JPH0434708B2 - - Google Patents
Info
- Publication number
- JPH0434708B2 JPH0434708B2 JP58205904A JP20590483A JPH0434708B2 JP H0434708 B2 JPH0434708 B2 JP H0434708B2 JP 58205904 A JP58205904 A JP 58205904A JP 20590483 A JP20590483 A JP 20590483A JP H0434708 B2 JPH0434708 B2 JP H0434708B2
- Authority
- JP
- Japan
- Prior art keywords
- suppression pool
- temperature
- suppression
- measuring
- flow rate
- 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 - Lifetime
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は沸騰水型原子炉の格納容器内に設置さ
れるサプレツシヨンプールの温度監視装置に関す
る。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a temperature monitoring device for a suppression pool installed in a containment vessel of a boiling water nuclear reactor.
原子炉格納容器内に設置されるサプレツシヨン
プールは、異常過渡時に原子炉の冷却材を最終的
に確保するために設置されるものである。異常過
渡時に原子炉にサプレツシヨンプール内の冷却材
を注入し、原子炉燃料の健全性を確保する残留熱
除去系ポンプの有効NPSHを確保するために、
サプレツシヨンプール水の温度を監視する必要が
ある。
A suppression pool installed inside the reactor containment vessel is installed to ultimately secure coolant for the reactor during abnormal transients. In order to ensure the effective NPSH of the residual heat removal system pump, which injects coolant in the suppression pool into the reactor during abnormal transients and ensures the integrity of the reactor fuel,
Suppression pool water temperature must be monitored.
従来のプラントではサプレツシヨンプール内に
点在する温度測定器によりサプレツシヨンプール
水の温度を監視をしているが、温度測定器を設置
した局所だけの温度測定であり熱伝導による時間
遅れのため各温度測定器の測定値に時間差が出る
ので、サプレツシヨンプール全体の熱容量を把握
できず、サプレツシヨンプール水の温度を正しく
監視しているといえない。また、サプレツシヨン
プール水の温度上昇率の把握も困難である。さら
に、従来プラントではサプレツシヨンプール水の
温度測定値がある設定値に達すると警報を表示し
運転員がサプレツシヨンプール冷却モードを起動
させるため、運転員の見落しなどがあるとサプレ
ツシヨンプール水の温度上昇、ひいては残留熱除
去系ポンプの有効NPSHを確保できなくなりサ
プレツシヨンプール内の冷却材を原子炉に注入で
きないという事態が生じる。特に最近米国で発生
した原子力プラントの放射能洩れ事故を契機とし
て人為的なミスを防ぐため、サプレツシヨンプー
ル内の状態を正確に把握して運転員に的確な情報
を与える温度監視装置の開発の必要性が指摘され
ている。 In conventional plants, the temperature of the suppression pool water is monitored using temperature measuring devices scattered within the suppression pool, but the temperature is only measured in the area where the temperature measuring devices are installed, and there is a time delay due to heat conduction. As a result, there is a time difference in the measured values of each temperature measuring device, making it impossible to grasp the heat capacity of the entire suppression pool, and it cannot be said that the temperature of the suppression pool water is being monitored correctly. Furthermore, it is difficult to grasp the temperature rise rate of the suppression pool water. Furthermore, in conventional plants, when the measured temperature of the suppression pool water reaches a certain set value, an alarm is displayed and the operator activates the suppression pool cooling mode. The temperature of the suppression pool water rises, and as a result, the effective NPSH of the residual heat removal system pump cannot be ensured, resulting in a situation where the coolant in the suppression pool cannot be injected into the reactor. In particular, in order to prevent human error due to the radiation leak accident at a nuclear power plant that recently occurred in the United States, we developed a temperature monitoring device that accurately grasps the conditions inside the suppression pool and provides accurate information to operators. The need for this has been pointed out.
本発明の目的は、異常過渡時に使用される残留
熱除去系ポンプの有効NPSHを正確に確保する
ために異常過渡時のサプレツシヨンプール水の温
度や温度上昇率を把握し、更に一定時間後のサプ
レツシヨンプール内の温度を予測し、この予測さ
れた温度がサプレツシヨンプール冷却モード設定
値に達するとサプレツシヨンプール冷却モードを
起動させる温度監視装置を提供することにある。
The purpose of the present invention is to grasp the temperature and temperature rise rate of the suppression pool water during abnormal transients in order to accurately ensure the effective NPSH of the residual heat removal system pump used during abnormal transients, and to To provide a temperature monitoring device that predicts the temperature in a suppression pool of a person and activates a suppression pool cooling mode when the predicted temperature reaches a suppression pool cooling mode setting value.
すなわち、本発明の特徴はサプレツシヨンプー
ル内に設置される温度測定器と水位測定器で測定
された測定値から演算装置で求まる通常運転時の
サプレツシヨンプール内の熱容量と、異常時運転
時に測定されるサプレツシヨンプール内へ流入す
る流量の温度と流入する流量から演算装置で算出
されるサプレツシヨンプール内へ流入する流量の
熱容量とからサプレツシヨンプール内の温度およ
び温度上昇を算出することにより、残留熱除去系
の有効NPSH確保に支障をきたす前に運転員に
ブラウン管表示、警報表示により注意を促すとと
もに、サプレツシヨンプール冷却モードを自動起
動させることにある。
In other words, the feature of the present invention is that the heat capacity in the suppression pool during normal operation is determined by a calculation device from the values measured by the temperature measuring device and the water level measuring device installed in the suppression pool, and the heat capacity in the suppression pool during abnormal operation is calculated using a calculation device. The temperature and temperature rise in the suppression pool are calculated from the temperature of the flow rate flowing into the suppression pool, which is measured at the same time, and the heat capacity of the flow rate flowing into the suppression pool, which is calculated by a calculation device from the inflow flow rate. By calculating this, it is possible to alert the operator with a cathode ray tube display and an alarm display before the residual heat removal system becomes obstructed in ensuring effective NPSH, and to automatically start the suppression pool cooling mode.
以下本発明の一実施例について図面を参照して
詳細に説明する。第1図において、サプレツシヨ
ンプール1は原子炉圧力容器2を格納する一次格
納容器3内に設置される。通常運転時は原子炉圧
力容器2内で生成された蒸気が主蒸気管4を通り
図示しないタービンに送られる。サプレツシヨン
プール1内の温度はサプレツシヨンプール1内に
点在する温度測定器5で測定され、サプレツシヨ
ンプール1内の水位は水位測定器6によつて測定
される。
An embodiment of the present invention will be described in detail below with reference to the drawings. In FIG. 1, a suppression pool 1 is installed within a primary containment vessel 3 that houses a reactor pressure vessel 2. As shown in FIG. During normal operation, steam generated within the reactor pressure vessel 2 is sent through the main steam pipe 4 to a turbine (not shown). The temperature in the suppression pool 1 is measured by temperature measuring devices 5 scattered within the suppression pool 1, and the water level in the suppression pool 1 is measured by a water level measuring device 6.
異常過渡時には主蒸気隔離弁7を閉めることに
よつて原子炉が隔離されるため、原子炉圧力が上
昇し、かつこの状態では原子炉への給水が停止し
て原子炉水位が低下する。なお、原子炉給水系統
については図示していない。原子炉水位の低下に
より原子炉の炉心の冷却が妨げられるのを防ぐた
め、非常用冷却系の一つである原子炉隔離時冷却
系(以下RCIC)8がRCICタービン止め弁24を
開くことにより起動する。サプレツシヨンプール
1には主蒸気管4からの主蒸気により駆動される
RCICタービン9の排気が流入する。RCICタービ
ン9の排気の流量と温度は、排気管に設けられた
流量センサ10と温度センサ11により測定され
る。 During abnormal transients, the reactor is isolated by closing the main steam isolation valve 7, so the reactor pressure increases, and in this state, water supply to the reactor is stopped and the reactor water level falls. Note that the reactor water supply system is not shown. In order to prevent the cooling of the reactor core from being interrupted due to a drop in the reactor water level, the reactor isolation cooling system (hereinafter referred to as RCIC) 8, which is one of the emergency cooling systems, opens the RCIC turbine stop valve 24. to start. The suppression pool 1 is driven by main steam from the main steam pipe 4.
The exhaust gas of the RCIC turbine 9 flows in. The flow rate and temperature of the exhaust gas from the RCIC turbine 9 are measured by a flow rate sensor 10 and a temperature sensor 11 provided in the exhaust pipe.
また、原子炉圧力の上昇による原子炉圧力容器
2の破損を防ぐため逃がし安全弁12を開いて蒸
気をサプレツシヨンプール1に排気し原子炉圧力
を低下させる。逃がし安全弁12からの排気の流
量と温度は排気管側に設けた流量センサ13と温
度センサ14により得る事ができる。サプレツシ
ヨンプール水の温度が上昇してきた場合、原子炉
水位がさらに低下した場合起動する低圧注水モー
ドでの残留熱除去系ポンプ15の有効NPSHを
確保し、原子炉への冷却材注入を可能とするた
め、残留熱除去系ポンプ15を起動し、サプレツ
シヨンプール水を熱交換器16に送り込み、冷却
水17との熱交換によりサプレツシヨンプール水
を冷却しふたたびサプレツシヨンプール1に流入
することでサプレツシヨンプール1の冷却を行な
うサプレツシヨンプール冷却モードを起動する。
この時サプレツシヨンプールの冷却に用いられる
冷却材の流量と温度は、サプレツシヨンプール1
への流入配管側に設けられた流量センサ18と温
度センサ19により測定される。 In addition, in order to prevent damage to the reactor pressure vessel 2 due to an increase in reactor pressure, the safety relief valve 12 is opened to exhaust steam to the suppression pool 1 and reduce the reactor pressure. The flow rate and temperature of the exhaust gas from the relief safety valve 12 can be obtained by a flow rate sensor 13 and a temperature sensor 14 provided on the exhaust pipe side. When the temperature of the suppression pool water rises, the effective NPSH of the residual heat removal system pump 15 is ensured in the low-pressure water injection mode that is activated when the reactor water level drops further, making it possible to inject coolant into the reactor. In order to do this, the residual heat removal system pump 15 is started, the suppression pool water is sent to the heat exchanger 16, the suppression pool water is cooled by heat exchange with the cooling water 17, and the suppression pool water is returned to the suppression pool 1. A suppression pool cooling mode is started in which the suppression pool 1 is cooled by the inflow.
At this time, the flow rate and temperature of the coolant used to cool the suppression pool are as follows:
The temperature is measured by a flow rate sensor 18 and a temperature sensor 19 provided on the inflow pipe side.
まず、通常運転時のサプレツシヨンプール1内
の熱容量は次の通りに求まる。通常運転時におい
てはサプレツシヨンプール1に流入出する熱量は
なく、サプレツシヨンプール水の温度はほぼ一様
である。従つて温度測定器5による測定値よりサ
プレツシヨンプール水の単位体積当りの熱容量
Q0が次式より求まる。 First, the heat capacity in the suppression pool 1 during normal operation is determined as follows. During normal operation, no amount of heat flows into or out of the suppression pool 1, and the temperature of the suppression pool water is almost uniform. Therefore, from the measured value by the temperature measuring device 5, the heat capacity per unit volume of the suppression pool water is
Q 0 can be found from the following formula.
Q0=K0Ct0 ……(1)
ここでK0は変換定数、Cは比熱、t0は温度測定
値である。またサプレツシヨンプール1の水位測
定器6の測定値とサプレツシヨンプール1の形状
のデータに基づいてサプレツシヨンプール水の体
積W0が得られる。以上の様にサプレツシヨンプ
ール1内の温度と水位を入力として演算装置によ
りサプレツシヨンプール水の単位体積当りの熱容
量Q0と体積W0、さらにサプレツシヨンプール1
内の熱容量Q0W0を求めることができる。 Q 0 =K 0 Ct 0 (1) where K 0 is a conversion constant, C is specific heat, and t 0 is a temperature measurement value. Further, the volume W 0 of the suppression pool water is obtained based on the measurement value of the water level measuring device 6 of the suppression pool 1 and data on the shape of the suppression pool 1. As described above, by inputting the temperature and water level in the suppression pool 1, the calculation device calculates the heat capacity Q 0 and volume W 0 per unit volume of the suppression pool water, and further calculates the heat capacity Q 0 and volume W 0 per unit volume of the suppression pool water.
The heat capacity Q 0 W 0 can be found.
異常過渡時サプレツシヨンプール1に流入する
流体はRCIタービン9の排気と逃がし安全弁12
から排気である。 The fluid flowing into the suppression pool 1 during an abnormal transient is the exhaust gas of the RCI turbine 9 and the relief safety valve 12.
It is exhaust from.
RCICタービン9の排気の流量F1は流量センサ
10の測定値より得られる。排気の温度は温度セ
ンサ11より得られ、これによりRCICタービン
9の排気の単位体積当りの熱容量Q1が求まる。
逃し安全弁12からの排気の流量F2は流量セン
サ13より得られ、温度センサ14より排気の温
度さらに逃し安全弁12からの排気の単位体積当
りの熱容量Q2が計算できる。従つてRCICタービ
ン9の排気と逃し安全弁12からの排気の流入に
よるサプレツシヨンプール水の単位体積当りの熱
容量の増加率△Qは次式で求められる。 The flow rate F 1 of the exhaust gas of the RCIC turbine 9 is obtained from the measurement value of the flow rate sensor 10 . The temperature of the exhaust gas is obtained from the temperature sensor 11, and from this, the heat capacity Q 1 per unit volume of the exhaust gas of the RCIC turbine 9 is determined.
The flow rate F2 of the exhaust gas from the relief safety valve 12 is obtained from the flow rate sensor 13, and the temperature of the exhaust gas and the heat capacity Q2 per unit volume of the exhaust gas from the relief safety valve 12 can be calculated from the temperature sensor 14. Therefore, the rate of increase ΔQ in the heat capacity per unit volume of the suppression pool water due to the inflow of the exhaust gas from the RCIC turbine 9 and the exhaust gas from the relief safety valve 12 is determined by the following equation.
△Q=Q1F1+Q2F2/W0+W1+W2 ……(2)
ここでW1,W2はサプレツシヨンプール1に流
入したRCICタービン9の排気と逃し安全弁12
からの排気の体積で、それぞれF1,F2を積分す
ることによつて求まる。 △Q=Q 1 F 1 +Q 2 F 2 /W 0 +W 1 +W 2 ...(2) Here, W 1 and W 2 are the exhaust gas of the RCIC turbine 9 flowing into the suppression pool 1 and the relief safety valve 12
is the volume of exhaust gas from the , and is determined by integrating F 1 and F 2 respectively.
またこの時のサプレツシヨンプール水の単位体
積当りの熱容量Qは、
Q=Q0W0+Q1W1+Q2W2/W0+W1+W2 ……(3)
となる。サプレツシヨンプール水の単位体積当り
の熱容量Qとその増加率△Qより次式を用いてサ
プレツシヨンプール水の温度T、温度上昇率△T
を計算する事ができる。 Further, the heat capacity Q per unit volume of the suppression pool water at this time is Q=Q 0 W 0 +Q 1 W 1 +Q 2 W 2 /W 0 +W 1 +W 2 (3). From the heat capacity Q per unit volume of the suppression pool water and its rate of increase △Q, use the following formula to calculate the temperature T of the suppression pool water and the rate of increase △T.
can be calculated.
T=Q/KC,△T=Q/KC ……(4) ただし、Kは変換定数、Cは比熱である。 T=Q/KC, △T=Q/KC...(4) However, K is a conversion constant and C is a specific heat.
異常過渡時、サプレツシヨンプール冷却モード
を起動した場合の熱容量は次の通りに求まる。熱
交換器16の熱交換率をαTとすると、熱交換器1
6に流入する熱量P1と流出する熱量P2の関係は
次式で示される。 The heat capacity when the suppression pool cooling mode is activated during an abnormal transient is determined as follows. If the heat exchange coefficient of the heat exchanger 16 is α T , then the heat exchanger 1
The relationship between the amount of heat P 1 flowing into 6 and the amount of heat P 2 flowing out is shown by the following equation.
P2=αT P1(0<αT<1) ……(5)
残留熱除去系ポンプ15により熱交換器16に
送り込まれるサプレツシヨンプール水の流量と熱
交換後の温度は、流量センサ18と温度センサ1
9より得られ、これよりサプレツシヨンプール冷
却モードよりサプレツシヨンプール1に流入する
冷却材の流量F3と単位体積当りの熱容量Q3が求
まる。よつてサプレツシヨンプール冷却モードを
起動させた場合におけるサプレツシヨンプール水
の単位体積当りの熱容量の増加率△Q′は(2)式を
変形して次式で示される。 P 2 =α T P 1 (0<α T <1) ...(5) The flow rate of the suppression pool water sent to the heat exchanger 16 by the residual heat removal system pump 15 and the temperature after heat exchange are determined by the flow rate Sensor 18 and temperature sensor 1
9, and from this, the flow rate F 3 of the coolant flowing into the suppression pool 1 in the suppression pool cooling mode and the heat capacity Q 3 per unit volume are determined. Therefore, the rate of increase ΔQ' in the heat capacity per unit volume of the suppression pool water when the suppression pool cooling mode is activated is expressed by the following equation by modifying equation (2).
△Q′≡Q1F1+Q2F2−1/αT(1−αT)Q3F3/W
0+W1+W2
……(6)
またこの時のサプレツシヨンプール水の単位体
積当りの熱容量Q′は(3)式を変形して
Q′≡
Q0W0+Q1+W1+Q2W2−1/αT(1−αT)Q3W3/W0+W1
+W2
……(7)
となる。サプレツシヨンプール水の単位体積当り
の熱容量Q′とその増加率△Q′より(4)式と同様に
してサプレツシヨンプール冷却モードを起動した
場合のサプレツシヨンプール水の温度T′と温度
上昇率△T′を計算することができる。 △Q′≡Q 1 F 1 +Q 2 F 2 −1/α T (1−α T )Q 3 F 3 /W
0 +W 1 +W 2
...(6) Also, in this case, the heat capacity Q' per unit volume of the suppression pool water can be calculated by modifying equation (3) as Q'≡
Q 0 W 0 +Q 1 +W 1 +Q 2 W 2 -1/α T (1-α T )Q 3 W 3 /W 0 +W 1
+W 2
...(7) becomes. From the heat capacity Q' per unit volume of the suppression pool water and its rate of increase △Q', the temperature T' of the suppression pool water when the suppression pool cooling mode is activated in the same way as equation (4) is calculated. The temperature increase rate △T′ can be calculated.
以上に述べたように、サプレツシヨンプール1
への流入流量、温度の測定値を第2図に示す演算
装置20に入力することにより、異常過渡時には
RCICタービンの排気と逃し安全弁の排気の流入
後のサプレツシヨンプール水の温度Tと温度上昇
率△Tを計算し、中央制御室制御盤21のブラウ
ン管表示器22に表示し運転員に正確なサプレツ
シヨンプール水の温度と温度上昇率を知らせる事
ができる。またサプレツシヨンプール水の温度が
上昇すると、サプレツシヨンプール冷却モードの
起動を想定した場合の温度上昇率△T′を算出し
て、現状の温度上昇率△Tと次式の比較を行な
う。 As mentioned above, suppression pool 1
By inputting the measured values of the inflow flow rate and temperature into the arithmetic unit 20 shown in FIG.
The temperature T and temperature rise rate △T of the suppression pool water after the inflow of the RCIC turbine exhaust and the relief safety valve exhaust are calculated and displayed on the cathode ray tube display 22 of the central control room control panel 21 to provide accurate information to operators. It can inform you of the temperature of the suppression pool water and the rate of temperature rise. In addition, when the temperature of the suppression pool water increases, calculate the temperature increase rate △T' assuming activation of the suppression pool cooling mode, and compare the current temperature increase rate △T with the following formula. .
τT+△T−△T′ ……(8)
ここでτはサプレツシヨンプール冷却モードを
起動する設定温度である。この比較により残留熱
除去系ポンプ15の有効NPSHを確保するのが
困難なあらかじめ設定された温度τにまで上昇す
ると判断した場合、すなわち(8)式の不等式が成立
した場合サプレツシヨンプール冷却モードを自動
的起動させる。 τT+ΔT−ΔT′...(8) Here, τ is the set temperature for starting the suppression pool cooling mode. If it is determined from this comparison that the temperature rises to a preset temperature τ at which it is difficult to ensure the effective NPSH of the residual heat removal system pump 15, that is, if the inequality of equation (8) is established, the suppression pool cooling mode start automatically.
さらにサプレツシヨンプール冷却モードを起動
したあとも温度上昇がある場合中央制御室制御盤
21の警報表示装置23に警報を表示することに
より運転員にサプレツシヨンプールの温度変化に
注意を促がすとともに、他のサプレツシヨンプー
ル水を冷却する手段をとる必要性を知らせること
ができる。サプレツシヨンプール冷却モード起動
後のサプレツシヨンプール水の温度T′も演算装
置により計算し制御盤21のブラウン管表示器2
2に表示する。このような表示によつて運転員は
原子炉の健全性確保に極めて有効な情報を得るこ
とが可能となるとともにサプレツシヨンプール冷
却モードを自動起動させることによつて、原子炉
過渡時という異常状態において、運転員の見落し
などが生じても残留熱除去系ポンプの有効
NPSHを確保することができ原子炉水位の異常
低下時の原子炉燃料の健全性を確保することがで
きる。 Furthermore, if the temperature continues to rise even after starting the suppression pool cooling mode, an alarm will be displayed on the alarm display device 23 of the central control room control panel 21 to alert operators to the temperature change in the suppression pool. At the same time, it can notify other suppression pools of the need to take measures to cool the water. The temperature T' of the suppression pool water after starting the suppression pool cooling mode is also calculated by the arithmetic unit and displayed on the cathode ray tube display 2 of the control panel 21.
Display on 2. This type of display allows operators to obtain extremely effective information for ensuring the health of the reactor, and by automatically starting the suppression pool cooling mode, it is possible to detect abnormalities during reactor transients by automatically starting the suppression pool cooling mode. Under certain conditions, even if an operator overlooks the system, the residual heat removal system pump remains effective.
NPSH can be secured and the integrity of the reactor fuel can be ensured when the reactor water level drops abnormally.
以上述べたように、本発明によればサプレツシ
ヨンプール水の温度が既設の温度測定器と全く異
なつた原理によりわかり、たとえ既設の温度測定
器が何らかの理由により作動しないような場合で
も温度上昇率を計算し、表示することが可能なた
め運転員はサプレツシヨンプール水の状態を正確
に把握できる。
As described above, according to the present invention, the temperature of suppression pool water can be determined using a principle completely different from that of existing temperature measuring devices, and even if the existing temperature measuring device does not work for some reason, the temperature of the suppression pool water can be determined. The rate can be calculated and displayed, allowing operators to accurately grasp the condition of the suppression pool water.
これにより、プラント過渡時のサプレツシヨン
プール水の温度上昇に対し、運転員は有効な対策
がただちに取ることができると共に、運転員の見
落し誤操作が発生した場合でもサプレツシヨンプ
ール水温度が健全となり原子炉の最終的な冷却水
源が確保できているため運転員は他の緊急操作に
集中でき、原子力発電所の安全性向上に極めて重
大な効果がある。 As a result, operators can immediately take effective measures against the rise in temperature of the suppression pool water during plant transitions, and even in the event of an operator's oversight or erroneous operation, the suppression pool water temperature can be maintained. Since the reactor is healthy and the final source of cooling water is secured, operators can concentrate on other emergency operations, which has an extremely significant effect on improving the safety of nuclear power plants.
第1図は本発明が適用される原子力システムの
配管計装概略図、第2図は本発明の一実施例を説
明するブロツク図である。
1……サプレツシヨンプール、2……原子炉圧
力容器、3……一次格納容器、4……主蒸気管、
5……温度測定器、6……水位測定器、7……主
蒸気管、8……RCIC、9……RCICタービン、1
0……RCICタービン排気流量センサ、11……
RCICタービン排気温度センサ、12……逃し安
全弁、13……逃し安全弁排気流量センサ、14
……逃し安全弁排気温度センサ、15……残留熱
除去系ポンプ、16……熱交換器、17……冷却
水、18……サプレツシヨンプール冷却モード流
量センサ、19……サプレツシヨンプール冷却モ
ード温度センサ、20……演算センサ、21……
中央制御室制御盤、22……ブラウン管表示器、
23……警報表示装置、24……RCICタービン
止め弁。
FIG. 1 is a schematic diagram of piping and instrumentation of a nuclear power system to which the present invention is applied, and FIG. 2 is a block diagram illustrating an embodiment of the present invention. 1... Suppression pool, 2... Reactor pressure vessel, 3... Primary containment vessel, 4... Main steam pipe,
5... Temperature measuring device, 6... Water level measuring device, 7... Main steam pipe, 8... RCIC, 9... RCIC turbine, 1
0...RCIC turbine exhaust flow sensor, 11...
RCIC turbine exhaust temperature sensor, 12... Relief safety valve, 13... Relief safety valve exhaust flow rate sensor, 14
... Relief safety valve exhaust temperature sensor, 15 ... Residual heat removal system pump, 16 ... Heat exchanger, 17 ... Cooling water, 18 ... Suppression pool cooling mode flow rate sensor, 19 ... Suppression pool cooling Mode temperature sensor, 20... Calculation sensor, 21...
Central control room control panel, 22... CRT display,
23... Alarm display device, 24... RCIC turbine stop valve.
Claims (1)
ンプール内に点在する温度測定器と、前記サプレ
ツシヨンプールの水位を測定する水位測定器と、
異常運転時に原子炉より前記サプレツシヨンプー
ルに流入する蒸気の流量と流量温度を測定する第
1測定器と、異常運転時に原子炉隔離冷却系より
前記サプレツシヨンプールに流入する蒸気の流量
と流量温度を測定する第2測定器と、異常運転時
のサプレツシヨンプール冷却モード起動後に前記
サプレツシヨンプールに流入する流量と流量温度
を測定する第3測定器と、サプレツシヨンプール
冷却モード起動前には前記第1、前記第2測定器
から測定された測定値を入力して前記サプレツシ
ヨンプール内の熱容量および熱容量の変化から前
記プレツシヨンプール内の温度および温度上昇率
を求め、この温度および温度上昇率に基づいて一
定時間後の前記サプレツシヨンプール内の予測温
度を算出し、この算出された予測温度がサプレツ
シヨンプール冷却モード起動温度に達するとサプ
レツシヨンプール冷却モードを起動させる演算装
置と、前記演算装置で求まる演算結果を表示する
表示器とからなることを特徴とするサプレツシヨ
ンプールの温度監視装置。 2 特許請求の範囲の第1項記載のサプレツシヨ
ンプールの温度監視装置において、サプレツシヨ
ンモード起動後には前記第1、第2、第3測定器
で測定された測定値を入力してサプレツシヨンプ
ール内の熱容量および熱容量の変化を求めること
でサプレツシヨンプール内の温度および温度上昇
率を算出する演算装置と、前記演算装置で求まる
演算結果を表示する表示器を具備することを特徴
とするサプレツシヨンプールの温度監視装置。[Scope of Claims] 1. Temperature measuring instruments scattered within a suppression pool installed in a reactor containment vessel, and a water level measuring instrument for measuring the water level of the suppression pool;
a first measuring device for measuring the flow rate and flow temperature of steam flowing into the suppression pool from the reactor during abnormal operation; and a first measuring device for measuring the flow rate and flow temperature of steam flowing into the suppression pool from the reactor isolation cooling system during abnormal operation. a second measuring device that measures the flow rate temperature; a third measuring device that measures the flow rate and flow rate temperature flowing into the suppression pool after activation of the suppression pool cooling mode during abnormal operation; and a suppression pool cooling mode. Before startup, the temperature and temperature increase rate in the suppression pool are determined from the heat capacity and change in heat capacity in the suppression pool by inputting the measured values from the first and second measuring devices. , calculates the predicted temperature in the suppression pool after a certain period of time based on this temperature and temperature increase rate, and when the calculated predicted temperature reaches the suppression pool cooling mode activation temperature, the suppression pool starts cooling. 1. A suppression pool temperature monitoring device comprising: a calculation device for activating a mode; and a display device for displaying calculation results obtained by the calculation device. 2. In the suppression pool temperature monitoring device according to claim 1, after starting the suppression mode, the measurement values measured by the first, second, and third measuring devices are inputted to suppress the suppression pool. It is characterized by comprising a calculation device that calculates the temperature and temperature increase rate in the suppression pool by determining the heat capacity and the change in heat capacity in the suppression pool, and a display device that displays the calculation results obtained by the calculation device. Temperature monitoring device for suppression pools.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58205904A JPS6098391A (en) | 1983-11-04 | 1983-11-04 | Monitor device for temperature of suppression pool |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58205904A JPS6098391A (en) | 1983-11-04 | 1983-11-04 | Monitor device for temperature of suppression pool |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6098391A JPS6098391A (en) | 1985-06-01 |
| JPH0434708B2 true JPH0434708B2 (en) | 1992-06-08 |
Family
ID=16514672
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58205904A Granted JPS6098391A (en) | 1983-11-04 | 1983-11-04 | Monitor device for temperature of suppression pool |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6098391A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2003270378A (en) * | 2002-03-12 | 2003-09-25 | Toshiba Corp | Nuclear power plant suppression pool temperature monitoring device |
| JP2011174774A (en) * | 2010-02-24 | 2011-09-08 | Hitachi-Ge Nuclear Energy Ltd | Isolation cooling system in nuclear power plant |
| JP2014074657A (en) * | 2012-10-04 | 2014-04-24 | Toshiba Corp | Used fuel pool water monitoring device, used fuel pool water monitoring method and used fuel pool water monitoring system |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5788388A (en) * | 1980-11-21 | 1982-06-02 | Tokyo Shibaura Electric Co | Device for monitoring water level of suppression pool in reactor container |
| JPS5798388A (en) * | 1980-12-11 | 1982-06-18 | Dainippon Printing Co Ltd | Manufacture of decorative laminated sheet |
-
1983
- 1983-11-04 JP JP58205904A patent/JPS6098391A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6098391A (en) | 1985-06-01 |
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