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JPH0833774B2 - Reactor pressure control device - Google Patents
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JPH0833774B2 - Reactor pressure control device - Google Patents

Reactor pressure control device

Info

Publication number
JPH0833774B2
JPH0833774B2 JP62028051A JP2805187A JPH0833774B2 JP H0833774 B2 JPH0833774 B2 JP H0833774B2 JP 62028051 A JP62028051 A JP 62028051A JP 2805187 A JP2805187 A JP 2805187A JP H0833774 B2 JPH0833774 B2 JP H0833774B2
Authority
JP
Japan
Prior art keywords
reactor
pressure
reactor pressure
control device
bypass valve
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
Application number
JP62028051A
Other languages
Japanese (ja)
Other versions
JPS63196912A (en
Inventor
豊 吉田
幸雄 村田
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 JP62028051A priority Critical patent/JPH0833774B2/en
Publication of JPS63196912A publication Critical patent/JPS63196912A/en
Publication of JPH0833774B2 publication Critical patent/JPH0833774B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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

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  • Control Of Fluid Pressure (AREA)

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は、沸騰水型原子力発電所の原子炉圧力を制御
するための原子炉圧力制御装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Industrial Application] The present invention relates to a reactor pressure control device for controlling the reactor pressure of a boiling water nuclear power plant.

(従来の技術) 従来、沸騰水型原子力発電所の原子炉を停止するに
は、まず原子炉からタービンへの主蒸気配管に設けられ
た主止弁を全閉する。次に、原子炉圧力制御装置を用い
て、原子炉からタービンをバイパスして復水器へ向かう
蒸気配管に設けられたバイパス弁を制御し、原子炉から
の主蒸気を直接復水器へ送って原子炉圧力を定格圧力か
ら除々に減圧し、制御棒を操作することにより原子炉を
停止していた。
(Prior Art) Conventionally, in order to stop a nuclear reactor of a boiling water nuclear power plant, first, a main stop valve provided in a main steam pipe from the nuclear reactor to the turbine is fully closed. Next, using the reactor pressure control device, the bypass valve provided in the steam pipe that bypasses the turbine from the reactor to the condenser is controlled to send the main steam from the reactor directly to the condenser. The reactor pressure was gradually reduced from the rated pressure and the control rod was operated to shut down the reactor.

このとき、原子炉の圧力容器には機械的な熱応力の制
約があり、炉水温度の急激な変化は好ましくない。
At this time, the pressure vessel of the nuclear reactor has a restriction of mechanical thermal stress, and a rapid change of the reactor water temperature is not preferable.

このため、原子炉圧力制御装置は炉水温度の変化率を
一定範囲内に保ちながら減圧制御を行なっていた。
For this reason, the reactor pressure control device performs pressure reduction control while keeping the rate of change of reactor water temperature within a certain range.

(発明が解決しようとする問題点) しかしながら、従来の原子炉圧力制御装置は、原子炉
圧力を検出するための圧力検出器としてブルドン管と差
動トランスを使用しており、定格圧力付近で線形の検出
特性を持たせているため、10kg/cm2g以下の低圧力領域
では非線形の検出特性となっている。このため、低圧力
領域での原子炉圧力を正しく検出することができず、10
kg/cm2g以下は制御範囲外となっており、運転員による
手動操作にて減圧制御を行なわなければならない。とこ
ろが、低圧力領域ではバイパス弁の操作量も多く、運転
員による長時間にわたる手動操作では負担が大きく、炉
水温度の変化率を一定範囲内に保つ減圧制御が難かしい
という問題点があった。
(Problems to be Solved by the Invention) However, the conventional reactor pressure control device uses a Bourdon tube and a differential transformer as a pressure detector for detecting the reactor pressure, and is linear near the rated pressure. Since it has the detection characteristics of, it has a non-linear detection characteristic in the low pressure region of 10 kg / cm 2 g or less. Therefore, the reactor pressure in the low pressure region cannot be detected correctly, and
Below kg / cm 2 g is out of the control range, the decompression control must be performed manually by the operator. However, in the low pressure region, the amount of operation of the bypass valve is large, and the manual operation by the operator for a long time is a heavy burden, and there is a problem that it is difficult to perform depressurization control to keep the rate of change of the reactor water temperature within a certain range. .

そこで本発明は、原子炉圧力が10kg/cm2g以下の低圧
力領域でも炉水温度の変化率を一定範囲内に保ちながら
自動的に減圧制御を行なうことのできる原子炉圧力制御
装置を提供することを目的とする。
Therefore, the present invention provides a reactor pressure control device capable of automatically performing decompression control while keeping the rate of change of reactor water temperature within a certain range even in a low pressure region where the reactor pressure is 10 kg / cm 2 g or less. The purpose is to do.

[発明の構成] (問題点を解決するための手段) 本発明は、バイパス弁オープニングジャッキと、低圧
力領域の原子炉圧力を正しく検出するために、原子炉圧
力を検出する圧力検出器の低圧力領域の非線形特性を線
形特性に補正する非線形補償要素と、炉水温度を入力し
て炉水温度と飽和蒸気圧の関係より所定の時間間隔毎の
原子炉圧力目標値を算出するための圧力目標値算出手段
とを設けて、非線形補償要素からの補正された原子炉圧
力が圧力目標値算出手段の算出する原子炉圧力目標値に
追従すべくバイパス弁オープニングジャッキを用いてバ
イパス弁を制御するものである。
[Structure of the Invention] (Means for Solving Problems) The present invention provides a bypass valve opening jack and a low pressure detector for detecting the reactor pressure in order to correctly detect the reactor pressure in a low pressure region. A non-linear compensation element that corrects the non-linear characteristic of the pressure region to a linear characteristic, and the pressure for calculating the reactor pressure target value at predetermined time intervals based on the relationship between the reactor water temperature and the saturated vapor pressure by inputting the reactor water temperature. A target value calculation means is provided to control the bypass valve using the bypass valve opening jack so that the corrected reactor pressure from the non-linear compensation element follows the reactor pressure target value calculated by the pressure target value calculation means. It is a thing.

(作用) これにより、原子炉圧力が10kg/cm2g以下の低圧力領
域においても、自動的に炉水温度の変化率を一定範囲内
に保ちつつ減圧制御を行なうことができる。
(Operation) As a result, even in the low pressure region where the reactor pressure is 10 kg / cm 2 g or less, the decompression control can be automatically performed while keeping the rate of change of the reactor water temperature within a certain range.

(実施例) 本発明の一実施例による原子炉圧力制御装置を沸騰水
型原子力発電所に適用したシステム構成を第1図に示
す。
(Embodiment) FIG. 1 shows a system configuration in which a reactor pressure control device according to an embodiment of the present invention is applied to a boiling water nuclear power plant.

原子炉1からの蒸気は主蒸気配管2を通り、一方は主
止弁3を介して発電機4に直結された蒸気タービン5へ
送られる。もう一方はタービンバイパス弁6を介して復
水器7へ送られる。蒸気タービン5の出口蒸気は復水器
7で冷却されて復水となって復水管8を通り復水ポンプ
9により給水加熱器10に送られる。復水はこの給水加熱
器10により加熱され給水ポンプ11により再び原子炉1に
送られる。
Steam from the nuclear reactor 1 passes through a main steam pipe 2, and one of them is sent to a steam turbine 5 directly connected to a generator 4 via a main stop valve 3. The other is sent to the condenser 7 via the turbine bypass valve 6. The outlet steam of the steam turbine 5 is cooled by the condenser 7 and becomes condensed water, which passes through the condensate pipe 8 and is sent to the feed water heater 10 by the condensate pump 9. Condensed water is heated by the feed water heater 10 and sent to the reactor 1 again by the feed water pump 11.

一方、原子炉1内の原子炉圧力および炉水温度はそれ
ぞれ圧力検出器12および温度検出器13により検出され
る。圧力検出器12からの原子炉圧力Pは原子炉圧力制御
装置14内のサンプリング周期毎に信号を入力するサンプ
ラー15Aを介して原子炉圧力Pを補正するための非線形
補償要素16に入力される。温度検出器13からの炉水温度
Tは同じく原子炉圧力制御装置14内のサンプラー15Aを
介して圧力目標値算出手段17に入力される。この圧力目
標値算出手段17は入力した炉水温度Tより目標圧力変化
率PDを算出するための関数発生器18と、サンプラー15A
がサンプリングを開始したとき、すなわち制御開始時の
原子炉圧力Pを初期値とし、これに関数発生器18の算出
した目標圧力変化率PDをサンプリング周期毎に加算し加
算結果を原子炉圧力目標値PAとして出力する積分器19よ
りなる。この原子炉圧力目標値PAと、前述した非線形補
償要素16からの補正された原子炉圧力PCは、加算器20に
入力され、その偏差はA制御要素21、B制御要素22およ
びサンプラー15Aと連動してサンプリング周期毎に信号
を出力するサンプラー15Bを介してバイパス弁制御装置2
3へ弁開度要求信号aとなって出力される。ここで、A
制御要素21は加算器20からの偏差をバイパス弁制御装置
23への弁開度要求信号aに変換するためのものであり、
B制御要素22はその変化が大きい場合あるいは一定範囲
内でない場合に所定の制限を与えるためのものである。
バイパス弁制御装置23内のバイパス弁オープニングジャ
ッキ開度設定器24は原子炉圧力制御装置14からの弁開度
要求信号aを入力してバイパス弁6の弁開度目標値a′
を算出するためのものである。このバイパス弁オープニ
ングジャッキ開度設定器24により算出された弁開度目標
値a′は、バイパス弁6の弁開度信号bを入力したC制
御要素25からの実際の弁開度b′と共に加算器26に入力
される。加算器26はこれら入力した弁開度目標値a′お
よび実際の弁開度b′の偏差をとるためのものであり、
その偏差はバイパス弁オープニングジャッキ開度制御器
27に入力されて制御信号cとなってバイパス弁6に出力
される。
On the other hand, the reactor pressure and the reactor water temperature in the reactor 1 are detected by the pressure detector 12 and the temperature detector 13, respectively. The reactor pressure P from the pressure detector 12 is input to a non-linear compensating element 16 for correcting the reactor pressure P via a sampler 15A which inputs a signal for each sampling period in the reactor pressure control device 14. The reactor water temperature T from the temperature detector 13 is also input to the target pressure value calculating means 17 via the sampler 15A in the reactor pressure control device 14. This pressure target value calculation means 17 is a function generator 18 for calculating a target pressure change rate PD from the input reactor water temperature T, and a sampler 15A.
When sampling starts, that is, the reactor pressure P at the start of control is set as an initial value, and the target pressure change rate PD calculated by the function generator 18 is added to this for each sampling cycle, and the addition result is the reactor pressure target value. It consists of an integrator 19 that outputs as PA. This reactor pressure target value PA and the corrected reactor pressure PC from the above-mentioned non-linear compensation element 16 are input to the adder 20, and the deviation thereof is linked with the A control element 21, the B control element 22 and the sampler 15A. By-pass valve controller 2 via sampler 15B which outputs a signal for each sampling cycle
It is output to 3 as a valve opening request signal a. Where A
The control element 21 is a bypass valve control device for the deviation from the adder 20.
For converting the valve opening request signal a to 23,
The B control element 22 is for providing a predetermined limit when the change is large or not within a certain range.
The bypass valve opening jack opening setting device 24 in the bypass valve control device 23 inputs the valve opening request signal a from the reactor pressure control device 14 and receives the valve opening target value a ′ of the bypass valve 6.
For calculating. The valve opening target value a'calculated by the bypass valve opening jack opening setter 24 is added together with the actual valve opening b'from the C control element 25 to which the valve opening signal b of the bypass valve 6 is input. Input to the container 26. The adder 26 is for taking a deviation between the input valve opening target value a'and the actual valve opening b '.
The deviation is the bypass valve opening jack opening controller
The signal is input to 27, becomes a control signal c, and is output to the bypass valve 6.

以上の構成で、原子炉1が通常に運転されているとき
は、バイパス弁6は閉じており、主止弁3が開いてい
る。これにより、原子炉1からの主蒸気は主蒸気配管2
を通り、主止弁3を通って蒸気タービン5を駆動し、発
電機4を回転させて発電機出力を得ている。
With the above configuration, when the nuclear reactor 1 is operating normally, the bypass valve 6 is closed and the main stop valve 3 is open. As a result, the main steam from the reactor 1 is fed into the main steam pipe 2
, The steam turbine 5 is driven through the main stop valve 3 and the generator 4 is rotated to obtain the generator output.

この状態から原子炉1を停止するときは、発電機4と
系統を遮断し、主止弁3を閉じて蒸気タービン5への主
蒸気の供給を遮断し、蒸気タービン5を停止する。
When shutting down the reactor 1 from this state, the generator 4 and the system are shut off, the main stop valve 3 is closed to shut off the supply of main steam to the steam turbine 5, and the steam turbine 5 is shut down.

次に、図示せぬ従来の原子炉圧力制御装置を用いてバ
イパス弁6を除々に開き原子炉1からの主蒸気を復水器
7へ送り、炉水温度Tの変化率を一定範囲内(−55℃/H
以下)に保ちながら定格圧力10kg/cm2gまで減圧する。
Next, by using a conventional reactor pressure control device (not shown), the bypass valve 6 is gradually opened and the main steam from the reactor 1 is sent to the condenser 7 to keep the rate of change of the reactor water temperature T within a certain range ( −55 ° C / H
Keep the following) and reduce the pressure to the rated pressure of 10 kg / cm 2 g.

さて、原子炉圧力Pが10kg/cm2gとなったとき、原子
炉圧力制御装置14を起動する。すると、サンプラー15A
が所定のサンプリング周期で圧力検出器12からの原子炉
圧力Pおよび温度検出器13からの炉水温度Tを原子炉圧
力制御装置内に入力する。圧力目標値算出手段17内の関
数発生器18は、第2図に示すように、現在の炉水温度T1
を入力し、サンプリング周期Δt秒後の炉水温度T2をT2
=T1+Δt×(目標降温率)として算出する。さらに、
炉水温度Tと原子炉1の飽和圧力との関係より炉水温度
がT1,T2の時の原子炉圧力P1,P2を求め、目標圧力変化率
PDをPD=P2−P1により算出し、これを積分器19に出力す
る。積分器19は、原子炉圧力制御装置14が時刻t1で起動
したときの原子炉圧力P1を初期値とし、入力した目標圧
力変化率PD(=P2−P1)を加算し、これを圧力目標値PA
(=P2)として出力する。
Now, when the reactor pressure P reaches 10 kg / cm 2 g, the reactor pressure control device 14 is started. Then, the sampler 15A
Inputs the reactor pressure P from the pressure detector 12 and the reactor water temperature T from the temperature detector 13 into the reactor pressure control device at a predetermined sampling period. As shown in FIG. 2, the function generator 18 in the pressure target value calculation means 17 determines the current reactor water temperature T 1
Input, and set the reactor water temperature T 2 after the sampling period Δt seconds to T 2
= T 1 + Δt × (target temperature drop rate). further,
From the relationship between the reactor water temperature T and the saturation pressure of the reactor 1 , the reactor pressures P 1 and P 2 are calculated when the reactor water temperature is T 1 and T 2 , and the target pressure change rate
PD is calculated by PD = P 2 −P 1 , and this is output to the integrator 19. The integrator 19 sets the reactor pressure P 1 when the reactor pressure controller 14 is started at time t 1 as an initial value, adds the input target pressure change rate PD (= P 2 −P 1 ), and Target pressure PA
Output as (= P 2 ).

一方、非線形補償要素16は圧力検出器12の検出する原
子炉圧力Pが10kg/cm2g以下の場合、非線形特性となり
正しい原子炉圧力が検出されないため、第3図に示すよ
うな非線形関数により、入力した圧力検出器12からの原
子炉圧力Pの線形化を行ない、補正した原子炉圧力PCを
出力する。
On the other hand, when the reactor pressure P detected by the pressure detector 12 is 10 kg / cm 2 g or less, the non-linear compensation element 16 has non-linear characteristics and the correct reactor pressure cannot be detected. The input reactor pressure P from the pressure detector 12 is linearized, and the corrected reactor pressure PC is output.

加算器20は積分器19からの圧力目標値PAと非線形補償
要素16からの補正した原子炉圧力PCとの偏差をA制御要
素21に出力する。A制御要素21はこれをバイパス弁6へ
の弁開度要求信号aに変換する一方、B制御要素22はこ
れに所定の制限を加え、サンプラー15Bを介して弁開度
要求信号aをバイパス弁制御装置23に出力する。バイパ
ス弁オープニングジャッキ制御装置23内のバイパス弁オ
ープニングジャッキ開度設定器24はこの弁開度要求信号
aに基づいてバイパス弁6の弁開度目標値a′を算出す
る。加算器26はこの弁開度目標値a′とC制御要素25か
らの実際の弁開度b′を入力して、その偏差分をバイパ
ス弁オープニングジャッキ開度制御器27に出力する。バ
イパス弁オープニングジャッキ開度制御器27はこれに基
づいて制御信号Cを出力してバイパス弁6を操作し、原
子炉1からバイパス弁6を介して復水器7へ送る主蒸気
を制御し、原子炉圧力PをΔt秒間にP1よりP2まで減圧
する。これにより、Δt秒後の飽和蒸気圧によって定ま
る炉水温度TをT2にすることができる。
The adder 20 outputs the deviation between the pressure target value PA from the integrator 19 and the corrected reactor pressure PC from the nonlinear compensation element 16 to the A control element 21. The A control element 21 converts this into a valve opening request signal a to the bypass valve 6, while the B control element 22 imposes a predetermined limit on this, and the valve opening request signal a is bypassed via the sampler 15B. Output to the control device 23. The bypass valve opening jack opening setting device 24 in the bypass valve opening jack control device 23 calculates the valve opening target value a ′ of the bypass valve 6 based on the valve opening request signal a. The adder 26 inputs this valve opening target value a ′ and the actual valve opening b ′ from the C control element 25, and outputs the deviation thereof to the bypass valve opening jack opening controller 27. Based on this, the bypass valve opening jack opening controller 27 outputs the control signal C to operate the bypass valve 6 to control the main steam sent from the reactor 1 to the condenser 7 via the bypass valve 6, The reactor pressure P is reduced from P 1 to P 2 in Δt seconds. As a result, the reactor water temperature T determined by the saturated vapor pressure after Δt seconds can be T 2 .

一般に、n回目のサンプリング周期において、炉水温
度がTnならば目標とするΔt秒後の炉水温度Tn+1をTn+1
=Tn+Δt×(目標降温率)とし、炉水温度tn+1に対応
する原子炉圧力Pn+1を求め、目標圧力変化率PDをPD=Pn
+1−Pnとし、原子炉圧力目標値PAを とする。このように算出した原子炉圧力目標値PAを目標
値として、バイパス弁6バイパス弁オープニングジャッ
キ制御装置23により調節して、非線形補償要素16からの
補正された原子炉圧力PCをフィードバック制御すること
により、Δt秒後に炉水温度TをTn+1とすることができ
る。
Generally, if the reactor water temperature is Tn in the n-th sampling cycle, the target reactor water temperature Tn +1 after Δt seconds is Tn +1.
= Tn + Δt × (target temperature decrease rate), the reactor pressure Pn + 1 corresponding to the reactor water temperature tn + 1 is calculated, and the target pressure change rate PD is PD = Pn
+1 −Pn and set the reactor pressure target value PA And By adjusting the reactor pressure target value PA thus calculated as a target value by the bypass valve 6 and the bypass valve opening jack control device 23, the corrected reactor pressure PC from the non-linear compensation element 16 is feedback-controlled. , Δt seconds later, the reactor water temperature T can be set to Tn +1 .

以上のように本実施例によれば、低圧力領域におい
て、炉水温度Tの変化率を一定範囲内に保ちながら、自
動的に原子炉の減圧制御を行なうことができる。
As described above, according to the present embodiment, in the low pressure region, the pressure reduction control of the reactor can be automatically performed while keeping the rate of change of the reactor water temperature T within a certain range.

尚、本実施例では、10kg/cm2g以下の減圧制御につい
て説明したが、従来の原子炉圧力制御装置をまったく使
用せず定格圧力より10kg/cm2g以下までの減圧制御もす
べてこの原子炉圧力制御装置14に行なわせることももち
ろん可能である。
In the present embodiment, the pressure reduction control of 10 kg / cm 2 g or less was described, but the conventional reactor pressure control device was not used at all, and the pressure reduction control from the rated pressure to 10 kg / cm 2 g or less was also performed with this atom. Of course, it is also possible to make the furnace pressure control device 14 carry out.

[発明の効果] 以上のように本発明によれば、10kg/cm2g以下の低圧
力領域においても炉水温度変化率を一定範囲内に保ちな
がら自動的に減圧制御を行なうことができ、原子炉停止
時の運転員による長時間に渡る減圧操作をなくし、プラ
ントの稼動率向上に大巾に貢献する原子炉圧力制御装置
が得られる。
As described above, according to the present invention, even in the low pressure region of 10 kg / cm 2 g or less, the pressure reduction control can be automatically performed while keeping the reactor water temperature change rate within a certain range. It is possible to obtain a reactor pressure control device that greatly contributes to the improvement of the operating rate of the plant by eliminating the long-term depressurization operation by the operator when the reactor is stopped.

【図面の簡単な説明】[Brief description of drawings]

第1図は本発明の一実施例による原子炉圧力制御装置を
沸騰水型原子力発電所に適用したシステム構成図、第2
図はプラント停止時の原子炉圧力と炉水温度の特性変化
説明図、第3図は第1図の非線形補償要素の入出力特性
説明図である。 1……原子炉、2……主蒸気配管、3……主止弁、4…
…発電機、5……蒸気タービン、6……バイパス弁、7
……復水器、8……復水管、9……復水ポンプ、10……
給水加熱器、11……給水ポンプ、12……圧力検出器、13
……温度検出器、14……原子炉圧力制御装置、15A,15b
……サンプラー、16……非線形補償要素、17……圧力目
標値算出手段、18……関数発生器、19……積分器、20,2
6……加算器、21,22,25……制御要素、23……バイパス
弁オープニングジャッキ制御装置、24……バイパス弁オ
ープニングジャッキ開度設定器、27……バイパス弁オー
プニングジャッキ開度制御器。
FIG. 1 is a system configuration diagram in which a reactor pressure control device according to an embodiment of the present invention is applied to a boiling water nuclear power plant, and FIG.
FIG. 3 is an explanatory view of characteristic changes of reactor pressure and reactor water temperature when the plant is stopped, and FIG. 3 is an explanatory view of input / output characteristics of the nonlinear compensation element of FIG. 1 ... Reactor, 2 ... Main steam piping, 3 ... Main stop valve, 4 ...
… Generator, 5 …… Steam turbine, 6 …… Bypass valve, 7
… Condenser, 8 …… Condenser pipe, 9 …… Condensate pump, 10 ……
Water heater, 11 …… Water pump, 12 …… Pressure detector, 13
...... Temperature detector, 14 ...... Reactor pressure control device, 15A, 15b
…… Sampler, 16 …… Nonlinear compensation element, 17 …… Pressure target value calculation means, 18 …… Function generator, 19 …… Integrator, 20,2
6 …… Adder, 21,22,25 …… Control element, 23 …… Bypass valve opening jack controller, 24 …… Bypass valve opening jack opening setter, 27 …… Bypass valve opening jack opening controller.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】原子炉からタービンをバイパスして復水器
へ向かう蒸気配管に設けられたバイパス弁の開度を制御
して、炉水温度の変化率を一定範囲内に保ちながら原子
炉の減圧制御を行なう原子炉圧力制御装置において、検
出した炉水温度より原子炉圧力目標値を算出する圧力目
標値算出手段と、原子炉圧力を検出する圧力検出器の非
線形特性を補正するための非線形補償要素と、この非線
形補償要素で補正された原子炉圧力値と前記圧力目標値
算出手段により算出された原子炉圧力目標値との偏差に
応じて前記バイパス弁を制御するバイパス弁オープニン
グジャッキ制御装置とを備えることを特徴とする原子炉
圧力制御装置。
Claim: What is claimed is: 1. By controlling the opening of a bypass valve provided in a steam pipe that bypasses the turbine to the condenser and bypasses the turbine, keeping the rate of change of the reactor water temperature within a certain range. In a reactor pressure control device that performs depressurization control, a target pressure value calculating means for calculating a target reactor pressure value from the detected reactor water temperature, and a non-linearity for correcting the non-linear characteristics of a pressure detector for detecting the reactor pressure. A compensating element and a bypass valve opening jack control device for controlling the bypass valve according to a deviation between the reactor pressure value corrected by the non-linear compensating element and the reactor pressure target value calculated by the pressure target value calculating means. A reactor pressure control device comprising:
JP62028051A 1987-02-12 1987-02-12 Reactor pressure control device Expired - Lifetime JPH0833774B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62028051A JPH0833774B2 (en) 1987-02-12 1987-02-12 Reactor pressure control device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62028051A JPH0833774B2 (en) 1987-02-12 1987-02-12 Reactor pressure control device

Publications (2)

Publication Number Publication Date
JPS63196912A JPS63196912A (en) 1988-08-15
JPH0833774B2 true JPH0833774B2 (en) 1996-03-29

Family

ID=12237954

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62028051A Expired - Lifetime JPH0833774B2 (en) 1987-02-12 1987-02-12 Reactor pressure control device

Country Status (1)

Country Link
JP (1) JPH0833774B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6935156B2 (en) * 2003-09-30 2005-08-30 Rosemount Inc. Characterization of process pressure sensor
KR101275301B1 (en) * 2011-12-15 2013-06-17 한국전력기술 주식회사 An apparatus and method controlling output for set-up signal of pressure point in order to control automatically a steam bypass control system, and an apparatus and method controlling automatically a steam bypass control system thereof

Also Published As

Publication number Publication date
JPS63196912A (en) 1988-08-15

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