JPS5838897A - Reactor feedwater control device - Google Patents

Reactor feedwater control device

Info

Publication number
JPS5838897A
JPS5838897A JP56138070A JP13807081A JPS5838897A JP S5838897 A JPS5838897 A JP S5838897A JP 56138070 A JP56138070 A JP 56138070A JP 13807081 A JP13807081 A JP 13807081A JP S5838897 A JPS5838897 A JP S5838897A
Authority
JP
Japan
Prior art keywords
water level
deviation
signal
reactor
controller
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP56138070A
Other languages
Japanese (ja)
Inventor
明 佐藤
正英 小林
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP56138070A priority Critical patent/JPS5838897A/en
Publication of JPS5838897A publication Critical patent/JPS5838897A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Biological Treatment Of Waste Water (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 水制御装置iこ関する。[Detailed description of the invention] Regarding water control equipment.

一般に、沸騰水f!JIJJK子力発電所では、i子炉
の冷却水が直接、プラントの作動流体となる直接サイク
ル型が使用されている。そのため、使用される冷却水は
、安全運転上、′原子炉圧力容器内において一定の水位
を維持させる必要から原子炉給水制御装置によって給水
量が制御されるよう1どなっている。
In general, boiling water f! The JIJJK child power plant uses a direct cycle type in which the cooling water of the i child reactor directly becomes the working fluid of the plant. Therefore, for safe operation, the amount of cooling water used is controlled by the reactor water supply control device because it is necessary to maintain a constant water level in the reactor pressure vessel.

この給水制御装置は、一般lこは、原子炉水位を検出す
る水位検出器、所定の水位を設定する水位設定器、検出
水位と設定水位との偏差から給水量を制御する比例・積
分・微分要素を有する制御器、この制御器からの出力に
従って給水量を変化させる給水流量駆動制御機構から成
っている。
This water supply control device generally consists of a water level detector that detects the reactor water level, a water level setter that sets a predetermined water level, and a proportional, integral, and differential system that controls the water supply amount from the deviation between the detected water level and the set water level. It consists of a controller having elements, and a water supply flow rate drive control mechanism that changes the water supply amount according to the output from this controller.

かかる従来の制御装置においては、その主要部分である
制御器の制御定数は一定で69.しかも一般的には通常
運転時に良好な制御が行なえるように設定させるため1
通常時での原子炉水位制御は極めて良好である。ところ
が、沸騰水温原子炉には尋寺半春急激な出力変化時、例
えば再循環流量の急激な増加、減少や再循環ポンプトリ
ップによる出力変動等が生じた場合は、発生する主蒸気
流量の変化率が大きくなって、主蒸気流量と給水流量と
の大きなアンバランスが生じることがあp、また、炉心
内ボイド層の変化ζζより原子炉水位が大幅に変動する
こともあ#)、そのため、速やかな原子炉水位の整定が
必要とされるも、それは極めて困難であるという欠点を
有していた。
In such a conventional control device, the control constant of the controller, which is the main part, is constant and is 69. Moreover, in general, 1 is set to allow good control during normal operation.
Reactor water level control under normal conditions is extremely good. However, in boiling water temperature reactors, when there is a sudden change in output, such as a sudden increase or decrease in the recirculation flow rate or a recirculation pump trip, the main steam flow rate changes. As a result, a large imbalance between the main steam flow rate and the feed water flow rate may occur, and the reactor water level may fluctuate significantly due to changes in the void layer in the core. Although it is necessary to quickly stabilize the reactor water level, it has the drawback of being extremely difficult.

そζで本発明は、如上の従来存した欠点を改善して、大
幅な原子炉水位の変動時に、極めて迅速な給水流量の制
御を行ない、速やかな原子炉水位本発明は、検出水位と
設定水位との偏差量が予め定められた偏差幅から逸脱し
た場合に、制御器に入力される水位偏差信号を一時的に
比例増幅器を介して拡大することで給水流量の制御量を
大きくすることによシ前記目的を達成しようとするもの
である。
Therefore, the present invention improves the above-mentioned conventional drawbacks and performs extremely rapid control of the water supply flow rate when the reactor water level fluctuates significantly. When the amount of deviation from the water level deviates from a predetermined deviation width, the water level deviation signal input to the controller is temporarily expanded via a proportional amplifier to increase the control amount of the water supply flow rate. The aim is to achieve the above objectives.

以下1図面t−参照して本発明の一実施例t−g関する
と次の通シである。
Hereinafter, with reference to the drawings 1 to 1, an embodiment of the present invention t to g will be described as follows.

図において示される符号lは、洲騰水型の原子炉の原子
炉圧力容器であり%その冷却水の水位2は、給水機構3
によって供給される給水流量Bと、蒸気導出機構4によ
って得られる主蒸気流mAとのバ2ンメによって一定に
維持されている。また、この水位2は、冷却水を再循環
させるべく原子炉圧力容器」に付設された再循環ポンプ
5の!に動部量によって吃、また、炉心内ボイド量の変
動によっても一時的に変動することもある。
The symbol l shown in the figure is the reactor pressure vessel of the rising water type nuclear reactor, and the water level 2 of its cooling water is the water supply mechanism 3.
The main steam flow mA obtained by the steam derivation mechanism 4 is maintained constant by the coupling between the feed water flow rate B supplied by the steam flow rate B and the main steam flow mA obtained by the steam derivation mechanism 4. Also, this water level 2 is due to the recirculation pump 5 attached to the reactor pressure vessel to recirculate the cooling water! In addition, it may fluctuate temporarily depending on the amount of moving parts, and also due to fluctuations in the amount of voids in the core.

しかして、原子炉圧力容器l内の水位2は、水位検出@
6によって検出され、原子炉水位信号Cとして加減演算
器7に出力される。この加減演算器7は、原子炉圧力容
器1内の水位2を一定位に設定制御する水位設定@8か
らの出力信号である水位設定信号りと、前記原子炉水位
信号Cとを減算し、検出水位と設定水位との偏差を水位
偏差信号Eとして出力する。
Therefore, the water level 2 in the reactor pressure vessel l is determined by water level detection @
6 and output as a reactor water level signal C to an addition/subtraction calculator 7. This addition/subtraction calculator 7 subtracts the reactor water level signal C from the water level setting signal R, which is an output signal from the water level setting @8 that controls the water level 2 in the reactor pressure vessel 1 to a constant level, The deviation between the detected water level and the set water level is output as a water level deviation signal E.

この水位偏差信号Eは、リレー10を備えた比較器9を
経て制御器12番こ入力され、この制御器12によって
給水流量駆動制御機構13を制御し、前記給水機構3で
の給水量を調整するようになっている。
This water level deviation signal E is input to a controller 12 via a comparator 9 equipped with a relay 10, and this controller 12 controls a water supply flow rate drive control mechanism 13 to adjust the amount of water supplied by the water supply mechanism 3. It is supposed to be done.

しかして、比較器9は、水位偏差信号Eと予め定められ
た偏差量T(検出水位と設定水位との偏差)の大小とを
比較し、制御器12に入力される信号ルートを切替えゐ
リレーlOを備えている。このリレー10は、水位偏差
信号Eが予め定められた偏差量Tよ〕小さい時にはそれ
をその11制御器12へ、大きい時には比例増幅器11
によって増幅修正された修正水位偏差信号Fとして制御
器12へ切換出力させるよう動作する。
The comparator 9 compares the water level deviation signal E with the predetermined deviation amount T (deviation between the detected water level and the set water level), and switches the signal route input to the controller 12. It is equipped with lO. When the water level deviation signal E is smaller than a predetermined deviation amount T, this relay 10 sends it to the controller 12, and when it is larger, it is sent to the proportional amplifier 11.
It operates to switch and output the corrected water level deviation signal F to the controller 12 as the corrected water level deviation signal F which has been amplified and corrected.

すなわち、比例増幅器11は、検出水位と設定水位との
偏差が予め定められた偏差量Tを越えた時、水位偏差信
号Eを予め定められた比率で拡大増幅して修正水位偏差
信号Fとして出力するもので。
That is, when the deviation between the detected water level and the set water level exceeds a predetermined deviation amount T, the proportional amplifier 11 amplifies the water level deviation signal E by a predetermined ratio and outputs it as a corrected water level deviation signal F. Something to do.

これが制御器入力信号Gとなって制御器校に入力される
This becomes the controller input signal G and is input to the controller.

制御器12は、給水流量駆動制御機構13を制御する比
例・積分・微分!!素を有しておシ、前述の如く、給水
機構3での給水量を決定調整する。
The controller 12 is a proportional, integral, and differential controller that controls the water supply flow rate drive control mechanism 13! ! As described above, the amount of water supplied by the water supply mechanism 3 is determined and adjusted.

次に、出力が急激に変動し、原子炉圧力容器lの水位2
が大Iに変化する場合での作用を、第2図に基づいて説
明する。
Next, the power fluctuates rapidly, and the water level in the reactor pressure vessel 2
The effect when the value changes to large I will be explained based on FIG. 2.

出力変動が生じ主蒸気流量Aが変化し始めると。When output fluctuation occurs and the main steam flow rate A begins to change.

炉内ボイド層の変化の効果と給水流量Bとが瞬時には追
従しないため、その間iこアンバツンスが生じ、これに
よって原子炉水位信号Cが変化し始める。このとき、水
位設定は一定としであるため、検出水位と設定水位との
偏差に対応して加減演算器7から出力された水位偏差信
号Eは、原子炉水位信号Cの変化と同様に変化し始める
。変化を開始してからのしばらくの間は、水位偏差信号
Eは予め設定された偏差量Tより小さいためその11制
御器入力信号Gとなって給水流量Bを制御する。
Since the effect of the change in the void layer in the reactor and the feed water flow rate B do not follow instantaneously, an imbalance occurs during that time, and as a result, the reactor water level signal C begins to change. At this time, since the water level setting is constant, the water level deviation signal E output from the addition/subtraction calculator 7 in response to the deviation between the detected water level and the set water level changes in the same way as the reactor water level signal C changes. start. For a while after the change starts, the water level deviation signal E is smaller than the preset deviation amount T, so it becomes the 11 controller input signal G to control the water supply flow rate B.

通常の小さな出力変動時には、このようなシーケンス制
御によって給水流量Bが制御され、水位2は設定水位に
復原するよう制御される。
During normal small output fluctuations, the water supply flow rate B is controlled by such sequence control, and the water level 2 is controlled to return to the set water level.

これに反し、大幅で急激な出力変動が生じた場合には、
給水流量Bの制御が十分に追従できず。
On the other hand, if a large and sudden change in output occurs,
The water supply flow rate B cannot be controlled sufficiently.

水位偏差信号Eはしばらくすると予め設定された偏差量
Tより大きくなる。すると、その時点で比較器9のリレ
ーlOが切換作動して比例増幅器11によって増幅修正
された修正水位偏差信号Fに、前記の水位偏差信号Eが
切換わる。この修正水位偏差信号Fは、水位偏差信号E
を予め定められた比率で増幅した信号であるため、急激
で大きな出力信号が制御器νに入力され、その結果、給
水流量Bは急激に変化させられ、原子炉圧力容器1の水
位2の変動を迅速に抑制するよう大きく制御するもので
ある。そして1以上の動作によって、水位2の変動が抑
制されて設定水位に戻9始め、水位偏差信号Eが予め定
められた偏差量Tの範囲内番ζ復帰すると、再び制御器
入力信号Gは水位偏差信号Eに切替シ、以後、設定水位
に復原するまで比較的おだやかな割合で水位2を制御す
るものである。
The water level deviation signal E becomes larger than the preset deviation amount T after a while. At that point, the relay lO of the comparator 9 is switched, and the water level deviation signal E is switched to the corrected water level deviation signal F which has been amplified and corrected by the proportional amplifier 11. This corrected water level deviation signal F is the water level deviation signal E
Since the signal is amplified at a predetermined ratio, a sudden and large output signal is input to the controller ν, and as a result, the feed water flow rate B is suddenly changed, causing fluctuations in the water level 2 in the reactor pressure vessel 1. This is a major control that quickly suppresses the Then, by the operation 1 or more, the fluctuation of the water level 2 is suppressed and the water level returns to the set water level 9. When the water level deviation signal E returns to the number ζ within the range of the predetermined deviation amount T, the controller input signal G again changes to the water level. After switching to the deviation signal E, the water level 2 is thereafter controlled at a relatively gentle rate until the water level returns to the set water level.

したがって1通常運転に適した制御器12の制御定数で
あっても、そのままで、原子炉圧力容器lの水位が大き
く変動した場合にも、増幅修正された制御入力信号G屹
対応して給水流量駆動制御機構13を大きく制御でき・
るようにするから、十分に速やかな安定した運転制御を
行なうことができ、そのため1発電プラントの稼動率を
向上させることが可能となる利点が得られる。
Therefore, even if the control constants of the controller 12 are suitable for normal operation, even if the water level in the reactor pressure vessel l fluctuates greatly, the amplified and corrected control input signal G will respond to the feedwater flow rate. The drive control mechanism 13 can be greatly controlled.
Since the power generation plant is configured to operate in a stable manner, it is possible to perform sufficiently rapid and stable operation control, which has the advantage that it is possible to improve the operating rate of one power generation plant.

すなわち、これは、検出水位と設定水位との偏差が予め
定められた偏差量Tを越えた時、給水流量駆動制御機構
13を制御する制御器ルに入力される水位偏差信号Eを
拡大して修正水位偏差信号Gとする比例増幅器11を介
装したからであり、しかも、仁の比例増幅器11は従来
の給水制御装置に簡単ζこ組み込めるから、従来のそれ
を大きく改造することなく設置でき1便利である。
That is, when the deviation between the detected water level and the set water level exceeds a predetermined deviation amount T, the water level deviation signal E input to the controller that controls the water supply flow rate drive control mechanism 13 is expanded. This is because the proportional amplifier 11 that uses the corrected water level deviation signal G is inserted, and since the proportional amplifier 11 can be easily incorporated into the conventional water supply control device, it can be installed without major modification of the conventional device. It's convenient.

以上説明したように、本発明によれば、水位偏差がある
一定量以上に大きくなった場合のみ、それから得られる
偏差信号を増幅して制御器に入力させゐ制御偏置を俟備
することにより、制御能力及びプラント稼動率の極めて
高い原子炉給水制御装置を提供することかで龜る。
As explained above, according to the present invention, only when the water level deviation becomes larger than a certain amount, the deviation signal obtained from the deviation signal is amplified and inputted to the controller by providing a control eccentricity. Our goal is to provide a reactor water supply control system with extremely high control capabilities and plant availability.

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

図面は本発明の一実施例を示すもので、#I1図はブロ
ック図、g2#Aはその作用を表わす線図である。 l・・・原子炉圧力容器、2・・・水位、3・・・給水
機構。 4・・・蒸気導出機構、5・・・再循環ポンプ、6・・
・水位検出器、7・・・加減演算器、8・・・水位設定
器、10・・・リレー、9・・・比較器、11・・・比
例増幅器、12・・・制御器、13・・・給水流量駆動
制御機構、A・・・主蒸気流量、B・・・給水流量、C
・・・原子炉水位信号、D・・・水位設定信号、E・・
・水位偏差信号、G・・・制御器入力信号、T・・・偏
差量。 545
The drawings show one embodiment of the present invention, and figure #I1 is a block diagram, and figure g2#A is a line diagram showing its operation. l...Reactor pressure vessel, 2...Water level, 3...Water supply mechanism. 4... Steam derivation mechanism, 5... Recirculation pump, 6...
・Water level detector, 7... Addition/subtraction calculator, 8... Water level setter, 10... Relay, 9... Comparator, 11... Proportional amplifier, 12... Controller, 13. ...Water supply flow rate drive control mechanism, A...Main steam flow rate, B...Water supply flow rate, C
...Reactor water level signal, D...Water level setting signal, E...
・Water level deviation signal, G...controller input signal, T...deviation amount. 545

Claims (1)

【特許請求の範囲】 1、原子炉圧力容器内の原子炉水位を検出する水位検出
器と、Wr定の原子炉水位を設定する水位設定器と、検
出水位と設定水位との偏差を水位偏差信号として出力す
る加減演算器と、入力される水位偏差信号によって給水
流量駆動制御機構を制御する比例・積分・微分要素を有
する制御器と、前記偏差の大小を比較し、前記制御器に
入力される信号ルートを切替えるリレーを備え九比I2
器とから成る原子炉給水制御装置において、検出水位と
設定水位との偏差が予め定められ九個差量を越えた時、
前記制御器に入力される水位偏差信号を拡大して修正水
位偏差信号として出力する比例増幅器を介装したことを
特徴とする原子炉給水制御装置。 2 比較器のリレーは、水位偏差信号が予め定められな
偏差量より小さい時にはそれをそのまま制御器へ、大き
い時には比例増幅器によって増幅修正された修正水位偏
差信号として制御器へ切換出力させるよう動作する特許
請求の範囲第1項記載の原子炉給水制御装置。
[Claims] 1. A water level detector that detects the reactor water level in the reactor pressure vessel, a water level setting device that sets the reactor water level at Wr constant, and the deviation between the detected water level and the set water level as water level deviation. An addition/subtraction calculator that outputs as a signal, and a controller that has proportional, integral, and differential elements that control the water supply flow rate drive control mechanism based on the input water level deviation signal, compare the magnitude of the deviation, and compare the magnitude of the deviation and Nine ratio I2 equipped with a relay to switch the signal route.
In the reactor water supply control system, which consists of a
A nuclear reactor water supply control system, characterized in that a proportional amplifier is installed for amplifying a water level deviation signal input to the controller and outputting the expanded water level deviation signal as a corrected water level deviation signal. 2 The relay of the comparator operates so that when the water level deviation signal is smaller than a predetermined deviation amount, it is sent to the controller as is, and when it is larger, it is switched and output to the controller as a corrected water level deviation signal that has been amplified and corrected by the proportional amplifier. A nuclear reactor feed water control device according to claim 1.
JP56138070A 1981-09-02 1981-09-02 Reactor feedwater control device Pending JPS5838897A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56138070A JPS5838897A (en) 1981-09-02 1981-09-02 Reactor feedwater control device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56138070A JPS5838897A (en) 1981-09-02 1981-09-02 Reactor feedwater control device

Publications (1)

Publication Number Publication Date
JPS5838897A true JPS5838897A (en) 1983-03-07

Family

ID=15213264

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56138070A Pending JPS5838897A (en) 1981-09-02 1981-09-02 Reactor feedwater control device

Country Status (1)

Country Link
JP (1) JPS5838897A (en)

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