JPH09222489A - Method and device for automatic power regulation of boiling water reactor - Google Patents

Method and device for automatic power regulation of boiling water reactor

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Publication number
JPH09222489A
JPH09222489A JP8030726A JP3072696A JPH09222489A JP H09222489 A JPH09222489 A JP H09222489A JP 8030726 A JP8030726 A JP 8030726A JP 3072696 A JP3072696 A JP 3072696A JP H09222489 A JPH09222489 A JP H09222489A
Authority
JP
Japan
Prior art keywords
value
reactor
target value
rate
power
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
JP8030726A
Other languages
Japanese (ja)
Other versions
JP3316825B2 (en
Inventor
Akira Murata
昭 村田
Yoshiyuki Miyamoto
義之 宮本
Shoji Tanigawa
尚司 谷川
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP03072696A priority Critical patent/JP3316825B2/en
Publication of JPH09222489A publication Critical patent/JPH09222489A/en
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Expired - Lifetime 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
    • 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

PROBLEM TO BE SOLVED: To suppress overshoot by maintaining a target value at a constant value in the case the deviation exceeds a normal value and reelevating the target value from the constant value in the case of lower value than the normal value. SOLUTION: An operator inputs a terminal target set value and the rising rate of the target set value and a computer sets the initial value of the target set value and terminal target set value and calculates the deviation ΔP(t) of the actual reactor power at present time (t) from the target set value 1. When the deviation Δ P(t) is smaller than a reference value (a), the target set value 1 is raised and whether the target set value 1 reached the terminal target set value or not is judged. If not, the target set value 1 is raised and processing is terminated when it reaches. For suppressing overshoot, when the deviation ΔP(t) is larger than the reference value (a), the target set value 1 is maintained at 1a so that the reactor power increase during this time and the deviation ΔP(t) reduces. Then, the target set value 1 is maintained at the constant value la until the deviation ΔP(t) reduces to another reference value (b). After reducing, the target set value 1 is raised again.

Description

【発明の詳細な説明】Detailed Description of the Invention

【０００１】[0001]

【発明の属する技術分野】本発明は沸騰水型原子力発電
プラントの出力自動制御技術に係り、特に、起動時にお
ける制御棒自動操作に好適な自動出力調整方法及びその
装置に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an automatic output control technique for a boiling water nuclear power plant, and more particularly to an automatic output adjusting method and apparatus suitable for automatic control rod operation at startup.

【０００２】[0002]

【従来の技術】制御棒を自動制御する従来技術として、
特開平０１４−８３１９０号公報記載の制御棒自動制御
装置がある。この従来の制御棒自動制御装置は、運転モ
−ドの選択手段と、選択されたモ−ドにおける制御目標
値決定手段と、各モ−ドに対応する制御棒操作タイミン
グを決定する手段とを備えており、原子炉出力制御モ−
ドでは、初期時刻ｔ0の原子炉出力をＰ0とすると、原子
炉出力目標値変化率Ｐcが制限値以下となるように制御
棒が自動的に操作される。ここで、任意の時刻ｔにおけ
る制御目標値Ｐ(t)は、Ｐ(t)=Ｐ0＋Ｐc*(t-t0)として計
算され、原子炉出力制御モ−ドに対応した論理に基づく
制御棒操作タイミングにより、原子炉出力Ｐ(t)に追従
するように、目標原子炉出力と観測される原子炉出力と
の偏差により、制御棒が自動操作される。2. Description of the Related Art As a conventional technique for automatically controlling a control rod,
There is a control rod automatic control device described in JP-A-014-83190. This conventional control rod automatic control device comprises a selecting means for the operating mode, a control target value determining means for the selected mode, and a means for determining the control rod operating timing corresponding to each mode. It is equipped with a reactor power control mode.
If the reactor output at the initial time t0 is P0, the control rod is automatically operated so that the reactor output target value change rate Pc becomes equal to or less than the limit value. Here, the control target value P (t) at an arbitrary time t is calculated as P (t) = P0 + Pc * (t-t0), and the control rod operation timing is based on the logic corresponding to the reactor power control mode. Thus, the control rod is automatically operated according to the deviation between the target reactor output and the observed reactor output so as to follow the reactor output P (t).

【０００３】[0003]

【発明が解決しようとする課題】原子力発電プラントで
は、制御棒操作による原子炉への反応度投入が制御棒引
抜に対し線形の関係にはならない。つまり、制御棒位置
により、制御棒引抜量に対し投入される反応度の大きい
領域と小さい領域があり、非線形の関係となる。その原
因は、炉心中央部では中性子束分布が高く、制御棒引抜
により燃料の核***反応が進むのに比べ、炉心周辺部で
は中性子束分布が低く、制御棒引抜により燃料の核***
反応が進まないことによる。In a nuclear power plant, the reactivity injection into the reactor by operating the control rods does not have a linear relationship with the control rod withdrawal. That is, depending on the control rod position, there is a region where the reactivity is large and a region where the reactivity is small relative to the control rod withdrawal amount, and there is a non-linear relationship. The cause is that the neutron flux distribution is high in the central part of the core and the fission reaction of the fuel progresses due to the extraction of the control rod, whereas the neutron flux distribution is low in the peripheral part of the core and the fission reaction of the fuel does not proceed due to the withdrawal of the control rod. by.

【０００４】制御棒引抜・挿入シ−ケンスは、制御棒落
下事象や制御防誤引抜事象のみでなく、上記の非線形の
関係も考慮して決定されているが、それでも、制御棒引
抜時における投入反応度の非線形性を無くすことはでき
ない。この様な反応度特性を持つ制御棒を、従来技術に
より制御する場合、制御棒引抜による反応度投入の大き
い領域では目標原子炉出力と観測される原子炉出力の偏
差をある範囲に抑えることが可能であるが、反応度投入
の小さい領域では、制御棒を引き抜いても十分な反応度
が投入されず、目標原子炉出力と観測される原子炉出力
との偏差が大きくなる場合が考えられる。The control rod pull-out / insertion sequence is determined in consideration of not only the control rod drop event and the control-preventive false pull-out event but also the above-mentioned nonlinear relationship, but the control rod pull-out / insertion sequence is never closed. The reactivity non-linearity cannot be eliminated. When a control rod having such reactivity characteristics is controlled by the conventional technique, it is possible to suppress the deviation between the target reactor output and the observed reactor output within a certain range in a region where the reactivity input by pulling out the control rod is large. Although it is possible, in the region where the reactivity input is small, even if the control rod is pulled out, sufficient reactivity may not be input, and the deviation between the target reactor output and the observed reactor output may increase.

【０００５】偏差が大きくなった場合、次に、このまま
の偏差で制御棒による反応度投入の大きくなる領域に移
行して自動制御により反応度投入を行うと、その偏差に
見合った急激な反応度投入となり、目標値を大きくオ−
バ−シュ−トしてしまう虞がある。これを図示すると、
図１１に示す様に、原子炉目標設定値が最終目標設定値
となるように線形に目標設定値１を上昇させ制御棒をこ
れに従って操作しても、実際の原子炉出力２は線形には
上昇せずに両者間の偏差が大になるときがあり、この結
果、オーバーシュートが発生してしまう虞がある。この
一時的なオーバーシュートの大きさが警報発生の設定値
を越える大きさの場合には、反応度投入の行えない領域
から反応度投入の行える領域に移行する度に警報が発生
されて原子力発電プラントの異常発生と誤認されるた
め、上記のオーバーシュートをなくす必要がある。When the deviation becomes large, if the deviation is increased to the area where the reactivity input by the control rod becomes large and the reactivity is input by the automatic control, the rapid reactivity corresponding to the deviation is obtained. It is turned on and the target value is greatly increased.
There is a risk that it will burst. To illustrate this,
As shown in FIG. 11, even if the target set value 1 is linearly increased so that the reactor target set value becomes the final target set value and the control rod is operated in accordance with this, the actual reactor output 2 becomes linear. There is a case where the deviation between the two becomes large without rising, and as a result, an overshoot may occur. If the magnitude of this temporary overshoot exceeds the set value for alarm generation, an alarm is generated and nuclear power is generated each time the area where reactivity input cannot be performed changes to the area where reactivity input can be performed. It is necessary to eliminate the above overshoot because it is mistakenly recognized as a plant abnormality.

【０００６】本発明の目的は、目標原子炉出力と観測さ
れる原子炉出力との偏差が設定値より大きくなる場合に
オーバーシュートを抑制し目標原子炉出力を一定値に制
御する原子炉出力自動調整方法及びその装置を提供する
ことにある。An object of the present invention is to provide an automatic reactor power control that suppresses overshoot and controls the target reactor power to a constant value when the deviation between the target reactor power and the observed reactor power exceeds a set value. An object is to provide an adjusting method and an apparatus thereof.

【０００７】[0007]

【課題を解決するための手段】上記目的は、原子力発電
プラントの制御棒を用いた原子炉出力上昇過程で、原子
力出力の設定された最終目標値及び出力上昇率から任意
時刻での目標値を算出し該目標値と実際の測定値との偏
差に基づいて制御棒を操作する原子炉出力自動調整にお
いて、前記偏差が規定を越える値になった場合に前記目
標値を一定の値に維持し、前記偏差が規定以下の値にな
った場合に再び前記目標値を該一定の値から上昇させる
ことで、達成される。[Means for Solving the Problems] The above-mentioned object is to obtain a target value at an arbitrary time from a set final target value and a power increase rate of nuclear power in a reactor power increasing process using a control rod of a nuclear power plant. In the automatic adjustment of the reactor output in which the control rod is operated based on the deviation between the calculated target value and the actual measured value, the target value is maintained at a constant value when the deviation exceeds a specified value. This is achieved by raising the target value from the constant value again when the deviation becomes a value equal to or less than the specified value.

【０００８】上記目的は、また、原子力出力変化率が規
定値以下となった場合には目標値を一定の値に維持し、
前記変化率が規定値を越える場合には前記目標値を上昇
させることで、達成される。The above-mentioned object is to maintain the target value at a constant value when the rate of change in nuclear power output is below a specified value,
When the rate of change exceeds the specified value, it is achieved by increasing the target value.

【０００９】上記目的は、また、原子力出力変化率が第
１規定値を越える値の場合には目標値を所定変化率で上
昇させ、前記変化率が第１規定値以下となった場合で且
つ目標値と実際の原子力出力値との偏差が第２規定値を
越える場合には目標値を一定の値に維持することで、達
成される。The above object is also to increase the target value by a predetermined rate of change when the rate of change in nuclear power output exceeds the first specified value, and when the rate of change becomes less than or equal to the first specified value. When the deviation between the target value and the actual nuclear power output value exceeds the second specified value, it is achieved by maintaining the target value at a constant value.

【００１０】偏差が大きくなった場合や、原子力出力変
化率が小さくなった場合に、目標値をそのまま上昇させ
ずに一定に維持するため、偏差が大きくなりすぎること
がなくなり、過度なオーバーシュートが回避される。When the deviation becomes large or when the rate of change in nuclear power output becomes small, the target value is not increased but is kept constant, so that the deviation does not become too large and excessive overshoot occurs. Avoided.

【００１１】[0011]

【発明の実施の形態】以下、本発明の一実施形態を図面
を参照して説明する。図１は、本発明の一実施形態に係
る原子炉出力自動調整装置を適用した沸騰水型原子力発
電プラントの構成図であり、１は沸騰水型原子炉、２は
制御棒、３は制御棒駆動系、４は再循環流量制御系、５
はタービン制御系、６は本実施形態に係る原子炉出力自
動調整装置、７は制御棒引抜監視装置、８はプラント起
動・停止総括監視計算機、９は炉心監視用計算機であ
る。BEST MODE FOR CARRYING OUT THE INVENTION An embodiment of the present invention will be described below with reference to the drawings. FIG. 1 is a configuration diagram of a boiling water nuclear power plant to which an automatic reactor power adjusting device according to an embodiment of the present invention is applied, 1 is a boiling water nuclear reactor, 2 is a control rod, 3 is a control rod. Drive system, 4 is a recirculation flow rate control system, 5
Is a turbine control system, 6 is a reactor power automatic adjusting device according to the present embodiment, 7 is a control rod withdrawal monitoring device, 8 is a plant start / stop general monitoring computer, and 9 is a core monitoring computer.

【００１２】この原子力発電プラントでは、プラント起
動時の原子炉出力上昇過程において、最初に与えられた
最終目標設定値と原子炉出力変化率とから計算された原
子炉目標設定値に基づいて自動出力制御装置６から制御
棒制御信号が制御棒駆動系３に発信され、制御棒引抜シ
−ケンスによって決められている制御棒引抜順序に従い
制御棒２が引抜かれ、沸騰水型原子炉１の原子炉出力が
上昇される。In this nuclear power plant, in the process of increasing the reactor power at the time of starting the plant, the automatic output is performed based on the reactor target set value calculated from the final target set value and the reactor output change rate given first. A control rod control signal is transmitted from the control device 6 to the control rod drive system 3, the control rods 2 are withdrawn in accordance with the control rod withdrawal sequence determined by the control rod withdrawal sequence, and the reactor of the boiling water reactor 1 is extracted. The output is increased.

【００１３】図２は、図１に示す出力自動調整装置６の
詳細構成図である。この出力自動調整装置６は、目標原
子炉出力設定演算部１００と、最終目標出力到達判定部
１０１と、制御棒操作指令部１０２と、ぺリオド計算部
１０３により構成される。尚、図中の「最終目標出力設
定値」「ＡＰＲＭ」「主蒸気流量」「目標原子炉出力上
昇率」「ＳＲＮＭ」の各データは、統括監視計算機８か
ら出力自動調整装置６に与えられる。尚、図１中におい
て、自動出力調整装置６からタービン制御系５と再循環
流量制御系６へ出力される制御信号は、図２では省略し
てある。FIG. 2 is a detailed block diagram of the automatic output adjustment device 6 shown in FIG. The automatic output adjustment device 6 is composed of a target reactor power setting calculation unit 100, a final target power arrival determination unit 101, a control rod operation command unit 102, and a period calculation unit 103. Each data of “final target output set value”, “APRM”, “main steam flow rate”, “target reactor power increase rate”, and “SRNM” in the figure is given from the integrated monitoring computer 8 to the output automatic adjustment device 6. The control signals output from the automatic output adjusting device 6 to the turbine control system 5 and the recirculation flow rate control system 6 in FIG. 1 are omitted in FIG.

【００１４】目標原子炉出力設定演算部１００は、目標
出力計算部１００ａとフィルタ部１００ｂと加算器１０
０ｃとを備える。目標出力計算部１００ａは、センサ*2
からのモードスイッチ切替要求信号と、センサ*1からの
目標原子炉出力値−測定原子炉出力値間の偏差検出信号
と、センサ*3からの原子炉出力変化率検出信号とを取り
込み、オペレータが指定し統括監視計算機８から出力さ
れる最終目標（原子炉）出力設定値と出力上昇率とから
最終目標設定値までの目標原子炉出力値を演算して求め
る。The target reactor power setting calculation unit 100 includes a target power calculation unit 100a, a filter unit 100b, and an adder 10.
0c and. The target output calculation unit 100a is a sensor * 2
The mode switch switching request signal from the sensor, the deviation detection signal between the target reactor output value and the measured reactor output value from the sensor * 1, and the reactor output change rate detection signal from the sensor * 3 are captured by the operator. The target reactor output value up to the final target set value is calculated by calculating from the final target (reactor) output set value and the output increase rate that are designated and output from the integrated monitoring computer 8.

【００１５】フィルタ部１００ｂは、主蒸気流量をフィ
ルタリングして原子炉出力値を得、加算器１００ｃは、
この原子炉出力値と目標出力計算部１００ａから出力さ
れる目標原子炉出力値との偏差を求めて出力する。尚、
フィルタ部１００ｂの後段に前記センサ*3が接続され、
加算器１００ｃの出力に前記センサ*1が接続される。こ
こで、目標出力計算部１００ａは、各種センサ*1，*2，
*3からの検出信号に基づいて、制御棒の引抜により十分
な反応度投入が行えず目標出力設定値に原子炉出力が追
従できない時間領域に入ったことを検知したとき、詳細
は図３で後述するようにして、出力する目標出力設定値
を一定値に維持する。The filter unit 100b filters the main steam flow rate to obtain a reactor output value, and the adder 100c
The deviation between this reactor output value and the target reactor output value output from the target output calculation unit 100a is calculated and output. still,
The sensor * 3 is connected to the subsequent stage of the filter unit 100b,
The sensor * 1 is connected to the output of the adder 100c. Here, the target output calculation unit 100a uses various sensors * 1, * 2,
Based on the detection signal from * 3, when it is detected that the reactivity has not been sufficiently injected by pulling out the control rod and the reactor output cannot follow the target output setting value, the details are shown in Fig. 3. As will be described later, the output target output setting value is maintained at a constant value.

【００１６】最終目標出力到達判定部１０１は、統括監
視計算機からの最終目標出力設定値及びＡＰＲＭと、フ
ィルタ部１０１ｂから出力される原子炉出力値と、モー
ドスイッチ切替要求信号値とに基づいて、最終目標出力
に到達したか否かを判定し、判定結果を制御棒操作指令
部１０２に出力すると共に、図示しない信号線を介して
統括監視計算機にも出力する。The final target output arrival determination unit 101 determines, based on the final target output set value and APRM from the integrated monitoring computer, the reactor output value output from the filter unit 101b, and the mode switch switching request signal value. It is determined whether or not the final target output has been reached, and the determination result is output to the control rod operation command unit 102 and also output to the overall monitoring computer via a signal line (not shown).

【００１７】制御棒操作指令部１０２は、目標原子炉出
力設定演算部１００から出力される偏差信号と、最終目
標出力到達判定部１０１から出力される判定結果と、Ｓ
ＲＮＭ信号を受けてペリオド計算部１０３が算出したペ
リオド信号と、図１の制御棒引抜監視装置７から出力さ
れた制御棒操作情報信号とを取り込み、制御棒操作指令
を、図１の制御棒駆動制御系３に出力する。この制御棒
操作指令部１０２は、引抜／挿入許可判定部１０２ａ
と、操作モード判定部１０２ｂとを備える。The control rod operation command unit 102 outputs a deviation signal output from the target reactor power setting calculation unit 100, a determination result output from the final target output arrival determination unit 101, and S
The period signal calculated by the period calculator 103 in response to the RNM signal and the control rod operation information signal output from the control rod pull-out monitoring device 7 of FIG. 1 are taken in, and the control rod operation command is issued to the control rod drive of FIG. Output to the control system 3. The control rod operation command unit 102 is a pull-out / insertion permission determination unit 102a.
And an operation mode determination unit 102b.

【００１８】引抜／挿入許可判定部１０２ａは、前記の
各信号を取り込んで、制御棒をどの程度引き抜けばいい
のか、最終目標値に到達しているのか否か、前回の制御
棒操作完了から所定時間（例えば１５秒）経過している
か否か、ペリオドが所定時間（例えば２００秒）以下で
あるか否か、図示しないセンサからの信号に基づき原子
炉水位レベルが規定値を逸脱しているか否か、等を併せ
て判定し、制御棒の引き抜き／挿入の許可を判定する。
この判定結果に基づいて制御棒駆動制御系３が制御棒操
作を行い、最終目標値に達したか否かは、最終目標出力
到達判定部１０１が行う。以上の操作により、前述した
オーバーシュートが抑制され、適切なプラント運用が可
能になる。The pull-out / insertion permission decision unit 102a takes in the above-mentioned signals to determine how far the control rod should be pulled out, whether or not the final target value has been reached, and whether or not the control rod has been operated last time. Whether or not a predetermined time (for example, 15 seconds) has elapsed, whether or not the period is less than or equal to a predetermined time (for example, 200 seconds), and whether the reactor water level deviates from the specified value based on a signal from a sensor (not shown). Whether or not, etc. is also determined, and permission for pulling out / inserting the control rod is determined.
Based on this determination result, the control rod drive control system 3 operates the control rod, and the final target output arrival determination unit 101 determines whether or not the final target value has been reached. By the above operation, the above-mentioned overshoot is suppressed, and proper plant operation becomes possible.

【００１９】図３は、目標出力設定値を一定に維持する
制御を、原子炉出力の偏差に基づいて行う場合の判定処
理手順を示すフローチャートである。尚、図４，図５
は、目標出力設定値の一定維持と制御棒引抜により投入
される原子炉出力との関係を示すグラフである。FIG. 3 is a flow chart showing a determination processing procedure in the case where the control for maintaining the target output set value constant is performed based on the deviation of the reactor output. 4 and 5
[Fig. 4] is a graph showing the relationship between the constant maintenance of the target output set value and the reactor power input by pulling out the control rod.

【００２０】ここで、任意の時刻ｔにおける目標出力設
定値と観測される原子炉出力の偏差を △Ｐ(t)=Ｐ(t)-Ｐ'(t) として定義する。但し、Ｐ(t)は図４における任意の時
刻ｔの目標原子炉出力設定値であり、同様に、Ｐ'(t)は
図４における任意の時刻ｔにおける主蒸気流量を観測し
フィルタリングして得た実際の原子炉出力である。Here, the deviation between the target power set value and the observed reactor power at an arbitrary time t is defined as ΔP (t) = P (t) -P '(t). However, P (t) is the target reactor power setting value at any time t in FIG. 4, and similarly P ′ (t) is obtained by observing and filtering the main steam flow rate at any time t in FIG. It is the actual reactor power obtained.

【００２１】また、原子炉出力の偏差大の設定値をａと
し、この値ａを超えた偏差が生じた場合には、制御棒引
抜シ−ケンスに従った制御棒引抜による反応度投入が十
分に行えない領域と判断し、偏差が小さくなるまで目標
出力設定値を一定の値に保つ処理を行う。偏差小の設定
値をｂとし、この値ｂより小さな原子炉出力偏差になっ
た場合には、制御棒引抜シ−ケンスに従い引抜かれる制
御棒により十分目標設定値に追従できる原子炉出力を得
る反応度投入が可能な領域と判断し、目標設定値を一定
の値からもとの目標設定値に設定し直す処理を行う。Further, if the deviation of the reactor power deviation is set to a, and a deviation exceeding this value a occurs, it is sufficient to add the reactivity by pulling out the control rod according to the control rod pulling sequence. The target output set value is maintained at a constant value until the deviation becomes small. If the set value with a small deviation is b, and the reactor output deviation is smaller than this value b, a reaction to obtain a reactor output that can sufficiently follow the target set value by the control rod withdrawn according to the control rod pullout sequence. It is determined that the target setting value can be input once, and the target setting value is reset from the fixed value to the original target setting value.

【００２２】図３のステップ１で、先ず、最終目標設定
値と、目標設定値の上昇率とをオペレータが入力する
（ステップ１）。図４に最終目標設定値を破線で示す。
上昇率は、目標設定値１を示す直線の傾きに相当する。
このステップ１で入力がなされると、次のステップ２に
て、計算機が目標設定値の初期値と最終目標設定値とを
設定する。ステップ３では、図４に示す目標設定値１と
実際の原子炉出力値との現時点ｔにおける偏差ΔＰ(t)
が算出される。図４に示す様に、制御棒引き抜きの最初
の段階では制御棒引抜シーケンスに従って制御棒を引き
抜いても、それに伴い十分な反応度が得られるため、こ
の偏差ΔＰ(t)は大きくならない。そこで、ステップ４
では偏差ΔＰ(t)が値ａより大きいか否かが判定され、
偏差ΔＰ(t)が小さい場合にはステップ５に進んで目標
設定値１を前記上昇率に従って更新（上昇）させ、次の
ステップ６で、目標設定値１が最終目標設定値に達した
か否かが判定される。最終目標設定値に達していない場
合にはステップ４に戻り、最終目標設定値に達している
場合には本処理を終了する。これにより、基本的には、
目標設定値１は、初期値から最終目標設定値まで徐々に
上昇される。In step 1 of FIG. 3, the operator first inputs the final target set value and the rate of increase of the target set value (step 1). The final target set value is shown by a broken line in FIG.
The rate of increase corresponds to the slope of the straight line indicating the target set value 1.
When the input is made in step 1, the computer sets the initial target setting value and the final target setting value in the next step 2. In step 3, the deviation ΔP (t) between the target set value 1 shown in FIG. 4 and the actual reactor output value at the present time t
Is calculated. As shown in FIG. 4, in the first stage of pulling out the control rod, even if the control rod is pulled out in accordance with the control rod pulling-out sequence, a sufficient reactivity can be obtained accordingly, so that this deviation ΔP (t) does not become large. Therefore, step 4
Then, it is determined whether the deviation ΔP (t) is larger than the value a,
When the deviation ΔP (t) is small, the routine proceeds to step 5, where the target set value 1 is updated (increased) according to the increase rate, and at the next step 6, whether or not the target set value 1 has reached the final target set value. Is determined. If the final target set value has not been reached, the process returns to step 4, and if the final target set value has been reached, this processing ends. With this, basically,
The target set value 1 is gradually increased from the initial value to the final target set value.

【００２３】しかし前述した様に、実際の原子炉出力が
線形に上昇しない領域が存在する。この場合には、偏差
ΔＰ(t)が増大する。このまま制御を継続すると偏差Δ
Ｐ(t)が更に増大し、この増大した偏差を０にすべく制
御が進行すると前述した大きなオーバーシュートが発生
してしまう。そこで、本実施形態では、図３のステップ
４で偏差ΔＰ(t)が値ａより大きいか否かを判定し、こ
の偏差が値ａより大きい場合には、ステップ７に進み、
目標設定値１を一定値に保持する。即ち、図５に符号１
ａで示す様に、目標設定値１を一定値とする。これによ
り、前記偏差ΔＰ(t)は増大しなくなる。目標設定値１
ａが一定に保持されている期間に実際の原子炉出力は増
大するため、前記偏差ΔＰ(t)は減少する。そこで、ス
テップ８で偏差ΔＰ(t)が値ｂより小さいか否かを判定
し、偏差ΔＰ(t)が値ｂにまで小さくならない期間は目
標設定値１ａを一定に保持すべくステップ７に戻る。偏
差ΔＰ(t)が値ｂより小さくなった場合には前記ステッ
プ５に進み、再び、前記上昇率で目標設定値１ｂを更新
する。However, as described above, there is a region where the actual reactor power does not rise linearly. In this case, the deviation ΔP (t) increases. If control is continued as it is, deviation Δ
If P (t) further increases and the control proceeds so as to reduce the increased deviation to 0, the above-mentioned large overshoot will occur. Therefore, in the present embodiment, it is determined in step 4 of FIG. 3 whether the deviation ΔP (t) is larger than the value a. If the deviation is larger than the value a, the process proceeds to step 7,
The target set value 1 is maintained at a constant value. That is, reference numeral 1 in FIG.
As indicated by a, the target set value 1 is a constant value. As a result, the deviation ΔP (t) does not increase. Target set value 1
Since the actual reactor power increases while a is kept constant, the deviation ΔP (t) decreases. Therefore, in step 8, it is determined whether the deviation ΔP (t) is smaller than the value b, and the process returns to step 7 to keep the target set value 1a constant during the period when the deviation ΔP (t) does not decrease to the value b. . When the deviation ΔP (t) becomes smaller than the value b, the process proceeds to step 5 and the target set value 1b is updated again with the increase rate.

【００２４】図６は、本発明の第２実施形態に係る自動
出力調整装置の処理手順を示すフローチャートである。
本実施形態では、原子炉出力の目標設定値との偏差の他
に、原子炉出力変化率を加味して制御を行う。FIG. 6 is a flow chart showing the processing procedure of the automatic output adjusting apparatus according to the second embodiment of the present invention.
In the present embodiment, the control is performed in consideration of the reactor output change rate in addition to the deviation from the target set value of the reactor output.

【００２５】まず、ステップ１１で、最終目標設定値
と、目標設定値の上昇率とをオペレータが入力する。次
のステップ１２にて、目標値設定値の初期値と最終目標
値とが設定され、図７に示す様に、そのときの偏差ΔＰ
(t)と原子炉出力変化率dＰ／dtが算出される（ステップ
１３）。First, in step 11, the operator inputs the final target set value and the rate of increase of the target set value. In the next step 12, the initial value and the final target value of the target value setting value are set, and as shown in FIG. 7, the deviation ΔP at that time is set.
(t) and the reactor power change rate dP / dt are calculated (step 13).

【００２６】本実施形態では、次のステップ１４で、変
化率dＰ／dtが設定値ｃより大きいか否かが判定され、
大きい場合には、ステップ１５に進み、目標設定値を上
記上昇率で更新する。そして、ステップ１６で目標設定
値が最終目標値に達したか否かを判定し、達した場合に
は処理を終了し、達していない場合にはステップ１４に
戻る。即ち、本実施形態では、変化率dＰ／dtが設定値
ｃより大きい場合には、偏差の大きさに関わらず、常に
制御棒引抜による反応度投入が十分にあると判断して、
制御棒引き抜きを継続する。In the present embodiment, it is determined in the next step 14 whether the rate of change dP / dt is larger than the set value c,
If it is larger, the process proceeds to step 15 and the target set value is updated with the rate of increase. Then, in step 16, it is determined whether or not the target set value has reached the final target value. If the target set value has reached the final target value, the process is terminated, and if not reached, the process returns to step 14. That is, in the present embodiment, when the rate of change dP / dt is larger than the set value c, it is always judged that the reactivity injection by pulling out the control rod is sufficient regardless of the magnitude of the deviation,
Continue withdrawing control rod.

【００２７】原子炉出力変化率dＰ／dtが小さくなって
ステップ１４での判定が「否定」となった場合には、ス
テップ１８に進み、偏差Ｐ(t)が設定値ａより大きいか
否かを判定する。この判定結果がＰ(t)＞ａの場合には
ステップ１９に進み、目標設定値を一定に保持し、ステ
ップ１４に戻る。これは、図８の時点t1において、目標
設定値を一定にすることに該当する。When the reactor power change rate dP / dt becomes small and the determination in step 14 is "negative", the routine proceeds to step 18, where it is determined whether the deviation P (t) is larger than the set value a or not. To judge. If the determination result is P (t)> a, the process proceeds to step 19, the target set value is held constant, and the process returns to step 14. This corresponds to making the target set value constant at time t1 in FIG.

【００２８】制御が進み、ステップ１８での判定結果が
「否定」とったときは次のステップ２０で偏差Ｐ(t)が
設定値ｂより大きいか否かを判定する。偏差が設定値ｂ
よりも小さくなった場合には、再び目標設定値を更新す
べくステップ１５に戻る。ステップ２０での判定結果が
否定となった場合には、すなわち、変化率dＰ／dtが設
定値よりも小さく、且つ、偏差がａとｂの間にある場合
には、ステップ２１に進み、目標設定値を変更せずに
（つまり、目標設定値を「更新」しているときは「更
新」を続け、目標設定値が「一定」に保持されていると
きは「一定」を保持する。）ステップ１４に戻る。When the control advances and the judgment result in step 18 is "No", it is judged in next step 20 whether the deviation P (t) is larger than the set value b. Deviation is the set value b
If it becomes smaller than the above, the process returns to step 15 to update the target set value again. If the determination result in step 20 is negative, that is, if the rate of change dP / dt is smaller than the set value and the deviation is between a and b, the process proceeds to step 21 and the target Without changing the set value (that is, "update" is continued when the target set value is "updated", and "constant" is held when the target set value is held "constant"). Return to step 14.

【００２９】このように、原子炉出力変化率を考慮し、
原子炉出力偏差が大きくても変化率が大きい場合には制
御棒引き抜きシ−ケンスに従って引抜かれる制御棒によ
る反応度投入が大きいと判断して、原子炉出力偏差が大
きくても目標設定値を一定にはせず、逆に、原子炉出力
偏差が小さくても変化率が小さければ制御棒引抜による
反応度投入が十分ではないと判断して、目標設定値を一
定の場合はそれを継続する。原子炉出力偏差と変化率の
組合せによる判断を行うことで、より一層、目標設定値
に対する原子炉出力の追従性を高めることが可能とな
る。また、これまでの自動制御で問題となっていたオ−
バ−シュ−トが抑制され、かつ最終目標設定値に到達す
る時間も短縮できるという利点がある。Thus, considering the reactor power change rate,
If the rate of change is large even if the reactor output deviation is large, it is judged that the reactivity input by the control rods drawn out according to the control rod drawing sequence is large, and the target set value is kept constant even if the reactor output deviation is large. Conversely, if the rate of change is small even if the reactor output deviation is small, it is determined that the reactivity input by pulling out the control rod is not sufficient, and if the target set value is constant, it is continued. By performing the determination based on the combination of the reactor output deviation and the rate of change, it becomes possible to further improve the followability of the reactor output with respect to the target set value. In addition, the automatic control that has been a problem until now
There is an advantage that the burst rate is suppressed and the time to reach the final target set value can be shortened.

【００３０】尚、図５，図８で説明した実施形態では、
途中で目標設定値を一定に保持する関係で、最終目標設
定値に到達する時間が長くなったが、図９に例示するよ
うに、目標設定値を一定１ａに保持した後に再び目標設
定値を更新するときの上昇率Ａ，Ｂを大きくすること
で、最終目標設定に到達する時間を、初期値に対して設
定した時間と同じにできることはいうまでもない。In the embodiment described with reference to FIGS. 5 and 8,
Since the target set value is kept constant on the way, the time to reach the final target set value is long, but as illustrated in FIG. 9, the target set value is held at the constant 1a and then again set to the target set value. It goes without saying that the time to reach the final target setting can be made the same as the time set to the initial value by increasing the rate of increase A and B at the time of updating.

【００３１】図１０に、本発明実施形態を適用したとき
のシミュレーション結果を示す。同図（ａ）は、従来の
様に制御したときのオーバーシュートの計算結果であ
り、同図（ｂ）が、本実施形態を適用したときの炉出力
の計算結果である。このように、本実施形態によれば、
警報器が作動してしまうようなオーバーシュートが回避
できることが分かる。FIG. 10 shows a simulation result when the embodiment of the present invention is applied. The figure (a) is the calculation result of the overshoot at the time of control like the conventional, and the figure (b) is the calculation result of the furnace output when this embodiment is applied. Thus, according to the present embodiment,
It can be seen that the overshoot that would activate the alarm can be avoided.

【００３２】[0032]

【発明の効果】本発明によれば、最終目標原子炉出力設
定値と原子炉出力の偏差を小さく抑えることができ、そ
の結果、原子炉出力自動制御時のオ−バ−シュ−トを抑
え、不要な警報発生を回避でき、適切なプラントの運用
が行える。According to the present invention, the deviation between the final target reactor power set value and the reactor power can be suppressed to be small, and as a result, the overshoot during the reactor power automatic control can be suppressed. It is possible to avoid unnecessary alarms and operate the plant appropriately.

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

【図１】本発明の一実施形態に係る原子炉出力自動調整
装置を適用する原子力プラントの制御構成図である。FIG. 1 is a control configuration diagram of a nuclear power plant to which a reactor power automatic adjusting apparatus according to an embodiment of the present invention is applied.

【図２】図１に示す原子炉出力自動調整装置の詳細構成
図である。FIG. 2 is a detailed configuration diagram of the reactor power automatic adjusting apparatus shown in FIG.

【図３】図１に示す原子炉出力自動調整装置の一実施形
態に係る処理手順を示すフローチャートである。3 is a flowchart showing a processing procedure according to an embodiment of the reactor power automatic adjusting apparatus shown in FIG.

【図４】図３での処理手順による制御を説明する図であ
る。FIG. 4 is a diagram illustrating control according to the processing procedure in FIG.

【図５】図３での処理手順による制御を説明する図であ
る。5 is a diagram illustrating control according to the processing procedure in FIG.

【図６】図１に示す原子炉出力自動調整装置の他の実施
形態に係る処理手順を示すフローチャートである。6 is a flowchart showing a processing procedure according to another embodiment of the automatic reactor power adjusting apparatus shown in FIG.

【図７】図６での処理手順による制御を説明する図であ
る。FIG. 7 is a diagram illustrating control according to the processing procedure in FIG.

【図８】図６での処理手順による制御を説明する図であ
る。8 is a diagram illustrating control according to the processing procedure in FIG.

【図９】図１に示す原子炉出力自動調整装置の更に別の
実施形態に係る制御を説明する図である。FIG. 9 is a diagram illustrating control according to still another embodiment of the automatic reactor power adjusting apparatus shown in FIG. 1.

【図１０】従来方式による制御と本実施形態を適用した
ときの制御による原子炉出力出力のシミュレーション結
果を示す図である。FIG. 10 is a diagram showing a simulation result of reactor power output by control according to the conventional method and control when the present embodiment is applied.

【図１１】従来の自動出力制御時の原子炉出力と目標出
力設定値の関係を示す図である。FIG. 11 is a diagram showing a relationship between a reactor output and a target output set value during conventional automatic power control.

【符号の説明】[Explanation of symbols]

１…沸騰水型原子炉、２…制御棒、３…制御棒駆動系、
４再循環流量制御系、５…タ−ビン制御系、６…自動出
力調整装置、７…制御棒引抜監視装置、８…プラント起
動監視総括装置、９…炉心監視用計算機システム、１０
０目標出力計算値…１０１最終目標出力判定値、１０２
…制御棒操作指令部、１０３…ぺリオド計算部。1 ... Boiling water reactor, 2 ... Control rod, 3 ... Control rod drive system,
4 Recirculation flow rate control system, 5 ... Turbine control system, 6 ... Automatic power adjusting device, 7 ... Control rod withdrawal monitoring device, 8 ... Plant start monitoring general device, 9 ... Core monitoring computer system, 10
0 target output calculation value ... 101 final target output determination value, 102
... control rod operation command unit, 103 ... period calculation unit.

Claims (10)

【特許請求の範囲】[Claims] 【請求項１】 原子力発電プラントの制御棒を用いた原
子炉出力上昇過程で、原子力出力の設定された最終目標
値及び出力上昇率から任意時刻での目標値を算出し該目
標値と実際の測定値との偏差に基づいて制御棒を操作す
る原子炉出力自動調整方法において、前記偏差が規定を
越える値になった場合に前記目標値を一定の値に維持
し、前記偏差が規定以下の値になった場合に再び前記目
標値を該一定の値から上昇させることを特徴とする沸騰
水型原子炉の原子炉出力自動調整方法。1. A target value at an arbitrary time is calculated from the final target value and the power increase rate of the nuclear power output in the process of increasing the reactor power using a control rod of a nuclear power plant, and the target value and the actual value are calculated. In a reactor power automatic adjustment method for operating a control rod based on a deviation from a measured value, the target value is maintained at a constant value when the deviation exceeds a specified value, and the deviation is below a specified value. A method for automatically adjusting the reactor power of a boiling water reactor, wherein the target value is again raised from the constant value when the value becomes a value. 【請求項２】 原子力発電プラントの制御棒を用いた原
子炉出力上昇過程で、原子力出力の設定された最終目標
値及び出力上昇率から任意時刻での目標値を算出し該目
標値と実際の原子炉出力の変化率とに基づいて制御棒を
操作する原子炉出力自動調整方法において、前記変化率
が規定値以下となった場合には前記目標値を一定の値に
維持し、前記変化率が規定値を越える場合には前記目標
値を上昇させることを特徴とする沸騰水型原子炉の原子
炉出力自動調整方法。2. A target value at an arbitrary time is calculated from the final target value and the power increase rate of the nuclear power output in the process of increasing the reactor power using the control rod of the nuclear power plant, and the target value and the actual value are calculated. In the reactor power automatic adjustment method of operating the control rod based on the rate of change of the reactor power, when the rate of change becomes a specified value or less, the target value is maintained at a constant value, the rate of change. When the value exceeds the specified value, the target value is increased, and a method for automatically adjusting the reactor power of a boiling water reactor is provided. 【請求項３】 原子力発電プラントの制御棒を用いた原
子炉出力上昇過程で、原子力出力の設定された最終目標
値及び出力上昇率から任意時刻での目標値を算出し該目
標値と実際の測定値との偏差および実際の原子炉出力の
変化率に基づいて制御棒を操作する原子炉出力自動調整
方法において、前記変化率が第１規定値を越える値の場
合には前記目標値を所定変化率で上昇させ、前記変化率
が第１規定値以下となった場合で且つ前記偏差が第２規
定値を越える場合には前記目標値を一定の値に維持する
ことを特徴とする沸騰水型原子炉の原子炉出力自動調整
方法。3. A target value at an arbitrary time is calculated from the final target value and the power increase rate of the nuclear power output in the process of increasing the reactor power using the control rod of the nuclear power plant, and the target value and the actual value are calculated. In a reactor power automatic adjustment method for operating a control rod based on a deviation from a measured value and an actual rate of change of reactor power, when the rate of change exceeds a first prescribed value, the target value is set to a predetermined value. The boiling water is increased at a rate of change, and the target value is maintained at a constant value when the rate of change is equal to or less than a first specified value and the deviation exceeds a second specified value. Method for automatic adjustment of reactor power in a nuclear reactor. 【請求項４】 請求項１乃至請求項３のいずれかにおい
て、前記一定の値に維持した後に再び前記目標値を上昇
させる場合に、該上昇率を一定とすることを特徴とする
沸騰水型原子炉の原子炉出力自動調整方法。4. The boiling water type according to claim 1, wherein when the target value is increased again after being maintained at the constant value, the rate of increase is constant. Reactor power automatic adjustment method of reactor. 【請求項５】 請求項１乃至請求項３のいずれかにおい
て、前記一定の値に維持した後に再び前記目標値を上昇
させる場合に、該上昇率を変更することを特徴とする沸
騰水型原子炉の原子炉出力自動調整方法。5. The boiling water atom according to claim 1, wherein when the target value is increased again after being maintained at the constant value, the increase rate is changed. Reactor power automatic adjustment method of reactor. 【請求項６】 原子力発電プラントの制御棒を用いた原
子炉出力上昇過程で、原子力出力の設定された最終目標
値及び出力上昇率から任意時刻での目標値を算出し該目
標値と実際の測定値との偏差に基づいて制御棒を操作す
る信号を生成し制御棒駆動制御装置に出力する原子炉出
力自動調整装置において、前記偏差が規定を越える値に
なった場合に前記目標値を一定の値に維持する手段と、
前記偏差が規定以下の値になった場合に再び前記目標値
を該一定の値から上昇させる手段とを備えることを特徴
とする沸騰水型原子炉の原子炉出力自動調整装置。6. A target value at an arbitrary time is calculated from the final target value and the power increase rate of the nuclear power output in the process of increasing the reactor power using a control rod of a nuclear power plant, and the target value and the actual value are calculated. In a reactor power automatic adjustment device that generates a signal for operating the control rod based on the deviation from the measured value and outputs it to the control rod drive control device, the target value is kept constant when the deviation exceeds a specified value. Means to maintain the value of
A means for automatically adjusting the target value from the constant value when the deviation becomes a value equal to or less than a prescribed value, the reactor power automatic adjusting apparatus for a boiling water reactor. 【請求項７】 原子力発電プラントの制御棒を用いた原
子炉出力上昇過程で、原子力出力の設定された最終目標
値及び出力上昇率から任意時刻での目標値を算出し該目
標値と実際の原子炉出力の変化率とに基づいて制御棒を
操作する信号を生成し制御棒駆動制御装置に出力する原
子炉出力自動調整装置において、前記変化率が規定値以
下となった場合には前記目標値を一定の値に維持する手
段と、前記変化率が規定値を越える場合には前記目標値
を上昇させる手段とを備えることを特徴とする沸騰水型
原子炉の原子炉出力自動調整装置。7. A target value at an arbitrary time is calculated from the final target value and the power increase rate of the nuclear power output in the process of increasing the reactor power using a control rod of a nuclear power plant, and the target value and the actual value are calculated. In the reactor power automatic adjusting device that generates a signal for operating the control rod based on the rate of change of the reactor power and outputs it to the control rod drive control device, if the rate of change becomes less than or equal to a specified value, the target An apparatus for automatically adjusting the reactor power of a boiling water reactor, comprising: means for maintaining the value at a constant value; and means for increasing the target value when the rate of change exceeds a specified value. 【請求項８】 原子力発電プラントの制御棒を用いた原
子炉出力上昇過程で、原子力出力の設定された最終目標
値及び出力上昇率から任意時刻での目標値を算出し該目
標値と実際の測定値との偏差および実際の原子炉出力の
変化率に基づいて制御棒を操作する信号を生成し制御棒
駆動制御装置に出力する原子炉出力自動調整装置におい
て、前記変化率が第１規定値を越える値の場合には前記
目標値を所定変化率で上昇させる手段と、前記変化率が
第１規定値以下となった場合で且つ前記偏差が第２規定
値を越える場合には前記目標値を一定の値に維持する手
段とを備えることを特徴とする沸騰水型原子炉の原子炉
出力自動調整装置。8. A target value at an arbitrary time is calculated from the final target value and the power increase rate of the nuclear power output in the process of increasing the reactor power using the control rod of the nuclear power plant, and the target value and the actual value are calculated. In the reactor power automatic adjusting apparatus that generates a signal for operating the control rod based on the deviation from the measured value and the actual rate of change of the reactor output and outputs the signal to the control rod drive control unit, the rate of change is the first specified value. Means for increasing the target value at a predetermined rate of change, and a target value when the rate of change is less than or equal to a first specified value and the deviation exceeds a second specified value. And a means for maintaining the temperature at a constant value, the apparatus for automatically adjusting the reactor power of a boiling water reactor. 【請求項９】 請求項６乃至請求項８のいずれかにおい
て、前記一定の値に維持した後に再び前記目標値を上昇
させる場合に、該上昇率を一定とすることを特徴とする
沸騰水型原子炉の原子炉出力自動調整装置。9. The boiling water type according to claim 6, wherein when the target value is increased again after being maintained at the constant value, the rate of increase is constant. Automatic reactor power control system for nuclear reactors. 【請求項１０】 請求項６乃至請求項８のいずれかにお
いて、前記一定の値に維持した後に再び前記目標値を上
昇させる場合に、該上昇率を変更することを特徴とする
沸騰水型原子炉の原子炉出力自動調整装置。10. The boiling water atom according to claim 6, wherein when the target value is increased again after being maintained at the constant value, the increase rate is changed. Automatic reactor power control system for reactors.
JP03072696A 1996-02-19 1996-02-19 Automatic reactor power adjustment system for boiling water reactor Expired - Lifetime JP3316825B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP03072696A JP3316825B2 (en) 1996-02-19 1996-02-19 Automatic reactor power adjustment system for boiling water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP03072696A JP3316825B2 (en) 1996-02-19 1996-02-19 Automatic reactor power adjustment system for boiling water reactor

Publications (2)

Publication Number Publication Date
JPH09222489A true JPH09222489A (en) 1997-08-26
JP3316825B2 JP3316825B2 (en) 2002-08-19

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ID=12311671

Family Applications (1)

Application Number Title Priority Date Filing Date
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Country Status (1)

Country Link
JP (1) JP3316825B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102177321A (en) * 2008-12-11 2011-09-07 丰田自动车株式会社 Supercharger control device for internal combustion engine
KR101234549B1 (en) * 2011-08-11 2013-02-19 한국원자력연구원 Power control method and system for nuclear reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102177321A (en) * 2008-12-11 2011-09-07 丰田自动车株式会社 Supercharger control device for internal combustion engine
JP5018975B2 (en) * 2008-12-11 2012-09-05 トヨタ自動車株式会社 Supercharger control device for internal combustion engine
US8813493B2 (en) 2008-12-11 2014-08-26 Toyota Jidosha Kabushiki Kaisha Supercharger control device for an internal combustion engine
KR101234549B1 (en) * 2011-08-11 2013-02-19 한국원자력연구원 Power control method and system for nuclear reactor

Also Published As

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JP3316825B2 (en) 2002-08-19

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