodic test of the air operated valve. can do.
【００３６】また第３の発明によれば切換手段は、前記
空気排出ラインの前記原子炉格納容器内に設置した三方
弁と、上記原子炉格納容器外に設置した止め弁を設け、
かつ上記三方弁には、先端部を上記原子炉格納容器内に
開口する検出通路に圧力計とインターロックを設けると
ともに、該三方弁の一方端部には先端部を上記原子炉格
納容器内に開口する空気排出路に空気排出絞り弁を設
け、かつ上記止め弁には先端部を上記検出路に接続する
検出バイパス路を設けたので、原子炉格納容器内に圧力
に応じて三方弁が切換えられ、駆動空気切換回路の排出
側から排出空気を原子炉格納容器外もしくは内に排出す
ることができ、かつ空気排出絞り弁によって原子炉格納
容器内に排出される作動抵抗を原子炉格納容器外に排出
されるときと等しくすることができる。According to the third invention, the switching means is provided with a three-way valve installed inside the reactor containment vessel of the air discharge line, and a stop valve installed outside the reactor containment vessel.
Further, the three-way valve is provided with a pressure gauge and an interlock in a detection passage having a tip opening into the reactor containment vessel, and a tip part is provided at one end of the three-way valve into the reactor containment vessel. An air discharge throttle valve was provided in the open air discharge passage, and a detection bypass passage was connected to the stop valve to connect the tip to the detection passage.Therefore, a three-way valve was switched in the reactor containment vessel according to the pressure. The exhaust air can be discharged to the outside or inside of the reactor containment vessel from the discharge side of the drive air switching circuit, and the operating resistance discharged to the inside of the reactor containment vessel by the air discharge throttle valve Can be equal to when discharged to.
【００３７】また、第４の発明によれば、空気排出路に
逃がし弁を設けたので、空気排出絞り弁の開け忘れを防
止することができる。Further, according to the fourth aspect of the invention, since the relief valve is provided in the air discharge passage, it is possible to prevent forgetting to open the air discharge throttle valve.
【図１】本発明による原子炉格納容器内の空気作動弁を
示す説明図FIG. 1 is an explanatory view showing an air operated valve in a reactor containment vessel according to the present invention.
【図２】本発明の一実施例であるＭＳＩＶの閉作動時の
駆動空気切換回路図FIG. 2 is a drive air switching circuit diagram at the time of closing operation of the MSIV which is an embodiment of the present invention.
【図３】図２に示すＭＳＩＶの開作動時の駆動空気切換
回路図FIG. 3 is a drive air switching circuit diagram when the MSIV shown in FIG. 2 is opened.
【図４】本発明の他の一実施例であるＳＲＶの逃がし弁
機能における開作動時の駆動空気切換回路図FIG. 4 is a drive air switching circuit diagram at the time of opening operation in the relief valve function of SRV which is another embodiment of the present invention.
【図５】図４に示すＳＲＶのＡＤＳ機能における開作動
時の駆動空気切換回路図FIG. 5 is a drive air switching circuit diagram at the time of opening operation in the ADS function of the SRV shown in FIG.
【図６】図４に示すＳＲＶの閉作動時の駆動空気切換回
路図FIG. 6 is a drive air switching circuit diagram when the SRV shown in FIG. 4 is closed.
【図７】三方弁および止め弁の作動説明図FIG. 7 is an operation explanatory diagram of a three-way valve and a stop valve.
【図８】従来例による原子炉格納容器内の空気作動弁を
示す説明図FIG. 8 is an explanatory view showing an air operated valve in a reactor containment vessel according to a conventional example.
【図９】従来例のＭＳＩＶの開作動時の駆動空気切換回
路図FIG. 9 is a drive air switching circuit diagram when the MSIV of the conventional example is opened.
【図１０】従来例のＭＳＩＶの閉作動時の駆動空気切換
回路図FIG. 10 is a drive air switching circuit diagram at the time of closing operation of a conventional MSIV.
【図１１】従来例のＭＳＩＶのテスト閉時の駆動空気切
換回路図FIG. 11 is a drive air switching circuit diagram when the test of the conventional MSIV is closed.
【図１２】従来例のＳＲＶの閉作動時の空気切換回路図FIG. 12 is an air switching circuit diagram when the SRV of the conventional example is closed.
【図１３】従来例のＳＲＶの逃がし弁機能における開作
動時の空気切換回路図FIG. 13 is an air switching circuit diagram at the time of opening operation in the SRV relief valve function of the conventional example.
【図１４】従来例のＳＲＶのＡＤＳ機能における開作動
時の空気切換回路図FIG. 14 is an air switching circuit diagram at the time of opening operation in the ADS function of the SRV of the conventional example.
【図１５】沸騰水型原子力発電所の炉心冷却・除熱シス
テムの概略図FIG. 15 is a schematic diagram of a core cooling / heat removal system of a boiling water nuclear power plant.
【図１６】仮想的な崩壊熱除去機能作動遅延時の原子炉
格納容器圧力曲線図FIG. 16 is a pressure curve diagram of the containment vessel when the hypothetical decay heat removal function operation is delayed.
【図１７】排気ライン制御インタロックを示すブロック
図FIG. 17 is a block diagram showing an exhaust line control interlock.
１…原子炉圧力容器、２…原子炉格納容器、３…空気作
動弁、４…空気シリンダ、５…駆動空気切換回路、１５
…三方弁、１６…止め弁、１７…排気ライン、５９…イ
ンタロック。DESCRIPTION OF SYMBOLS 1 ... Reactor pressure vessel, 2 ... Reactor containment vessel, 3 ... Air operated valve, 4 ... Air cylinder, 5 ... Driving air switching circuit, 15
... 3-way valve, 16 ... Stop valve, 17 ... Exhaust line, 59 ... Interlock.
Claims (4)
置し、供給側を駆動空気供給ラインを介して外部に設置
した空気供給源に接続するとともに、排出側を上記原子
炉格納容器内に開口する駆動空気切換回路と、該駆動空
気切換回路に接続する空気シリンダによって駆動される
空気作動弁において、前記駆動空気切換回路の排出側に
一端部が接続し、他端部が前記原子炉格納容器外に開口
する空気排出ラインを設けたことを特徴とする空気作動
弁。1. A reactor installed in a boiling water reactor reactor containment vessel, the supply side is connected via a drive air supply line to an air supply source installed outside, and the discharge side is the reactor containment vessel. In a drive air switching circuit opening inside and an air operated valve driven by an air cylinder connected to the drive air switching circuit, one end is connected to the discharge side of the drive air switching circuit and the other end is the atom. An air actuated valve, which is provided with an air discharge line that opens outside the furnace containment vessel.
置し、供給側を駆動空気供給ラインを介して外部に設置
した空気供給源に接続するとともに、排出側を上記原子
炉格納容器内に開口する駆動空気切換回路と、該駆動空
気切換回路に接続する空気シリンダによって駆動される
空気作動弁において、前記駆動空気切換回路の排出側に
一端部が接続し、他端部が前記原子炉格納容器外に開口
する空気排出ラインを設け、かつ上記空気排出ライン
に、上記原子炉格納容器内の圧力に応じて上記駆動空気
切換回路からの排出空気を上記空気排出ラインを通って
上記原子炉格納容器外に排出するかもしくは上記排出ラ
インより分岐して上記原子炉格納容器内に排出するかを
切換える切換手段を設けたことを特徴とする空気作動
弁。2. The reactor is installed in a reactor containment vessel of a boiling water reactor, the supply side is connected via a drive air supply line to an air supply source installed outside, and the discharge side is the reactor containment vessel. In a drive air switching circuit opening inside and an air operated valve driven by an air cylinder connected to the drive air switching circuit, one end is connected to the discharge side of the drive air switching circuit and the other end is the atom. An air discharge line opening to the outside of the reactor containment vessel is provided, and the discharge air from the drive air switching circuit is supplied to the air discharge line through the air discharge line according to the pressure in the reactor containment vessel. An air actuated valve provided with switching means for switching between discharging to the outside of the reactor containment vessel or branching from the discharge line and discharging to the inside of the reactor containment vessel.
前記原子炉格納容器内に設置した三方弁と、上記原子炉
格納容器外に設置した止め弁を設け、かつ上記三方弁に
は、先端部を上記原子炉格納容器内に開口する検出路に
圧力計とインターロックを設けるとともに、該三方弁の
一方端部には先端部を上記原子炉格納容器内に開口する
空気排出路に空気排出絞り弁を設け、かつ上記止め弁に
は先端部を上記検出路に接続する検出バイパス路を設け
たことを特徴とする請求項２記載の空気作動弁。3. The switching means is provided with a three-way valve installed inside the reactor containment vessel of the air discharge line and a stop valve installed outside the reactor containment vessel, and the three-way valve has a tip end. Part is provided with a pressure gauge and an interlock in a detection path opening into the reactor containment vessel, and a tip end of one end of the three-way valve is discharged into an air discharge path opening into the reactor containment vessel. The air actuated valve according to claim 2, wherein a throttle valve is provided, and the stop valve is provided with a detection bypass passage that connects a tip end portion to the detection passage.
を特徴とする請求項３記載の空気作動弁。4. The air actuated valve according to claim 3, wherein the air discharge passage is provided with a relief valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3239895A JP2502224B2 (en) | 1991-09-19 | 1991-09-19 | Air operated valve |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3239895A JP2502224B2 (en) | 1991-09-19 | 1991-09-19 | Air operated valve |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0580191A true JPH0580191A (en) | 1993-04-02 |
| JP2502224B2 JP2502224B2 (en) | 1996-05-29 |
Family
ID=17051458
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP3239895A Expired - Lifetime JP2502224B2 (en) | 1991-09-19 | 1991-09-19 | Air operated valve |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2502224B2 (en) |
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1991
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|---|---|---|---|---|
| US5621281A (en) * | 1994-08-03 | 1997-04-15 | International Business Machines Corporation | Discharge lamp lighting device |
| US6982886B2 (en) | 2002-12-25 | 2006-01-03 | Rohm Co., Ltd | Dc-ac converter parallel operation system and controller ic therefor |
| US7233509B2 (en) | 2002-12-25 | 2007-06-19 | Rohm Co., Ltd. | Parallel operating system of DC-AC converters and controller IC therefor |
| US7471528B2 (en) | 2002-12-25 | 2008-12-30 | Rohm Co., Ltd. | Parallel operating system of DC-AC converters and controller IC therefor |
| WO2008156086A1 (en) * | 2007-06-18 | 2008-12-24 | Kabushiki Kaisha Toshiba | Drive system for safety valve |
| JP4768855B2 (en) * | 2007-06-18 | 2011-09-07 | 株式会社東芝 | Safety valve drive system |
| JP2013140079A (en) * | 2012-01-05 | 2013-07-18 | Hitachi-Ge Nuclear Energy Ltd | Reactor isolation cooler |
| JP2014153257A (en) * | 2013-02-12 | 2014-08-25 | Toshiba Corp | Reactor pressure vessel pressure reduction facility and main steam release safety valve driving unit |
| EP2775180A3 (en) * | 2013-03-06 | 2017-12-20 | Hitachi-GE Nuclear Energy, Ltd. | Alternative air supply and exhaust port for air-operated valve |
| JP2014173723A (en) * | 2013-09-18 | 2014-09-22 | Hitachi-Ge Nuclear Energy Ltd | Remote control device, and remote control device of nuclear power plant |
| JP2015087232A (en) * | 2013-10-30 | 2015-05-07 | 日立Ｇｅニュークリア・エナジー株式会社 | Gas supply apparatus and nuclear power plant air or nitrogen supply apparatus |
| EP2869307A3 (en) * | 2013-10-30 | 2015-06-24 | Hitachi-GE Nuclear Energy, Ltd. | Gas supply apparatus and air or nitrogen supply apparatus of nuclear plant |
| US9916908B2 (en) | 2013-10-30 | 2018-03-13 | Hitachi-Ge Nuclear Energy, Ltd. | Gas supply apparatus and air or nitrogen supply apparatus of nuclear plant |
| JP2015117721A (en) * | 2013-12-17 | 2015-06-25 | 日立Ｇｅニュークリア・エナジー株式会社 | Gas supply apparatus and air or nitrogen supply apparatus of nuclear power plant |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2502224B2 (en) | 1996-05-29 |
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