JPH03213603A - Controller for turbine steam governing valve - Google Patents

Controller for turbine steam governing valve

Info

Publication number
JPH03213603A
JPH03213603A JP2006824A JP682490A JPH03213603A JP H03213603 A JPH03213603 A JP H03213603A JP 2006824 A JP2006824 A JP 2006824A JP 682490 A JP682490 A JP 682490A JP H03213603 A JPH03213603 A JP H03213603A
Authority
JP
Japan
Prior art keywords
reactor
turbine
output
turbine steam
control 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.)
Granted
Application number
JP2006824A
Other languages
Japanese (ja)
Other versions
JP2863581B2 (en
Inventor
Toshihiro Fujii
敏浩 藤井
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 JP2006824A priority Critical patent/JP2863581B2/en
Publication of JPH03213603A publication Critical patent/JPH03213603A/en
Application granted granted Critical
Publication of JP2863581B2 publication Critical patent/JP2863581B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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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  • Control Of Turbines (AREA)

Abstract

PURPOSE:To moderate a transient phenomenon in a nuclear reactor at the time of closure of a turbine steam governing valve, in a controller where a valve position control circuit controls the position of the steam governing valve, by providing a change rate restricting device for restricting a closing speed of the steam governing valve, and varying a preset value according to the output of the reactor. CONSTITUTION:In a controller for a turbine steam governing value, the position of a steam governing valve 3 is determined according to an opening degree requiring signal 10 output from a pressure controller 9 on the basis of a nuclear reactor pressure signal 8 from a reactor pressure vessel 1, via a valve position control circuit 11. A power load unbalance relay 14 for inputting a turbine first-stage steam chamber pressure signal 12 and a current signal 13 from an electric line 7 is adapted to give an output to a rapid operational mode start circuit 15 when an output deviation exceeds a predetermined value, to rapidly close the steam governing valve 3 as well as to operate an emergency reactor shutdown system 16. In this case, the valve position control circuit 11 is provided therein with a change rate restricting device 18, a preset value of which can be varied according to a reactor output equivalent signal 19 by means of a change rate setting control circuit 20.

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は沸騰水型軽水炉を備えた原子力発電プラントに
おけるタービン蒸気加減弁制御装置に係り、特に定格出
力運転中の圧力制御装置等の故障によって生じるタービ
ン蒸気加減弁の閉鎖時において、原子炉の過渡事象を緩
和することができるとともに、原子炉出力が低い状態で
発電機負荷遮断が生じた場合において、タービン主軸の
回転数上昇が設計目標値を超えることを防止しかつ原子
炉の過渡事象を緩和することができるようにしたタービ
ン蒸気加減弁制御装置に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a turbine steam control valve control device in a nuclear power plant equipped with a boiling water type light water reactor, and particularly relates to a pressure control device during rated power operation. It is possible to alleviate transient events in the reactor when the turbine steam control valve is closed due to a failure of equipment, etc., and to reduce the rotational speed of the turbine main shaft in the event of generator load shedding while the reactor output is low. The present invention relates to a turbine steam control valve control device that can prevent the rise from exceeding a design target value and alleviate transient events in a nuclear reactor.

(従来の技術) 沸騰水型軽水炉を備えた原子力発電プラントにおいては
、圧力制御装置等の故障によりタービン蒸気加減弁の閉
鎖要求信号が出力された場合、特にその閉鎖時間を制限
するような回路が設けられていないために、タービン蒸
気加減弁は非常に速い速度で閉鎖する。その閉鎖時間は
沸騰水型原子炉を備えた一般的な原子力発電プラントで
は、概ね数秒未満である。
(Prior art) In a nuclear power plant equipped with a boiling water reactor, when a turbine steam control valve closure request signal is output due to a failure in a pressure control device, etc., a circuit that specifically limits the closure time is installed. Because it is not provided, the turbine steam control valve closes at a very rapid rate. The shutdown time is generally less than a few seconds in a typical nuclear power plant with a boiling water reactor.

(発明が解決しようとする課題) ところが、このような速い速度でタービン蒸気加減弁か
閉鎖すると、原子炉の発生蒸気の流出が制限されるため
に、原子炉の圧力が上昇し、その結果上して炉心内のボ
イドが潰れて正の反応度が投入され、原子炉の出力が増
加する。動特性解析の結果によれば、原子炉の出力上昇
で燃料の健全性上の余裕か低下する可能性があることか
分っている。
(Problem to be Solved by the Invention) However, when the turbine steam control valve is closed at such a high speed, the outflow of the steam generated in the reactor is restricted, and the pressure in the reactor increases, resulting in This collapses the voids in the reactor core, injecting positive reactivity and increasing the reactor's output. According to the results of the dynamic characteristic analysis, it is known that there is a possibility that the margin in terms of fuel integrity will decrease as the output of the reactor increases.

これを緩和するための一方策として、タービン蒸気加減
弁の閉鎖時間を現状よりも遅くすることか考えられる。
One possible way to alleviate this problem is to make the turbine steam control valve close more slowly than it currently does.

動特性解析の結果によれば、タービン蒸気加減弁の閉鎖
時間を全開から全閉まで6〜8秒以上とすれば、過渡事
象発生時の燃料健全性を確保できることが分っている。
According to the results of dynamic characteristic analysis, it has been found that fuel integrity can be ensured when a transient event occurs if the turbine steam control valve is closed for 6 to 8 seconds or more from fully open to fully closed.

この目的のため、タービン蒸気加減弁の弁位置制御回路
に閉鎖速度の変化率制限器を設けて閉鎖時間を遅くする
ことは有効な対策であると言える。
For this purpose, it can be said that it is an effective measure to slow down the closing time by providing a closing speed change rate limiter in the valve position control circuit of the turbine steam control valve.

一方、沸騰水型軽水炉を備えた原子力発電プラントにお
いては、プラント運転中に電力系統が遮断された場合、
タービン発電機への蒸気供給を速やかに停止してタービ
ン主軸の回転数が上昇するのを防ぐため、タービン蒸気
加減弁を急速に閉鎖するめの回路が設けられている。こ
の原子力発電プラントでは発電機負荷の遮断時にタービ
ン主軸の回転数が定格値の約110%を超えないことを
設計目標としており、この観点からタービン蒸気加減弁
の閉鎖時間は速いことか要求される。
On the other hand, in a nuclear power plant equipped with a boiling water reactor, if the power grid is interrupted during plant operation,
In order to promptly stop the steam supply to the turbine generator and prevent the rotational speed of the turbine main shaft from increasing, a circuit is provided for rapidly closing the turbine steam control valve. The design goal of this nuclear power plant is that the rotational speed of the turbine main shaft does not exceed approximately 110% of the rated value when the generator load is cut off, and from this point of view, the closing time of the turbine steam control valve is required to be fast. .

この目的のため、原子力発電プラントにはパワーロード
アンバランスリレーと呼ばれる保護リレーがあり、ター
ビンの第1段蒸気室圧力より換算した原子炉出力と送電
線電流より求めた発電機負荷を常時比較して、その差が
40%を超えたとき、タービン蒸気加減弁を急速作動モ
ードで閉鎖する構成としている。このとき、原子炉側は
急激な圧力上昇で出力が増加し、燃料健全性上の余裕は
低下するものの、急速作動モードの起動と同時に生じる
原子炉スクラム等によって核沸騰状態は維持され、特に
問題となる事象には至らないように設計されている。急
速作動モードによるタービン蒸気加減弁の閉鎖時間は極
めて速く、通常約100m5ec以下であり、譬え発電
機負荷遮断が生じてもタービン主軸の回転数が設計目標
値を超えることはない。
For this purpose, nuclear power plants have a protection relay called a power load unbalance relay, which constantly compares the reactor output calculated from the turbine's first stage steam chamber pressure and the generator load calculated from the transmission line current. When the difference exceeds 40%, the turbine steam control valve is closed in a rapid operation mode. At this time, the output of the reactor increases due to a sudden pressure rise, and the margin for fuel integrity decreases, but the nucleate boiling state is maintained due to the reactor scram, etc. that occurs at the same time as the start of the rapid operation mode, which is particularly problematic. It is designed to prevent this from happening. The closing time of the turbine steam control valve in the rapid operation mode is extremely fast, usually less than about 100 m5ec, and even if a generator load shedding occurs, the rotation speed of the turbine main shaft will not exceed the design target value.

しかしなから、原子炉の初期出力が定格出力より低い状
態で発電機負荷遮断が生じたときにパワーロードアンバ
ランスリレーの動作設定値に至らない場合かある。それ
は、原子炉出力が40%以下で発電機負荷遮断か生じた
場合が代表的であるが、実際には原子炉出力が60〜7
5%の場合でもパワーロードアンバランスリレーの動作
に至らないことがある。
However, when generator load shedding occurs when the initial output of the reactor is lower than the rated output, there are cases where the operation set value of the power load imbalance relay is not reached. Typically, this occurs when the reactor output is 40% or less and generator load shedding occurs, but in reality, the reactor output is 60 to 7%.
Even in the case of 5%, the power load unbalance relay may not operate.

これは、初めに原子炉出力が60〜75%で運転されて
いるときに電力系統周波数が少し上昇して、その後に発
電機負荷遮断に至った場合である。
This is the case when the power system frequency increases slightly when the reactor power is initially operating at 60-75%, and then the generator load is cut off.

一般に系統周波数が上昇すると、圧力制御装置はこれを
検出してタービン主軸の回転数を低下すべくタービン蒸
気加減弁をやや絞るように指令する。
Generally, when the system frequency increases, the pressure control device detects this and instructs the turbine steam control valve to be slightly throttled in order to reduce the rotational speed of the turbine main shaft.

このため、原子炉からタービン発電機に供給される蒸気
の量が減少し、タービン第1段蒸気室圧力が低下し、結
果としてパワーロードアンバランスリレーに入力される
原子炉出力相当信号が40%以下になっていると、譬え
そこで発電機負荷遮断か生じてもパワーロードアンバラ
ンスリレーは動作しない。パワーロードアンバランスリ
レーが動作しない場合、タービン蒸気加減弁の急速作動
モトは働かず、タービン蒸気加減弁は圧力制御装置の指
令に従って、急速作動モードよりは遅い通常閉鎖モード
で閉鎖する。
For this reason, the amount of steam supplied from the reactor to the turbine generator decreases, the pressure in the turbine first stage steam chamber decreases, and as a result, the reactor output equivalent signal input to the power load imbalance relay decreases by 40%. If the following conditions occur, the power load unbalance relay will not operate even if a generator load shedding occurs. If the power load unbalance relay is not activated, the quick-actuation mode of the turbine steam control valve is not activated, and the turbine steam control valve closes in a normal closing mode, which is slower than the rapid-actuation mode, according to the commands of the pressure control device.

解析の結果によれば、このような場合にタービン主軸の
回転数増加は最も厳しくなることが知られており、設計
目標である定格値の約110%以下を守るためには、タ
ービン蒸気加減弁の通常閉鎖モードでの閉鎖時間は全開
から全閉まで6〜8秒程度以下であることが要求される
According to the analysis results, it is known that the increase in the rotation speed of the turbine main shaft becomes the most severe in such cases, and in order to maintain the design target of approximately 110% or less of the rated value, it is necessary to increase the turbine steam control valve. The closing time in the normal closing mode is required to be approximately 6 to 8 seconds or less from fully open to fully closed.

いま、定格出力運転中において、圧力制御装置の故障に
よってタービン蒸気加減弁の閉鎖要求信号が生じたとき
の過渡事象を緩和するためのタービン蒸気加減弁の最小
許容閉鎖時間をα秒、パワーローFアンバンスリレーが
動作しないような発電機負荷遮断が生じたときのタービ
ン主軸の回転数増加を約110%以下に抑えるためのタ
ービン蒸気加減弁の最大許容閉鎖時間をβ秒として、個
々の発電プラント毎にこれを評価すると、β〈αである
かまたはα〈βあってもその差か少なく、実際にタービ
ン蒸気加減弁の弁位置制御回路に変化率制御器を設けて
閉鎖時間を制限することは難しいという結果か得られて
いる。
Now, during rated power operation, the minimum allowable closing time of the turbine steam regulator is set to α seconds, power low The maximum allowable closing time of the turbine steam control valve to suppress the increase in rotation speed of the turbine main shaft to approximately 110% or less in the event of a generator load shedding in which the imbalance relay does not operate is assumed to be β seconds, and each power generation plant If you evaluate this for each case, it will be found that β < α or even if α < β, the difference is small, and it is necessary to actually install a rate of change controller in the valve position control circuit of the turbine steam control valve to limit the closing time. The results show that it is difficult.

なお、現状の原子力発電プラントにおいて、パワーロー
トアンバランスリレーの設定値は40%であり、この設
定値を下げて発電機負荷遮断か生したときはいっても急
速作動モードによりタービン蒸気加減弁を急速閉鎖させ
れば、タービン主軸回転数の上ゲ7は問題なくなるが、
この場合には平行して生しる原子炉スクラムによって原
子炉か停止してしまうというデメリットがあり現実的な
案ではない。
In addition, in current nuclear power plants, the setting value of the power rotor unbalance relay is 40%, and even if this setting value is lowered and the generator load is cut off, the turbine steam control valve will be rapidly turned on by the rapid operation mode. If it is closed, the upper part of the turbine shaft rotational speed will not be a problem, but
In this case, there is a disadvantage that the reactor will be shut down due to reactor scram occurring in parallel, so it is not a realistic plan.

本発明は上記の事情を考慮してなされたもので、タービ
ン蒸気加減弁の閉鎖時間について、圧力制御装置の故障
によって生しるタービン蒸気加減弁の閉鎖時の、原子炉
の過渡事象を緩和するために閉鎖時間を遅くする必要が
あるという要求と、パワーロードアンバランスリレーか
動作せずタービン蒸気加減弁の急速作動モードが作動し
ないような発電機負荷遮断か生したときに、タービン主
軸の回転数上昇を設計目標値以下に抑えるために閉鎖時
間を速くする必要があるという要求の2つの要求を満た
すことができるタービン蒸気加減弁制御装置を提供する
ことを目的とする。
The present invention has been made in consideration of the above circumstances, and is intended to alleviate transient events in a nuclear reactor when the turbine steam regulating valve is closed due to a failure of the pressure control device. Due to the requirement that the closing time needs to be slowed down, the rotation of the turbine main shaft occurs when there is a generator load shedding, such as when the power load unbalance relay does not operate and the rapid operation mode of the turbine steam control valve does not operate. It is an object of the present invention to provide a turbine steam control valve control device that can satisfy two requirements: the need to shorten the closing time in order to suppress the increase in the number of steam regulators to below a design target value.

〔発明の構成〕[Structure of the invention]

(課題を解決するための手段) 上記の目的を達成するため、本発明は、沸騰水型軽水炉
からタービン発電機に蒸気を案内する主蒸気管に設けら
れたタービン蒸気加減弁と、このタービン蒸気加減弁の
弁位置を制御する弁位置制御回路とを備えたタービン蒸
気加減弁制御装置において、上記タービン蒸気加減弁の
閉鎖速度を制限する変化率制限器と、この変化率制限器
の設定値を原子炉の出力に応じて変化させる変化率設定
制御回路とを備えたものである。
(Means for Solving the Problems) In order to achieve the above object, the present invention provides a turbine steam control valve provided in a main steam pipe that guides steam from a boiling water reactor to a turbine generator, and a turbine steam control valve provided in a main steam pipe that guides steam from a boiling water reactor to a turbine generator. A turbine steam regulator control device comprising a valve position control circuit that controls the valve position of a regulator valve, a rate of change limiter that limits the closing speed of the turbine steam regulator, and a set value of the rate of change limiter. It is equipped with a rate-of-change setting control circuit that changes the output according to the reactor output.

(作用) 原子炉出力が定格出力程度に高いときには、変化率設定
制御回路か、圧力制御装置等の故障によって、タービン
蒸気加減弁の閉鎖要求信号か生したときの、過渡事象を
緩和するためのタービン蒸気加減弁の最小許容閉鎖時間
よりも閉鎖速度が遅くなるように、変化率制限器の設定
値を変化させる。
(Function) When the reactor output is as high as the rated output, this function is used to alleviate transient events when a turbine steam control valve closing request signal is generated due to a failure in the rate of change setting control circuit or pressure control device, etc. The setting value of the rate of change limiter is varied so that the closing speed is slower than the minimum allowable closing time of the turbine steam control valve.

変化率制限器はその設定値に基づいて上記最小許容閉鎖
時間よりも遅くなるようにタービン蒸気加減弁の閉鎖速
度を制限する。したがって、原子炉の出力上昇で燃料の
健全性上の余裕が低下するような原子炉の過渡事象を緩
和することができる。
The rate of change limiter limits the closing speed of the turbine steam control valve to be slower than the minimum allowable closing time based on its set value. Therefore, it is possible to alleviate a transient event in the reactor in which the margin in terms of fuel integrity decreases due to an increase in the output of the reactor.

一方、原子炉出力がパワーロードアンバランスリレーが
動作しないことがある程度に低いときには、変化率設定
制御回路か、パワーロードアンバランスリレーか動作し
ないうような発電機負荷遮断が生じたときのタービン主
軸の回転数増加を設計目標値以下に抑えるためのタービ
ン蒸気加減弁の最大許容閉鎖時間よりも速くなるように
、変化率制限器の設定値を変化させる。
On the other hand, when the reactor output is low enough that the power load unbalance relay does not operate, the rate of change setting control circuit or the power load unbalance relay does not operate. The setting value of the rate of change limiter is changed so that it becomes faster than the maximum allowable closing time of the turbine steam control valve in order to suppress the increase in the rotational speed of the turbine to below the design target value.

変化率制限器はその設定値に基づいて上記最大許容閉鎖
時間よりも速くなるようにタービン蒸気加減弁の閉鎖速
度を制限する。したかって、タービン主軸の回転数上昇
を設計目標値以下に抑えることができる。この場合、原
子炉出力が低いため、タービン蒸気加減弁の閉鎖速度を
速くしても、原子炉の過渡事象を緩和することができる
The rate of change limiter limits the closing speed of the turbine steam control valve to be faster than the maximum allowable closing time based on its set value. Therefore, the increase in the rotational speed of the turbine main shaft can be suppressed to below the design target value. In this case, since the reactor power is low, transient events in the reactor can be alleviated even if the closing speed of the turbine steam control valve is increased.

(実施例) 以下、本発明に係るタービン蒸気加減弁制御装置の一実
施例について添付図面を参照して説明する。
(Example) Hereinafter, an example of a turbine steam control valve control device according to the present invention will be described with reference to the accompanying drawings.

第1図において、原子炉圧力容器1には主蒸気管2が接
続され、この主蒸気管2は下流においてタービン蒸気加
減弁3を介装した後、タービン4に接続される。タービ
ン4はタービン主軸5を介して発電機6と連結され、こ
の発電機6て発電された電力は送電線7によって電力系
統網に送電される。
In FIG. 1, a main steam pipe 2 is connected to a reactor pressure vessel 1, and this main steam pipe 2 is connected to a turbine 4 after a turbine steam control valve 3 is inserted downstream. The turbine 4 is connected to a generator 6 via a turbine main shaft 5, and the power generated by the generator 6 is transmitted to the power grid via a power transmission line 7.

一方、原子炉圧力容器1からの原子炉圧力信号8が圧力
制御装置9に入力されており、この圧力制御装置9はタ
ービン蒸気加減弁3の開度要求信号10を出力するよう
になっている。この開度要求信号10はタービン蒸気加
減弁弁位置制御回路11に入力され、このタービン蒸気
加減弁弁位置制御回路11は開度要求信号10に従って
、タピン蒸気加減弁3の弁位置を決定するようになって
いる。
On the other hand, a reactor pressure signal 8 from the reactor pressure vessel 1 is input to a pressure control device 9, and this pressure control device 9 outputs an opening request signal 10 for the turbine steam control valve 3. . This opening request signal 10 is input to a turbine steam regulating valve position control circuit 11, and this turbine steam regulating valve position control circuit 11 determines the valve position of the tapin steam regulating valve 3 according to the opening request signal 10. It has become.

また、タービン4からのタービン第1段蒸気室圧力信号
12と、送電線7からの電流信号13がパワーロードア
ンバランスリレー14に入力されており、このパワーロ
ードアンバランスリレー14はそれらの出力偏差が40
%以上のときに、タービン蒸気加減弁の急速作動モード
を起動する急速作動モード起動回路15に信号を送って
、タービン蒸気加減弁3を急速閉鎖させるとともに、原
子炉緊急停止系16に信号を送って原子炉を直ちにスク
ラムさせる。
Further, a turbine first stage steam chamber pressure signal 12 from the turbine 4 and a current signal 13 from the power transmission line 7 are input to a power load unbalance relay 14, and this power load unbalance relay 14 detects the output deviation. is 40
% or more, a signal is sent to the rapid operation mode starting circuit 15 that starts the rapid operation mode of the turbine steam control valve to rapidly close the turbine steam control valve 3, and a signal is sent to the reactor emergency shutdown system 16. immediately scram the reactor.

いま、圧力制御装置9が故障して、タービン蒸気加減弁
3を閉鎖させる開度要求信号10が出力されると、ター
ビン蒸気加減弁3は数秒で全閉に至り、原子炉の圧力が
上昇して、燃料健全性上飯しい事象となる。また、電力
系統の周波数が一時的に上昇したり、発電機負荷遮断が
生じて、タービン主軸5の回転数が上昇すると、タービ
ン回転数上昇信号17が圧力制御装置9に伝えられて、
タービン蒸気加減弁3を閉鎖するような指令が発せられ
る。
If the pressure control device 9 malfunctions and the opening request signal 10 that closes the turbine steam control valve 3 is output, the turbine steam control valve 3 will be fully closed in a few seconds, and the reactor pressure will rise. As a result, fuel integrity becomes a problem. Further, when the frequency of the power system temporarily increases or generator load cutoff occurs, and the rotation speed of the turbine main shaft 5 increases, a turbine rotation speed increase signal 17 is transmitted to the pressure control device 9.
A command is issued to close the turbine steam control valve 3.

第2図は圧力制御装置9に故障が生じてタービン蒸気加
減弁3がある時間で閉鎖したと仮定して実施した動特性
解析の結果から、タービン蒸気加減弁3の閉鎖時間の最
小許容値αを原子炉の出力毎に求めたものであり、定格
出力運転状態では、その値αは6〜8秒程度である。ま
た、原子炉出力が低下した状態ではαは徐々に小さくな
り、例えば50〜60%出力状態では相当速く閉鎖して
も、原子炉の燃料健全性は充分に維持することが可能で
ある。
Figure 2 shows the minimum allowable value α for the closing time of the turbine steam regulator 3 based on the results of a dynamic characteristic analysis conducted assuming that a failure occurred in the pressure control device 9 and the turbine steam regulator 3 was closed for a certain period of time. is determined for each reactor output, and in the rated output operating state, the value α is about 6 to 8 seconds. Further, in a state where the reactor power is reduced, α gradually decreases, and even if the reactor is shut down fairly quickly in a state of 50 to 60% power, for example, the fuel integrity of the reactor can be sufficiently maintained.

一方、パワーロードアンバランスリレー14が動作しな
いような発電機負荷遮断が生じる原子炉出力は、個々の
沸騰水型軽水炉によって異なるが、概ね60〜75%程
度である。このような場合において、タービン蒸気加減
弁3の最大許容閉鎖時間βは、これも個々の沸騰水型軽
水炉によって異なるものの、概ね5〜7秒程度である。
On the other hand, the reactor output at which generator load shedding occurs such that the power load unbalance relay 14 does not operate varies depending on the individual boiling water type light water reactor, but is approximately 60 to 75%. In such a case, the maximum allowable closing time β of the turbine steam control valve 3 is approximately 5 to 7 seconds, although this also varies depending on the individual boiling water reactor.

そこで、第2図にはこの観点からの制約条件も併せて記
載している。従来の沸騰水型軽水炉のタービン蒸気加減
弁弁位置制御回路11においては、タービン蒸気加減弁
3の閉鎖時間を制限する回路は設けられていないが、こ
れがない場合のタービン蒸気加減弁3の実際の閉鎖時間
γはタービン蒸気加減弁3本体の構造によって決まり、
概ね数秒未満である。
Therefore, constraint conditions from this viewpoint are also shown in FIG. 2. The conventional turbine steam regulator valve position control circuit 11 of a boiling water type light water reactor is not provided with a circuit that limits the closing time of the turbine steam regulator valve 3. The closing time γ is determined by the structure of the turbine steam control valve 3 body,
Generally less than a few seconds.

これらのことを考慮すると、原子炉の燃料健全性を維持
するためには、第2図における線αと線γの交点P。の
出力以上では、タービン蒸気加減弁3の閉鎖時間を線α
以上になるように制御する必要があることがわかる。定
格出力運転状態でのαがβより大きいときは、全出力領
域に亘って一定の値を用いてタービン蒸気加減弁3の閉
鎖時間を制限することは不可能であるが、これを第2図
の破線Aで示すように、原子炉出力に応じて可変とする
ことにより、当初の要求を満足する構成とすることがで
きる。なお、破線Aは線αを包絡するものなら曲線状あ
るいは階段状等としてもよい。
Taking these things into consideration, in order to maintain the fuel integrity of the reactor, the intersection point P of line α and line γ in FIG. At outputs above , the closing time of the turbine steam control valve 3 is set by the line
It can be seen that it is necessary to control so that the above is achieved. When α is larger than β in the rated power operating state, it is impossible to limit the closing time of the turbine steam control valve 3 using a constant value over the entire power range, but this is shown in Fig. 2. As shown by the broken line A, by making it variable according to the reactor output, it is possible to create a configuration that satisfies the initial requirements. Note that the broken line A may be curved, stepped, etc. as long as it envelops the line α.

そこで、本実施例においては、タービン蒸気加減弁弁位
置制御回路11内にタービン蒸気加減弁3の閉鎖速度を
制限する変化率制限器18を設けた。そして、第2図の
破線Aに示すようにタービン蒸気加減弁3の閉鎖時間を
変化させるため、原子炉出力またはそれに相当する原子
炉出力相当信号19を入力し、変化率制限器18の設定
値を原子炉の出力に応じて変化させる変化率設定制御回
路20を設けた。
Therefore, in this embodiment, a change rate limiter 18 is provided in the turbine steam regulator valve position control circuit 11 to limit the closing speed of the turbine steam regulator valve 3. Then, in order to change the closing time of the turbine steam control valve 3 as shown by the broken line A in FIG. A rate-of-change setting control circuit 20 is provided to change the rate of change according to the output of the reactor.

この実施例において、原子炉出力が定格出力程度に高い
ときには、変化率設定制御回路20が、圧力制御装置9
等の故障によって、タービン蒸気加減弁3の閉鎖要求信
号が生じたときの、過渡事象を緩和するためのタービン
蒸気加減弁3の最小許容閉鎖時間αよりも閉鎖速度が遅
(なるように、変化率制限器18の設定値を変化させる
In this embodiment, when the reactor power is as high as the rated power, the rate of change setting control circuit 20 controls the pressure control device 9.
When a closure request signal for the turbine steam regulator 3 is generated due to a failure such as, the closing speed is slower than the minimum allowable closing time α of the turbine steam regulator 3 for mitigating the transient event. The setting value of the rate limiter 18 is changed.

変化率制限器18はその設定値に基づいて上記最小許容
閉鎖時間αよりも遅くなるようにタービン蒸気加減弁3
の閉鎖速度を制限する。したがって、原子炉の出力上昇
で燃料の健全性上の余裕か低下するような原子炉の過渡
事象を緩和することかできる。
The rate of change limiter 18 controls the turbine steam control valve 3 so that the rate of change limiter 18 is later than the minimum allowable closing time α based on its set value.
limit the closing speed. Therefore, it is possible to alleviate a transient event in a nuclear reactor where an increase in the reactor's output causes a decrease in the margin for the soundness of the fuel.

一方、原子炉出力かパワーロードアンバランスリレー1
4か動作しないことかある程度に低いときには、変化率
設定制御回路20が、パワーロードアンバランスリレー
14か動作しないうような発電機負荷遮断が生じたとき
のタービン主軸5の回転数増加を設計目標値以下に抑え
るためのタービン蒸気加減弁3の最大許容閉鎖時間βよ
りも速くなるように、変化率制限器18の設定値を変化
させる。
On the other hand, reactor output or power load unbalance relay 1
When the rate of change setting control circuit 20 is low to a certain extent, such as when the power load imbalance relay 14 does not operate, the design target is set to increase the rotation speed of the turbine main shaft 5 when a generator load cutoff occurs such that the power load imbalance relay 14 does not operate. The setting value of the rate of change limiter 18 is changed so that it becomes faster than the maximum allowable closing time β of the turbine steam control valve 3 for suppressing the closing time to below the value.

変化率制限器18はその設定値に基づいて上記最大許容
閉鎖時間βよりも速くなるようにタービン蒸気加減弁3
の閉鎖速度を制限する。したがって、タービン主軸5の
回転数上昇を設計目標値以下に抑えることができる。こ
の場合、原子炉出力が低いため、タービン蒸気加減弁3
の閉鎖速度を速くしても、原子炉の過渡事象を緩和する
ことができる。
Based on the set value, the change rate limiter 18 controls the turbine steam control valve 3 so that the rate of change is faster than the maximum allowable closing time β.
limit the closing speed. Therefore, the increase in the rotational speed of the turbine main shaft 5 can be suppressed to below the design target value. In this case, since the reactor output is low, the turbine steam control valve 3
Faster closure speeds can also mitigate reactor transients.

〔発明の効果〕〔Effect of the invention〕

以上説明したように、本発明はタービン蒸気加減弁の閉
鎖速度を制限する変化率制限器と、この変化率制限器の
設定値を原子炉の出力に応じて変化させる変化率設定制
御回路とを備えたから、圧力制御装置の故障等によって
生しるタービン蒸気加減弁の閉鎖時の原子炉の過渡事象
を緩和することができるとともに、発電機負荷遮断時の
タービン主軸の回転数上昇を設計目標値以下に抑えるこ
とができる。
As explained above, the present invention includes a rate-of-change limiter that limits the closing speed of a turbine steam control valve, and a rate-of-change setting control circuit that changes the set value of this rate-of-change limiter in accordance with the output of the reactor. By preparing for this, it is possible to alleviate transient events in the reactor when the turbine steam control valve is closed due to a failure of the pressure control device, etc., and to reduce the increase in the rotation speed of the turbine main shaft to the design target value when the generator load is cut off. It can be kept below.

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

第1図は本発明に係るタービン蒸気加減弁制御装置を備
えた原子力発電プラントを示す構成図、第2図は上記実
施例において圧力制御装置の故障に関する動特性解析の
結果の一例とタービン蒸気加減弁の閉鎖時間の設定値の
関係を示す特性図である。 1 ・原子炉圧力容器、2・・主蒸気管、3・・・ター
ビン蒸気加減弁、4・・タービン、5・・・タービン主
軸、6・・・発電機、7・・・送電線、9・・・圧力制
御装置、11・・・タービン蒸気加減弁弁位置制御回路
、I2・・・タービン第1段蒸気室圧力信号、15・・
・急速作動モード起動回路、16・・・原子炉緊急停止
系、18・・変化率制限器、19・・原子炉出力相当信
号、20・・変化率設定制御回路。
FIG. 1 is a configuration diagram showing a nuclear power plant equipped with a turbine steam control valve control device according to the present invention, and FIG. 2 is an example of the results of dynamic characteristic analysis regarding failure of the pressure control device in the above embodiment and turbine steam control device. FIG. 3 is a characteristic diagram showing a relationship between set values of valve closing time. 1 - Reactor pressure vessel, 2... Main steam pipe, 3... Turbine steam control valve, 4... Turbine, 5... Turbine main shaft, 6... Generator, 7... Power transmission line, 9 ... Pressure control device, 11 ... Turbine steam control valve position control circuit, I2 ... Turbine first stage steam chamber pressure signal, 15 ...
- Rapid operation mode starting circuit, 16... Nuclear reactor emergency shutdown system, 18... Rate of change limiter, 19... Nuclear reactor output equivalent signal, 20... Rate of change setting control circuit.

Claims (1)

【特許請求の範囲】[Claims] 沸騰水型軽水炉からタービン発電機に蒸気を案内する主
蒸気管に設けられたタービン蒸気加減弁と、このタービ
ン蒸気加減弁の弁位置を制御する弁位置制御回路とを備
えたタービン蒸気加減弁制御装置において、上記タービ
ン蒸気加減弁の閉鎖速度を制限する変化率制限器と、こ
の変化率制限器の設定値を原子炉の出力に応じて変化さ
せる変化率設定制御回路とを備えたことを特徴とするタ
ービン蒸気加減弁制御装置。
A turbine steam control valve control that includes a turbine steam control valve installed in a main steam pipe that guides steam from a boiling water light water reactor to a turbine generator, and a valve position control circuit that controls the valve position of this turbine steam control valve. The apparatus is characterized by comprising a rate-of-change limiter that limits the closing speed of the turbine steam control valve, and a rate-of-change setting control circuit that changes the set value of the rate-of-change limiter in accordance with the output of the reactor. Turbine steam control valve control device.
JP2006824A 1990-01-16 1990-01-16 Turbine steam control valve controller Expired - Fee Related JP2863581B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2006824A JP2863581B2 (en) 1990-01-16 1990-01-16 Turbine steam control valve controller

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2006824A JP2863581B2 (en) 1990-01-16 1990-01-16 Turbine steam control valve controller

Publications (2)

Publication Number Publication Date
JPH03213603A true JPH03213603A (en) 1991-09-19
JP2863581B2 JP2863581B2 (en) 1999-03-03

Family

ID=11648970

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2006824A Expired - Fee Related JP2863581B2 (en) 1990-01-16 1990-01-16 Turbine steam control valve controller

Country Status (1)

Country Link
JP (1) JP2863581B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010216706A (en) * 2009-03-16 2010-09-30 Toshiba Corp Water supply control device and water supply control method
JP2018115970A (en) * 2017-01-19 2018-07-26 日立Geニュークリア・エナジー株式会社 Valve closing speed control device, boiling water nuclear power plant, and operation method of boiling water nuclear power plant

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010216706A (en) * 2009-03-16 2010-09-30 Toshiba Corp Water supply control device and water supply control method
JP2018115970A (en) * 2017-01-19 2018-07-26 日立Geニュークリア・エナジー株式会社 Valve closing speed control device, boiling water nuclear power plant, and operation method of boiling water nuclear power plant

Also Published As

Publication number Publication date
JP2863581B2 (en) 1999-03-03

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