JPH03215791A - Nuclear reactor output controller - Google Patents

Nuclear reactor output controller

Info

Publication number
JPH03215791A
JPH03215791A JP2010496A JP1049690A JPH03215791A JP H03215791 A JPH03215791 A JP H03215791A JP 2010496 A JP2010496 A JP 2010496A JP 1049690 A JP1049690 A JP 1049690A JP H03215791 A JPH03215791 A JP H03215791A
Authority
JP
Japan
Prior art keywords
pump speed
flow rate
deviation
signal
output
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
JP2010496A
Other languages
Japanese (ja)
Inventor
Yukio Takigawa
瀧川　幸夫
Shigeo Ehata
江畑　茂男
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 JP2010496A priority Critical patent/JPH03215791A/en
Publication of JPH03215791A publication Critical patent/JPH03215791A/en
Pending legal-status Critical Current

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Classifications

    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To evade operation almost in a natural circulation high output state and to prevent the output of a nuclear rector from vibrating by calculating the deviation between the total pump speed signal from a total pump speed arithmetic unit and the total pump speed request signal from a recirculation flow rate control system. CONSTITUTION:A deviation arithmetic unit 16 calculates the deviation between the total pump speed signal 13 from the total pump speed arithmetic unit 12 and the total pump speed request signal 15 from the recirculation flow rate control system 14 and inputs it to a comparing device 18. When the deviation is larger than a set value, the device 18 judges the trip of a recirculation pump 6 and outputs an operation signal 20 to a selected control rod inserting device 19 to insert a specific number of control rods 8 into a reactor core 2, thereby making the output in a natural state lower than the output on an 80% output flow rate control curve. Further, when the deviation is smaller than the set value, an operation signal is outputted to a recirculation pump speed controller 22 to prevent the speed of the pump 6 from becoming lower than a minimum pump speed, thereby limiting the lower-limit value of a reactor core flow rate to a flow rate corresponding to the lowest pump speed.

Description

【発明の詳細な説明】 〔発明の目的〕 （産業上の利用分野） 本発明は原子炉出力制御装置に係り、特に自然循環高出
力状態近傍での運転を回避するようにした原子炉出力制
御装置に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Field of Application) The present invention relates to a nuclear reactor power control device, and particularly to a nuclear reactor power control device that avoids operation near a natural circulation high power state. Regarding equipment.

（従来の技術） 沸騰水型原子炉（ＢＷＲ）においては、再循環ポンプの
電源喪失等により再循環ポンプ全数トリップが発生する
と、流量が減少し、流量制御曲線に沿って状態が変化し
、自然循環高出力状態に至る。(Prior art) In a boiling water reactor (BWR), when all recirculation pumps trip due to loss of power to the recirculation pumps, the flow rate decreases, the state changes along the flow rate control curve, and the natural Cyclic high output state is reached.

また、ポンプ速度ランバック等の制御信号による流量減
少としては、例えば次のような例が考えられる。すなわ
ち、電力系統事故等による発電機負荷遮断やタービン発
電機系の異常等によるタビントリップのような異常事象
が生じた場合には、タービンの保護のためタービン主蒸
気止め弁が急速に閉鎖する。このタービン主蒸気止め弁
の閉鎖と共にタービンバイパス弁が開くが、作動しない
場合には原子炉はスクラムする。また、このタビンバイ
パス弁の開閉によらず、タービン主蒸気止め弁の閉鎖と
共に、再循環ポンプをトリップさせ、炉心流量を自然循
環流量にまで減少させることにより、原子炉出力を抑制
するように設計されている。Furthermore, the following examples can be considered as examples of a flow rate reduction caused by a control signal such as a pump speed runback. That is, when an abnormal event such as a generator load cutoff due to a power system accident or a turbine trip due to an abnormality in the turbine generator system occurs, the turbine main steam stop valve is rapidly closed to protect the turbine. When the turbine main steam stop valve closes, the turbine bypass valve opens, but if it does not operate, the reactor will scram. In addition, the design is designed to suppress the reactor output by closing the turbine main steam stop valve and tripping the recirculation pump, reducing the core flow rate to the natural circulation flow rate, regardless of whether the turbine bypass valve is opened or closed. has been done.

ここで、タービンバイパス弁が作動した場合や、タービ
ンバイパス弁不作動によるスクラムができなかった場合
には、流量制御曲線に沿って炉心流量と原子炉出力が変
化し、最終的には自然循環状態で比較的高出力の運転状
態が実現される。この後者はスクラム不能異常過渡事象
（ＡＴＷＳ）と呼ばれ、特別な検討が行なわれている。Here, if the turbine bypass valve is activated or if a scram cannot occur due to the turbine bypass valve being inoperative, the core flow rate and reactor power will change along the flow control curve, and eventually a natural circulation state will occur. A relatively high output operating state is achieved. This latter is called an anomalous non-scrummable transient event (ATWS) and is the subject of special consideration.

ところで、この自然循環高出力状態では一般的に原子炉
炉心部の安定性の安定度が低く、場合によっては原子炉
出力の振動現象が生ずるおそれがあるため、自然循環高
出力状態で長時間運転することは望ましくない。By the way, in this natural circulation high power state, the stability of the reactor core is generally low, and in some cases, there is a risk that the reactor output may oscillate, so long-term operation in the natural circulation high power state is not recommended. It is not desirable to do so.

（発明が解決しようとする課題） 原子炉炉心部の安定性は一般的に炉心流量が少ない程、
また原子炉出力が高い程安定度が低く、流量制御曲線上
では流量が低い程安定度が低い。(Problem to be solved by the invention) In general, the stability of the nuclear reactor core is lower as the core flow rate is lower.
Furthermore, the higher the reactor output, the lower the stability, and on the flow rate control curve, the lower the flow rate, the lower the stability.

このため、同一流量制御曲線上では自然循環状態が最も
安定度が低くなる。したがって、原子炉炉心部の安定性
の安定度が低く、原子炉出力の振動現象が生ずるおそれ
がある自然循環高出力状態での運転を回避する必要があ
る。Therefore, on the same flow rate control curve, the natural circulation state has the lowest stability. Therefore, it is necessary to avoid operation in a natural circulation high power state where the stability of the reactor core is low and there is a risk that oscillations in the reactor power may occur.

本発明は上記の事情を考慮してなされたもので、自然循
環高出力状態近傍での運転を回避することにより、原子
炉炉心の安定性の安定度低下による原子炉出力の振動発
生の可能性を排除することができる原子炉出力制御装置
を提供することを目的とする。The present invention has been made in consideration of the above-mentioned circumstances, and by avoiding operation near the natural circulation high power state, there is a possibility of occurrence of fluctuations in the reactor power due to a decrease in the stability of the reactor core. The purpose of the present invention is to provide a nuclear reactor power control device that can eliminate the

〔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に、本発明は再循環ポンプの
総ポンプ速度を計算して総ポンプ速度信号を出力する総
ポンプ速度演算装置と、総ポンプ速度要求信号を出力す
る再循環流量制御系と、上記総ポンプ速度信号および総
ポンプ速度要求信号を入力してその偏差を演算する偏差
演算装置と、この偏差演算装置からの偏差信号を入力し
て予め定めた設定値と比較する比較装置と、その比較に
より偏差の方が大きい場合に予め定めた複数本の制御棒
を挿入することにより自然循環状態での出力を８０％出
力流量制御曲線上の出力よりも低く維持させる選択制御
棒挿入装置と、上記の比較により偏差の方が小さい場合
に炉心流量の下限値を最低ポンプ速度に相当する流量に
制限する再循環ポンプ速度制限器とを具備したものであ
る。(Means for Solving the Problems) In order to achieve the above object, the present invention provides a total pump speed calculation device that calculates the total pump speed of a recirculation pump and outputs a total pump speed signal, and a total pump speed request A recirculation flow rate control system that outputs a signal, a deviation calculation device that inputs the total pump speed signal and the total pump speed request signal and calculates the deviation, and inputs the deviation signal from this deviation calculation device to calculate a predetermined value. A comparison device that compares the set value with the set value, and if the deviation is larger than the comparison, by inserting a plurality of predetermined control rods, the output in the natural circulation state can be increased to 80% from the output on the flow rate control curve. It is equipped with a selective control rod insertion device that maintains the deviation at a low level, and a recirculation pump speed limiter that limits the lower limit of the core flow rate to the flow rate corresponding to the minimum pump speed if the deviation is smaller based on the above comparison. be.

（作用） 沸騰水型原子炉の再循環ポンプの総ポンプ速度を計算す
る総ポンプ速度演算装置からの総ポンプ速度信号および
再循環流量制御系からの総ポンプ速度要求信号を入力し
た偏差演算装置は、それらの偏差を演算して偏差信号を
出力する。この偏差信号は比較装置に入力され、予め定
めた設定値より偏差の方が大きい場合には、再循環ポン
プがトリップしたと判断し、選択制御棒挿入装置へ動作
信号を出力する。動作信号を入力した選択制御棒挿入装
置は予め定めた複数本の制御棒を炉心へ挿入し、自然循
環状態での出力を８０％出力流量制御曲線上の出力より
も低く維持する。(Function) The deviation calculation device that calculates the total pump speed of the recirculation pump of a boiling water reactor receives the total pump speed signal from the total pump speed calculation device and the total pump speed request signal from the recirculation flow rate control system. , calculates their deviation and outputs a deviation signal. This deviation signal is input to a comparison device, and if the deviation is larger than a predetermined set value, it is determined that the recirculation pump has tripped, and an operation signal is output to the selective control rod insertion device. The selective control rod insertion device that receives the operation signal inserts a plurality of predetermined control rods into the reactor core, and maintains the output in the natural circulation state lower than the output on the 80% output flow rate control curve.

一方、偏差が設定値よりも小さい場合には、ポンプ速度
ランバック等の制御信号による流量現象であると判断し
、再循環ポンプ速度制限器へ動作信号を出力する。動作
信号を入力した再循環ポンプ速度制限器は再循環ポンプ
のポンプ速度が最低ポンプ速度以下とならないように制
限し、炉心流量の下限値を最低ポンプ速度に相当する流
量に制限する。On the other hand, if the deviation is smaller than the set value, it is determined that the flow rate phenomenon is caused by a control signal such as a pump speed runback, and an operation signal is output to the recirculation pump speed limiter. The recirculation pump speed limiter receiving the operation signal limits the pump speed of the recirculation pump so that it does not fall below the minimum pump speed, and limits the lower limit value of the core flow rate to a flow rate corresponding to the minimum pump speed.

したがって、自然循環高出力状態での運転を自動的に回
避することができ、原子炉炉心の安定性の安定度低下に
よる原子炉出力の振動発生の可能性を排除することがで
きる。Therefore, operation in a natural circulation high power state can be automatically avoided, and the possibility of occurrence of fluctuations in the reactor power due to a decrease in the stability of the reactor core can be eliminated.

（実施例） 本発明に係る原子炉出力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。(Embodiment) An embodiment of the nuclear reactor power 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には炉心２が収容され
、原子炉圧力容器１内は冷却水３で満たされる。冷却水
３はジェットボンプ４により矢印５で示すように炉心２
の下方から炉心２内に導入され、炉心２を通過する間に
加熱されてその一部が蒸発し、原子炉圧力容器１内に設
けられた図示しない気水分離器および蒸気乾燥器を経て
、主蒸気配管から蒸気タービンに導かれ、蒸気タービン
を回転させて発電を行なう。In FIG. 1, a reactor core 2 is housed in a reactor pressure vessel 1, and the inside of the reactor pressure vessel 1 is filled with cooling water 3. Cooling water 3 is delivered to the core 2 by jet pump 4 as shown by arrow 5.
is introduced into the reactor core 2 from below, is heated while passing through the reactor core 2, a part of which evaporates, and passes through a steam separator and a steam dryer (not shown) provided in the reactor pressure vessel 1. The main steam pipe leads to the steam turbine, which rotates the steam turbine to generate electricity.

一方、炉心２内で蒸発しなかった冷却水３は原子炉圧力
容器１外に複数個設けられた再循環ポンブ６により再び
ジェットボンプ４へ強制循環され、ジェットポンプ４に
より再び下部プレナムから炉心２へ導入される。また、
炉心２には制御棒駆動機構７により制御棒８が挿抜可能
に設けられ、これにより原子炉出力が制御される。On the other hand, the cooling water 3 that has not evaporated in the reactor core 2 is forcibly circulated again to the jet pump 4 by a plurality of recirculation pumps 6 provided outside the reactor pressure vessel 1. will be introduced to Also,
A control rod 8 is provided in the reactor core 2 so as to be insertable and removable by a control rod drive mechanism 7, thereby controlling the reactor output.

ここで、第２図は第１図に示すような沸騰水型原子炉に
おける炉心流量と炉心出力との関係を示す特性図であり
、符号ａは１００％出力パターン流量制御曲線を示し、
符号ｂは自然循環曲線を示している。Here, FIG. 2 is a characteristic diagram showing the relationship between core flow rate and core power in a boiling water reactor as shown in FIG. 1, and symbol a indicates a 100% output pattern flow rate control curve,
The symbol b indicates a natural circulation curve.

また、符号Ｃで示す斜線領域は、沸騰水型原子炉におい
て原子炉炉心の安定性を維持するために回避すべき自然
循環高出力近傍の領域を示すものである。この領域Ｃの
状態に至ることを回避するためには、自然循環高出力状
態に至ることが予想される異常過渡事象時において、８
０％出力バタン流量制御曲線ｄ上の出力よりも原子炉出
力を低く維持させるか、あるいは再循環ボンプ６の総ポ
ンプ速度が最低ポンプ速度曲線ｅ以下とならないように
維持することが必要となる。Further, the shaded area indicated by the symbol C indicates an area near natural circulation high power that should be avoided in order to maintain the stability of the reactor core in a boiling water reactor. In order to avoid reaching the state in region C, it is necessary to
It is necessary to maintain the reactor power lower than the power on the 0% output slam flow control curve d, or to maintain the total pump speed of the recirculation pumps 6 not to fall below the minimum pump speed curve e.

そのため、第１図に示すように、原子炉出力制御装置１
０には各再循環ボンプ６からのポンプ速度信号１１を入
力し、再循環ボンプ６の速度の総和を計算する総ポンプ
速度計算装置１２が備えられる。この総ポンプ速度計算
装置１２からは総ポンプ速度信号１３が出力され、この
総ポンプ速度信号］３と再循環流量制御系１４からの総
ポンプ速度要求信号１５とが偏差演算装置１６に入力さ
れ、この偏差演算装１１１６でその偏差ΔＳが演算され
る。Therefore, as shown in FIG.
0 is provided with a total pump speed calculation device 12 that inputs pump speed signals 11 from each recirculation pump 6 and calculates the sum of the speeds of the recirculation pumps 6. The total pump speed calculation device 12 outputs a total pump speed signal 13, and the total pump speed signal 3 and the total pump speed request signal 15 from the recirculation flow rate control system 14 are input to the deviation calculation device 16. The deviation calculation unit 1116 calculates the deviation ΔS.

偏差演算装置１６からは偏差信号１７が出力され１その
偏差信号１７は比較装置１８に入力されて、予め定めた
設定値ｋより偏差ΔＳが小さいか否かが判断される。偏
差ΔＳが設定値ｋよりも大きい場合には、再循環ポンプ
６が全数トリップしたと判断し、選択制御棒挿入装置１
９へ動作信号２０を出力する。動作信号２０を入力した
選択制御棒挿入装置１９は、制御棒駆動機構７へ選択制
御棒挿入信号２１を出力し、予め定めた複数本の制御棒
８を炉心２へ挿入することにより自然循環状態での出力
を８０％出力パターン流量制御曲線ｄ上の出力よりも低
く維持する。A deviation signal 17 is outputted from the deviation calculation device 16, and the deviation signal 17 is inputted to the comparison device 18, which determines whether the deviation ΔS is smaller than a predetermined set value k. If the deviation ΔS is larger than the set value k, it is determined that all the recirculation pumps 6 have tripped, and the selective control rod insertion device 1
The operation signal 20 is output to the terminal 9. The selective control rod insertion device 19 that has received the operation signal 20 outputs a selective control rod insertion signal 21 to the control rod drive mechanism 7 and inserts a predetermined plurality of control rods 8 into the reactor core 2 to achieve a natural circulation state. The output at 80% is maintained lower than the output on the flow control curve d.

一方、比較装置１８において偏差ΔＳが設定値ｋよりも
小さい場合には、ポンプ速度ランバック等の制御信号に
よる流量の減少であると判断し、再循環ポンプ速度制限
器２２へ動作信号２３を出力する。動作信号２３を入力
した再循環ポンプ速度制限器２２は各再循環ポンプ６へ
速度制限信号２４を出力し、炉心流量の下限値が最低ポ
ンプ速度に相当する流量となるように各再循環ボンプ６
の速度を制限する。On the other hand, if the deviation ΔS is smaller than the set value k in the comparator 18, it is determined that the flow rate has decreased due to a control signal such as a pump speed runback, and an operation signal 23 is output to the recirculation pump speed limiter 22. do. The recirculation pump speed limiter 22 inputting the operation signal 23 outputs a speed limit signal 24 to each recirculation pump 6, and controls each recirculation pump 6 so that the lower limit of the core flow rate corresponds to the minimum pump speed.
limit the speed of

このように上記実施例によれば、再循環ポンプ６の実際
の総ポンプ速度と再循環流量制御系１４により要求され
る総ポンプ速度との偏差ΔＳを求め、その偏差ΔＳが予
め定めた設定値ｋより大きい場合に再循環ポンプ６全数
トリップと判断して、選択制御棒挿入により原子炉出力
を８０％出力パターン流量制御曲線ｄ以下に維持する。According to the embodiment described above, the deviation ΔS between the actual total pump speed of the recirculation pump 6 and the total pump speed required by the recirculation flow rate control system 14 is determined, and the deviation ΔS is set to a predetermined set value. If it is larger than k, it is determined that all of the recirculation pumps 6 are tripped, and the reactor output is maintained below the 80% output pattern flow rate control curve d by selective control rod insertion.

また、偏差ΔＳが設定値ｋより小さい場合には炉心流量
が最低ポンプ速度に相当する流量以下とならないように
再循環ポンプ６の速度を制限する。Further, when the deviation ΔS is smaller than the set value k, the speed of the recirculation pump 6 is limited so that the core flow rate does not become less than the flow rate corresponding to the minimum pump speed.

したがって、自然循環高出力状態に至ることが予想され
る異常過渡事象時において、自然循環出力高出力状態近
傍での運転状態となることを自動的に回避し、原子炉炉
心の安定性の安定度低下による原子炉出力の振動発生の
可能性を排除することができる。Therefore, in the event of an abnormal transient event that is expected to lead to a natural circulation high power state, the operation state near the natural circulation high power state is automatically avoided, and the stability of the reactor core is improved. It is possible to eliminate the possibility of oscillations in the reactor output due to a drop.

〔発明の効果〕〔Effect of the invention〕

本発明は、再循環ポンプの総ポンプ速度を計算して総ポ
ンプ速度信号を出力する総ポンプ速度演算装置と、総ポ
ンプ速度要求信号を出力する再循環流量制御系と、上記
総ポンプ速度信号および総ポンプ速度要求信号を入力し
てその偏差を演算する偏差演算装置と、この偏差演算装
置からの偏差信号を入力して予め定めた設定値と比較す
る比較装置と、その比較により偏差の方が大きい場合に
予め定めた複数本の制御棒を挿入することにより自然循
環状態での出力を８０％出力流量制御曲線上の出力より
も低く維持させる選択制御棒挿入装置と、上記の比較に
より偏差の方が小さい場合に炉心流量の下限値を最低ポ
ンプ速度に相当する流量に制限する再循環ポンプ速度制
限器とを具備したから、自然循環高出力近傍の状態での
運転を自動的に回避することができ、原子炉炉心の安定
性の安定度低下による原子炉出力の振動発生の可能性を
排除することができる。The present invention includes a total pump speed calculation device that calculates the total pump speed of a recirculation pump and outputs a total pump speed signal, a recirculation flow rate control system that outputs a total pump speed request signal, and the total pump speed signal and A deviation calculation device inputs the total pump speed request signal and calculates its deviation, and a comparison device inputs the deviation signal from this deviation calculation device and compares it with a predetermined set value. A selective control rod insertion device maintains the output in a natural circulation state lower than the output on the 80% output flow rate control curve by inserting a predetermined plurality of control rods when the deviation is large. Since the system is equipped with a recirculation pump speed limiter that limits the lower limit of the core flow rate to the flow rate corresponding to the minimum pump speed when the core flow rate is smaller, operation under conditions near natural circulation high output is automatically avoided. This eliminates the possibility of oscillations in the reactor output due to a decrease in the stability of the reactor core.

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

第１図は本発明に係る原子炉出力制御装置の−実施例を
示すブロック構成図、第２図は沸騰水型原子炉における
炉心流量と炉心出力との関係を示す特性図である。 １・・・原子炉圧力容器、２・・・炉心、６・・・再循
環ポンプ、７・・・制御棒駆動機構、８・・・制御棒、
１０・・・原子炉出力制御装置、１１・・・ポンプ速度
信号、１２・・・総ポンプ速度計算装置、１３・・・総
ポンプ速度信号、１４・・・再循環流量制御系、１５・
・・総ポンプ速度要求信号、１６・・・偏差演算装置、
１７・・・偏差信号、１８・・・比較装置、１９・・・
選択制御棒挿入装置、２０・・・動作信号、２１・・・
選択制御棒挿入信号、２２・・・再循環ポンプ速度制限
器、２３・・・動作信号、２４・・・速度制限信号。FIG. 1 is a block diagram showing an embodiment of the reactor power control system according to the present invention, and FIG. 2 is a characteristic diagram showing the relationship between core flow rate and core power in a boiling water reactor. DESCRIPTION OF SYMBOLS 1... Reactor pressure vessel, 2... Reactor core, 6... Recirculation pump, 7... Control rod drive mechanism, 8... Control rod,
DESCRIPTION OF SYMBOLS 10... Reactor power control device, 11... Pump speed signal, 12... Total pump speed calculation device, 13... Total pump speed signal, 14... Recirculation flow rate control system, 15.
... Total pump speed request signal, 16 ... Deviation calculation device,
17... Deviation signal, 18... Comparison device, 19...
Selective control rod insertion device, 20... operation signal, 21...
Selected control rod insertion signal, 22... Recirculation pump speed limiter, 23... Operation signal, 24... Speed limit signal.

Claims (1)

【特許請求の範囲】[Claims] 再循環ポンプの総ポンプ速度を計算して総ポンプ速度信
号を出力する総ポンプ速度演算装置と、総ポンプ速度要
求信号を出力する再循環流量制御系と、上記総ポンプ速
度信号および総ポンプ速度要求信号を入力してその偏差
を演算する偏差演算装置と、この偏差演算装置からの偏
差信号を入力して予め定めた設定値と比較する比較装置
と、その比較により偏差の方が大きい場合に予め定めた
複数本の制御棒を挿入することにより自然循環状態での
出力を８０％出力流量制御曲線上の出力よりも低く維持
させる選択制御棒挿入装置と、上記の比較により偏差の
方が小さい場合に炉心流量の下限値を最低ポンプ速度に
相当する流量に制限する再循環ポンプ速度制限器とを具
備したことを特徴とする原子炉出力制御装置。a total pump speed calculation device that calculates the total pump speed of the recirculation pump and outputs a total pump speed signal; a recirculation flow rate control system that outputs a total pump speed request signal; and a total pump speed signal and total pump speed request. A deviation calculation device inputs a signal and calculates its deviation; a comparison device inputs the deviation signal from this deviation calculation device and compares it with a predetermined set value; A selective control rod insertion device that maintains the output in a natural circulation state lower than the output on the 80% output flow rate control curve by inserting a plurality of predetermined control rods, and when the deviation is smaller based on the above comparison. and a recirculation pump speed limiter that limits a lower limit value of the reactor core flow rate to a flow rate corresponding to a minimum pump speed.
JP2010496A 1990-01-22 1990-01-22 Nuclear reactor output controller Pending JPH03215791A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2010496A JPH03215791A (en) 1990-01-22 1990-01-22 Nuclear reactor output controller

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2010496A JPH03215791A (en) 1990-01-22 1990-01-22 Nuclear reactor output controller

Publications (1)

Publication Number Publication Date
JPH03215791A true JPH03215791A (en) 1991-09-20

Family

ID=11751803

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2010496A Pending JPH03215791A (en) 1990-01-22 1990-01-22 Nuclear reactor output controller

Country Status (1)

Country Link
JP (1) JPH03215791A (en)

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