JPS60114607A - Nuclear reactor feedwater controller for boiling-water type nuclear reactor - Google Patents

Nuclear reactor feedwater controller for boiling-water type nuclear reactor

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Publication number
JPS60114607A
JPS60114607A JP58221649A JP22164983A JPS60114607A JP S60114607 A JPS60114607 A JP S60114607A JP 58221649 A JP58221649 A JP 58221649A JP 22164983 A JP22164983 A JP 22164983A JP S60114607 A JPS60114607 A JP S60114607A
Authority
JP
Japan
Prior art keywords
signal
flow rate
reactor
water
main steam
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
JP58221649A
Other languages
Japanese (ja)
Inventor
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
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 JP58221649A priority Critical patent/JPS60114607A/en
Publication of JPS60114607A publication Critical patent/JPS60114607A/en
Pending legal-status Critical Current

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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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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

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

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は沸騰水型原子炉内の水位を予め設定された水位
に維持する沸騰水型原子炉の原子炉給水制御装置に間予
る。 。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a reactor water supply control system for a boiling water nuclear reactor that maintains the water level in the boiling water reactor at a preset water level. .

〔発明の技術的背景〕[Technical background of the invention]

一般に、沸騰水型原子炉を運転する場合には、安全運転
を行なうために、炉内の冷却材すなわち炉水の水位を一
定に維持しつつ運転される。この水位維持は原子炉出力
が変化する場合にも要求される。
Generally, when operating a boiling water nuclear reactor, the level of the coolant in the reactor, that is, the reactor water, is maintained constant in order to ensure safe operation. This water level maintenance is also required when reactor power changes.

このため従来は第1図に示すような原子炉給水制御装置
により炉水の水位維持を図っていた。
For this reason, conventionally, the water level of the reactor water has been maintained using a reactor water supply control system as shown in FIG.

図中、符号1は沸騰水型原子炉であり、この沸騰水型原
子炉1内で発生した蒸気は主蒸気流路2を通してタービ
ン3へ送られ、タービン3を回転させて発電機40発電
に供される。このタービン3を流出した蒸気は復水器5
において復水せしめられ、続いて給水ポンプ6によって
送給されるとともに給水流量制御器の1種である給水調
整弁7によって流量を制御されつつ給水として給水流路
8を通して沸騰水型原子炉1内へ送給される。
In the figure, reference numeral 1 indicates a boiling water reactor, and the steam generated in the boiling water reactor 1 is sent to a turbine 3 through a main steam flow path 2, which rotates the turbine 3 and generates electricity from a generator 40. Served. The steam flowing out of this turbine 3 is transferred to a condenser 5
The water is condensed in the boiling water reactor 1, and is then fed by the feed water pump 6, and is fed into the boiling water reactor 1 through the feed water channel 8 as feed water while the flow rate is controlled by the feed water regulating valve 7, which is a type of feed water flow rate controller. sent to.

この沸騰水型原子炉1内の炉水の水位維持は、水位計9
により水位を検知しつつ給水調整弁7の開度を調整して
行なわれる。
The water level of the reactor water in the boiling water reactor 1 is maintained by the water level gauge 9.
This is done by adjusting the opening degree of the water supply regulating valve 7 while detecting the water level.

この給水調整弁7の開度制御は自動的に行なわれる。The opening degree control of this water supply regulating valve 7 is performed automatically.

すなわち、主蒸気流路2に設けた主蒸気流量検知器10
によって主蒸気流量を検知し、給水流路8に設けた給水
流量検知器11によって給水流量を検知する。次に、ミ
スマツチ信号演算器12により両検知器10 、11か
らそれぞれ発せられる主蒸気流量信号10aと給水流量
信号11aとの差をめるとともに、その差にミスマツチ
ゲインGMとして所定の定数を乗じてミスマツチ信号1
2aを発する。その後、フィードバック信号演算器13
において、このミスマツチ信号12aと水位計9から送
られて来る水位信号9aとを加算してフィードバック信
号13aとして給水流量制御器14へ送出する。このフ
ィードバック信号13aとして、水位信号9aにミスマ
ツチ信号12aを加算するのは、原子炉1内の水位の変
化は主蒸気流量と給水流量とに差が生じた時に発生する
ものであるから、ミスマツチ信号12aを原子炉水位変
化の先行要素として作用させ、原子炉1の出力変更時等
の外乱による原子炉水位の変動をより小さく抑えるため
である。そして、給水流量制御器14において、フィー
ドバック信号13aと設定水位信号15aと差をめ、更
KPI形調節計16において前記差を零にする指令信号
14aを演算し、給水調整弁7へ送出する。この指令信
号14aを受けた給水調整弁7はその値に応じて開閉調
節され、給水流量を変化させる。この給水流量の変化は
前記と同様にしてフィードバックされて、原子炉1の水
位を一定に保持する給水流量となるように連続変化させ
られる。
That is, the main steam flow rate detector 10 provided in the main steam flow path 2
The main steam flow rate is detected by the water supply flow path 8, and the water supply flow rate is detected by the water supply flow rate detector 11 provided in the water supply flow path 8. Next, the mismatch signal calculator 12 calculates the difference between the main steam flow rate signal 10a and the feed water flow rate signal 11a respectively emitted from both detectors 10 and 11, and multiplies the difference by a predetermined constant as the mismatch gain GM. Mismatch signal 1
Emit 2a. After that, the feedback signal calculator 13
Then, this mismatch signal 12a and the water level signal 9a sent from the water level gauge 9 are added together and sent to the water supply flow rate controller 14 as a feedback signal 13a. The reason why the mismatch signal 12a is added to the water level signal 9a as this feedback signal 13a is that a change in the water level in the reactor 1 occurs when there is a difference between the main steam flow rate and the feed water flow rate. This is to cause the reactor water level 12a to act as a preceding element for changes in the reactor water level, thereby suppressing fluctuations in the reactor water level due to disturbances such as when changing the output of the reactor 1. Then, the water supply flow rate controller 14 calculates the difference between the feedback signal 13a and the set water level signal 15a, and the KPI type controller 16 calculates a command signal 14a that makes the difference zero, and sends it to the water supply adjustment valve 7. The water supply regulating valve 7 that receives this command signal 14a is adjusted to open or close according to the value of the command signal 14a, thereby changing the water supply flow rate. This change in the feed water flow rate is fed back in the same manner as described above, and is continuously changed so that the feed water flow rate maintains the water level of the reactor 1 constant.

〔背景技術の問題点〕[Problems with background technology]

このように従来装置においては、フィードバックにより
給水調整弁7を開閉させて、給水流量を適正値に保持せ
んとするものである。
In this way, in the conventional device, the water supply regulating valve 7 is opened and closed by feedback to maintain the water supply flow rate at an appropriate value.

この給水流量を原子炉出方変化等の外乱による影響を少
なくするには、ミスマツチ信号演算器12におけるミス
マツチゲインGMを大きくすればよい。
In order to reduce the influence of disturbances such as changes in the reactor output direction on this water supply flow rate, the mismatch gain GM in the mismatch signal calculator 12 may be increased.

一方、このミスマツチゲインGMを大きくすると給水調
整弁7の開閉のタイミングが実際の要求給水流量を維持
する弁開度と合致しなくなるおそれがあるので、十分に
ミスマツチゲインGMを大きくすることができないとい
う不都合があった。
On the other hand, if this mismatch gain GM is increased, the timing of opening and closing of the water supply regulating valve 7 may not match the valve opening degree that maintains the actual required water supply flow rate, so it is not possible to sufficiently increase the mismatch gain GM. The problem was that I couldn't do it.

〔発明の目的〕[Purpose of the invention]

本発明はこれらの点に鑑みてなされたものであり、原子
炉出力の急変等の外乱が生じても、原子炉内の水位の変
動を小さく抑えるとともに、常に安定的に動作して適正
給水流量を保持することができ、信頼性の高い沸騰水型
原子炉の原子炉給水制御装置を提供することを目的とす
る。
The present invention was made in view of these points, and even if a disturbance such as a sudden change in the reactor output occurs, fluctuations in the water level inside the reactor are suppressed to a minimum, and the present invention always operates stably to maintain an appropriate water supply flow rate. The purpose of the present invention is to provide a reactor water supply control device for a boiling water reactor that is capable of maintaining high reliability.

〔発明の概要〕[Summary of the invention]

本発明の沸騰水型原子炉の原子炉給水制御装置は、従来
装置に更に主蒸気流量信号の変化率をめるとともにこの
変化率をミスマツチ信号から減算して水位補正信号とし
てフィードバック信号演算器に向けて送出する補正演算
器を設けて、常に適正な指令信号を発するように形成し
たものである。
The reactor feed water control device for a boiling water reactor of the present invention further includes a change rate of the main steam flow rate signal in addition to the conventional device, subtracts this change rate from the mismatch signal, and sends it to a feedback signal calculator as a water level correction signal. A correction calculator is provided to send out a correct command signal to the target at all times.

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

以下、本発明の実施例を第2図および第3図について説
明する。
Embodiments of the present invention will be described below with reference to FIGS. 2 and 3.

第2図は本発明装置の構成を示しており、第1図と同一
部分には同一符号を付しである。
FIG. 2 shows the configuration of the apparatus of the present invention, and the same parts as in FIG. 1 are given the same reference numerals.

同図に示すように、本実施例はミスマツチ信号演算器1
2の後方に、丈に、補正演算器17を設けて形成されて
いる。この補正演算器17は、主蒸気流量検知器10か
ら発せられる生蒸気流量信号10aの変化を微分演算し
てめる変化率演算器18と、この変化率演算器18の出
力18aに所定の定数Gを乗じた値に上下限制限ゲート
をかけて主蒸気流量変化率信号19aを発する上下限制
限器19とを有し、この主蒸気流量変化率信号19aを
ミスマツチ信号12aから減算して、水位補正信号17
aとしてフィードバック信号演算器13へ送出する。
As shown in the figure, in this embodiment, the mismatch signal calculator 1
A correction computing unit 17 is provided at the rear of 2 and in the length. The correction calculator 17 includes a rate-of-change calculator 18 that performs a differential operation on the change in the live steam flow rate signal 10a emitted from the main steam flow rate detector 10, and a predetermined constant for the output 18a of the rate-of-change calculator 18. It has an upper and lower limit limiter 19 that applies an upper and lower limit limit gate to the value multiplied by Correction signal 17
It is sent to the feedback signal calculator 13 as a signal.

他の構成は従来例と同様である。Other configurations are similar to the conventional example.

次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.

原子炉出力が急減した場合を第3図により説明する。A case where the reactor output suddenly decreases will be explained with reference to FIG.

原子炉出力が急減すると、第3図(a)に示すように、
主蒸気流量信号10aが急減する。これにより給水流量
信号11aが主蒸気流量信号10aより大きくなり、ミ
スマツチ信号演算器12により演算されたミスマツチ信
号12aが、同図(blに示すように、正となって給水
流量を減少させる方向に変化する。
When the reactor output suddenly decreases, as shown in Figure 3(a),
The main steam flow rate signal 10a suddenly decreases. As a result, the feed water flow rate signal 11a becomes larger than the main steam flow rate signal 10a, and the mismatch signal 12a calculated by the mismatch signal calculator 12 becomes positive and decreases the feed water flow rate, as shown in FIG. Change.

同時に、変化率演算器18においてめられる主蒸気流量
変化率信号19aは、同図(C)に示すように、主蒸気
流量信号10aの急減に伴って負となる。
At the same time, the main steam flow rate change signal 19a calculated by the change rate calculator 18 becomes negative as the main steam flow rate signal 10a rapidly decreases, as shown in FIG.

そして、正となったミスマツチ信号12aから負となっ
た主蒸気流量変化率信号19aを減算して得られた水位
補正信号17aは、同図(d)に示すように、従来のミ
スマツチ信号12aのみの値(同図(d)破線)より主
蒸気流量変化率信号19aの分だけ大きい正の値となり
、給水流量を減少させる値となる。
The water level correction signal 17a obtained by subtracting the negative main steam flow rate change signal 19a from the positive mismatch signal 12a is, as shown in FIG. It becomes a positive value larger by the amount of the main steam flow rate change rate signal 19a than the value (broken line in FIG. 3(d)), and becomes a value that reduces the water supply flow rate.

よって、フィードバック信号演算器13によってめられ
るフィードバック信号13aは従来より大きくなり、設
定水位信号15aとの差が太きくなり、調節器14から
発せられる指令信号14aも大きくなり、給水流量制御
器である給水調整弁7を急速に閉弁させる。
Therefore, the feedback signal 13a determined by the feedback signal calculator 13 becomes larger than before, and the difference from the set water level signal 15a becomes larger, and the command signal 14a issued from the regulator 14 also becomes larger. The water supply regulating valve 7 is rapidly closed.

これにより、同図(e)に示すように、給水流量信号1
1aが従来の値(同図(e)破線)より早期に減少する
As a result, as shown in the same figure (e), the water supply flow rate signal 1
1a decreases earlier than the conventional value (dotted line in FIG. 6(e)).

従って、同図(f)に示すように、′原子炉水位信号9
aは、給水流量が主蒸気流量より一時的に大きくなるた
め設定水位(同図(f)のOレベル)より上昇するが、
同図(e)の示すように給水流量が従来の場合より早期
に減少するので、従来の原子炉水位信号(同図げ)の破
線)よりその上昇幅は小さく抑えられる。
Therefore, as shown in Figure (f), 'Reactor water level signal 9
a rises above the set water level (O level in figure (f)) because the feed water flow rate temporarily becomes larger than the main steam flow rate;
As shown in (e) of the same figure, the feed water flow rate decreases earlier than in the conventional case, so that the increase in the water level signal is suppressed to be smaller than that of the conventional reactor water level signal (the broken line in the same figure).

このようにして、原子炉1内の水位の変動を小さくし、
設定水位に保持することが行なわれる。
In this way, fluctuations in the water level inside the reactor 1 are reduced,
Holding at a set water level is carried out.

一方、原子炉出力が急増した場合には前記急減時の場合
と全く逆の応答によって、原子炉1内の水位の変動を小
さく抑制し、設定水位に保持されることとなる。
On the other hand, when the reactor output suddenly increases, the water level in the reactor 1 is kept at the set level by suppressing fluctuations in the water level by a completely opposite response to the sudden decrease.

し発明の効果〕 このように本発明は構成され作用するものであるから、
原子炉出力の急変等の外乱が生じても、原子炉内の水位
の変動を小さく抑えることができ、常に安定的に動作し
て適正給水流量を保持することができ、また、オスマツ
チゲインGMをより安定な方向に小さく設定しても、主
蒸気変化率信号により原子炉水位変動を太き(抑制する
ことができ、より安定な制御を行なうことができ、信頼
性が高くなる等の効果を奏する。
[Effects of the Invention] Since the present invention is constructed and operates in this manner,
Even if a disturbance such as a sudden change in reactor output occurs, fluctuations in the water level inside the reactor can be suppressed to a small level, and it can always operate stably and maintain an appropriate water supply flow rate. Even if it is set to a small value in the direction of more stability, the main steam change rate signal can widen (suppress) fluctuations in the reactor water level, resulting in more stable control and higher reliability. play.

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

第1図は従来の沸騰水型原子炉の原子炉給水制御装置を
示すブロック図、第2図は本発明の原子炉給水制御装置
の一実施例を示すブロック図、第3図(a)〜(f)は
本発明装置による各種信号の特性図を示す。 1・・・原子炉、7・・・給水調整弁(給水流量制御器
)、9・・・水位計、9a・・・水位信号、10・・・
主蒸気流量検知器、10a・・・主蒸気流量信号、11
・・・給水流量検知器、lla・・・給水流量信号、1
2・・・ミスマツチ信号演算器、12a・・・ミスマツ
チ信号、13・・・フィードバック信号演算器、13a
・・・フィードバック信号、14・・・調節器、14a
・・・指令信号、15a・・・設定水位信号、17・・
・補正演算器、17a・・・水位補正信号、18・・・
変化率演算器、19・・・上下限制限器、19a 主蒸
気流量変化率信号。 出願人代理人 猪 股 清 第3図
FIG. 1 is a block diagram showing a conventional reactor feed water control device for a boiling water reactor, FIG. 2 is a block diagram showing an embodiment of the reactor feed water control device of the present invention, and FIGS. (f) shows characteristic diagrams of various signals produced by the device of the present invention. DESCRIPTION OF SYMBOLS 1... Nuclear reactor, 7... Water supply adjustment valve (water supply flow rate controller), 9... Water level gauge, 9a... Water level signal, 10...
Main steam flow rate detector, 10a... Main steam flow rate signal, 11
...Water supply flow rate detector, lla...Water supply flow rate signal, 1
2... Mismatch signal calculator, 12a... Mismatch signal, 13... Feedback signal calculator, 13a
...Feedback signal, 14...Adjuster, 14a
...Command signal, 15a...Setting water level signal, 17...
・Correction calculator, 17a... Water level correction signal, 18...
Rate of change calculator, 19... Upper and lower limit limiter, 19a Main steam flow rate change signal. Applicant's agent Kiyoshi Inomata Figure 3

Claims (1)

【特許請求の範囲】 1、沸騰水型原子炉から流出される主蒸気流量を検知し
て主蒸気流量信号を発する主蒸気流量検知器と、前記沸
騰水型原子炉中へ流入する給水流量を検知して給水流量
信号を発する給水流量検知器と、前記沸騰水型原子炉内
の水位を検知して水位信号を発する水位計と、前記主蒸
気流量信号と給水流量信号との差をめて更にミスマツチ
ゲインを乗じてミスマツチ信号を発するミスマツチ信号
演算器と、このミスマツチ信号と前記水位信号とを加算
してフィードバック信号を発するフィードバック信号演
算器と、このフィードバック信号と設定水位との差をめ
るとともにその差を零にする指令信号を給水流路に設け
られた給水流量制御器に向けて発する調節器とにより形
成されている沸騰水型原子炉の原子炉給水制御装置にお
いて、前記主蒸気流量信号の変化率をめるとともに前記
ミスマツチ信号からこの変化率を減算して水位補正信号
として前記フィードバック信号演算器へ送出する補正演
算器を設けたことを特徴とする沸騰水型原子炉の原子炉
給水制御装置。 2、補正演算器は、主蒸気流量信号の変化を微分演算し
てめる変化率演算器と、この変化率演算器の出力に所定
の定数を乗じた値に上下限制限ゲートをかけて主蒸気流
量変化率信号を発する上下限制限器とを有することを特
徴とする特許請求の範囲第1項記載の沸騰水型原子炉の
原子炉給水制御装置。
[Scope of Claims] 1. A main steam flow rate detector that detects the flow rate of main steam flowing out from the boiling water reactor and generates a main steam flow rate signal, and a main steam flow rate detector that detects the flow rate of feed water flowing into the boiling water reactor. a feedwater flow rate detector that detects and issues a feedwater flow rate signal, a water level gauge that detects the water level in the boiling water reactor and issues a water level signal, and a difference between the main steam flow rate signal and the feedwater flow rate signal. Furthermore, a mismatch signal calculator multiplies a mismatch gain to generate a mismatch signal, a feedback signal calculator adds the mismatch signal and the water level signal to generate a feedback signal, and calculates the difference between this feedback signal and the set water level. In a reactor feed water control system for a boiling water reactor, the main steam A boiling water reactor comprising a correction calculator that calculates the rate of change of the flow rate signal, subtracts this rate of change from the mismatch signal, and sends the result as a water level correction signal to the feedback signal calculator. Reactor water supply control device. 2. The correction calculator consists of a rate-of-change calculator that performs differential calculations on changes in the main steam flow rate signal, and a value obtained by multiplying the output of this rate-of-change calculator by a predetermined constant by upper and lower limit gates. 2. A reactor feed water control system for a boiling water reactor according to claim 1, further comprising an upper and lower limit limiter for generating a steam flow rate change rate signal.
JP58221649A 1983-11-25 1983-11-25 Nuclear reactor feedwater controller for boiling-water type nuclear reactor Pending JPS60114607A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58221649A JPS60114607A (en) 1983-11-25 1983-11-25 Nuclear reactor feedwater controller for boiling-water type nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58221649A JPS60114607A (en) 1983-11-25 1983-11-25 Nuclear reactor feedwater controller for boiling-water type nuclear reactor

Publications (1)

Publication Number Publication Date
JPS60114607A true JPS60114607A (en) 1985-06-21

Family

ID=16770085

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58221649A Pending JPS60114607A (en) 1983-11-25 1983-11-25 Nuclear reactor feedwater controller for boiling-water type nuclear reactor

Country Status (1)

Country Link
JP (1) JPS60114607A (en)

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