JP2627524B2 - Water supply control device for nuclear power plant - Google Patents
Water supply control device for nuclear power plantInfo
- Publication number
- JP2627524B2 JP2627524B2 JP63021670A JP2167088A JP2627524B2 JP 2627524 B2 JP2627524 B2 JP 2627524B2 JP 63021670 A JP63021670 A JP 63021670A JP 2167088 A JP2167088 A JP 2167088A JP 2627524 B2 JP2627524 B2 JP 2627524B2
- Authority
- JP
- Japan
- Prior art keywords
- conversion
- reactor
- water supply
- supply control
- water level
- 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.)
- Expired - Lifetime
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Classifications
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- 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
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、原子力発電プラントの給水制御装置に係
り、特に給水制御部の制御性能の向上に有効である給水
制御装置に関する。Description: TECHNICAL FIELD The present invention relates to a water supply control device for a nuclear power plant, and more particularly to a water supply control device that is effective for improving the control performance of a water supply control unit.
原子力発電プラントは、原子炉と、この原子炉で発生
させた蒸気が導入されて駆動するタービンおよび発電機
と、ここを出た蒸気を凝縮させる復水器と、この復水器
内の水を前記原子炉に返送して給水する給水ポンプを基
本構成要素とする。原子炉への給水ラインには、給水調
節弁が設けられている。この給水調節弁は、給水量制御
部から出力される開度要求信号により制御される。給水
量制御部は、例えば原子炉への給水流量と原子炉からタ
ービンへ導入される主蒸気流量の差であるミスマッチ量
を水位換算器によって水位相当信号に換算し、この信号
を原子炉の水位計からの出力信号と加算器で加算し、そ
の結果値と原子炉水位設定値との差をP/I（比例積分演
算回路）に入力し、このP/Iから開度要求信号を前記給
水調節弁に出力する。ここで、水位換算器は、ゲインと
して一定の換算定数または換算関数が設定されている
（特開昭55−29719号公報等）。The nuclear power plant consists of a reactor, a turbine and a generator driven by the steam generated by the reactor, and a condenser for condensing the steam that has exited the reactor, and water in the condenser. A water supply pump for returning water to the reactor is supplied as a basic component. The water supply line to the reactor is provided with a water supply control valve. The water supply control valve is controlled by an opening request signal output from the water supply amount control unit. The water supply amount control unit converts the mismatch amount, which is the difference between the flow rate of the water supply to the reactor and the flow rate of the main steam introduced from the reactor to the turbine, into a water level equivalent signal by a water level converter, and converts this signal to the water level of the reactor. The output signal from the meter and the adder are added, and the difference between the result value and the reactor water level setting value is input to a P / I (proportional and integral operation circuit), and the opening request signal is supplied from the P / I to the water supply. Output to control valve. Here, in the water level converter, a constant conversion constant or conversion function is set as a gain (Japanese Patent Laid-Open No. 55-29719).
上記従来技術における給水制御装置は、水位換算器が
定格運転時に最適となるように一つのゲインを設定して
いたことから、過度時や負荷遮断となる事故時のような
負荷急変時には必ずしも最適なゲインとなっておらず、
制御性能が低下してしまうという問題があった。The water supply control device in the prior art described above has one gain set so that the water level converter is optimal at the time of rated operation. It is not gain,
There is a problem that control performance is reduced.
本発明の目的は、給水制御系のゲインを常に最適な値
に設定することのできる原子力発電プラントの給水制御
装置を提供することにある。An object of the present invention is to provide a water supply control device for a nuclear power plant that can always set the gain of the water supply control system to an optimum value.
本発明は、原子炉への給水量を制御する給水制御部を
備え、この給水制御部は原子炉内の水位変動に関係する
物理量を他の物理量に換算する換算部を有し、この換算
を経て前記給水量が定まる原子力発電プラントの給水制
御装置において、前記換算部の換算定数または換算関数
を換算量を異ならせて複数設け、原子炉内に出力分布変
化の検出器を設け、原子力発電プラントの負荷急変前後
の前記検出器からの出力信号により他の換算定数または
換算関数に切り替え可能に形成したものである。The present invention includes a water supply control unit that controls the amount of water supplied to the reactor, and the water supply control unit includes a conversion unit that converts a physical quantity related to water level fluctuation in the reactor into another physical quantity. In the water supply control device for a nuclear power plant in which the amount of water supply is determined via the reactor, a plurality of conversion constants or conversion functions of the conversion unit are provided with different conversion amounts, and a detector of a power distribution change is provided in the nuclear reactor, The conversion signal can be switched to another conversion constant or another conversion function by the output signal from the detector before and after the sudden change in the load.
すなわち、ゲインを複数個用意して、プラントの運転
状態により切り替えるものである。That is, a plurality of gains are prepared and switched according to the operation state of the plant.
プラントが定格運転にあるときは、それに対応するゲ
イン、すなわち換算定数または換算関数によって給水制
御部か動作し、負荷急変時には、その前後における原子
炉内の出力分布変化を検出し、例えば負荷遮断直後の前
記出力分布が異なる場合には検出器から、それに対応し
た出力信号が出てこの状態に対応する他のゲインに切り
替えて給水制御部が動作し、過渡時や事故時であっても
制御性能の低下を招くことがない。すなわち、原子炉内
の出力分布変化に依存し、変動幅が大きくなる負荷遮断
時の原子炉水位変動に対し、最適なゲインを設定するこ
とができる。When the plant is in rated operation, the feedwater control unit operates according to the gain corresponding to it, that is, the conversion constant or conversion function, and when the load changes suddenly, the change in the power distribution in the reactor before and after that is detected, for example, immediately after the load is cut off. If the output distribution is different, the detector outputs an output signal corresponding to the output distribution, switches to another gain corresponding to this state, operates the water supply control unit, and performs control performance even during a transient or accident. Is not caused. That is, an optimum gain can be set for the reactor water level fluctuation at the time of load shedding, which depends on the power distribution change in the reactor and the fluctuation width becomes large.
以下、本発明の一実施例を第１図により説明する。 Hereinafter, an embodiment of the present invention will be described with reference to FIG.
第１図は、沸騰水型原子力発電プラントの給水制御装
置へ本発明を適用した例である。沸騰水型原子力発電プ
ラントは、原子炉１で発生した蒸気を主蒸気配管８を介
してタービン３へ運び、発電機２を回わすことにより発
電を行うものである。このとき、原子炉１内の冷却水は
蒸気となって炉外に運び出されることから、原子炉１内
の冷却水を確保するために、発電機２を回わした後の冷
却水を復水器４から復水ポンプ５、給水ポンプ６を介し
て原子炉１内に補給している。FIG. 1 shows an example in which the present invention is applied to a water supply control device of a boiling water nuclear power plant. The boiling water nuclear power plant carries steam generated in the nuclear reactor 1 to the turbine 3 via the main steam pipe 8 and turns the generator 2 to generate power. At this time, since the cooling water in the reactor 1 is vaporized and carried out of the reactor, the cooling water after turning the generator 2 is condensed to secure the cooling water in the reactor 1. The reactor 4 is supplied to the reactor 1 via a condensate pump 5 and a feed water pump 6.
このとき、原子炉１内の水位は、原子炉の安全性を確
保し、プラントの運転を安定に継続するために、ある一
定の範囲に制御する必要がある。給水制御部100は、こ
の機能を担うために設けられており、給水ポンプ６の出
口側に配置されている給水調節弁９の開度を、その出力
信号によって制御することにより、給水流量を制御し、
最終的に原子炉１の水位の制御を行っている。At this time, the water level in the reactor 1 needs to be controlled within a certain range in order to secure the safety of the reactor and keep the plant operation stable. The water supply control unit 100 is provided to perform this function, and controls the flow rate of the water supply by controlling the opening degree of the water supply control valve 9 disposed on the outlet side of the water supply pump 6 by using an output signal thereof. And
Finally, the water level of the reactor 1 is controlled.
給水調節弁９の開度要求信号21は、基本的に原子炉水
位計11により測定した実水位22と原子炉水位設定値60と
の差23を加算器24で求め、その信号をP/I20のゲインに
より処理することにより算出するものである。しかしな
がら、実際には原子炉水位をより安定に制御するため
に、給水流量計10と主蒸気流量計12で測定した給水流量
と主蒸気流量のミスマッチ量32を、換算部である水位換
算計で水位に換算して、この換算後の信号26を加算器25
によって前記実水位22に加えることにより、原子炉水位
の変動を先行的に制御している。An opening request signal 21 of the water supply control valve 9 is basically obtained by an adder 24 as a difference 23 between an actual water level 22 measured by the reactor water level gauge 11 and a reactor water level set value 60, and the signal is calculated by the P / I 20 This is calculated by processing with the gain of. However, in practice, in order to control the reactor water level more stably, the mismatch 32 between the feed water flow rate and the main steam flow rate measured by the feed water flow meter 10 and the main steam flow meter 12 is calculated by a water level converter as a conversion unit. Converted to water level, the converted signal 26 is added to adder 25
By adding to the actual water level 22, the fluctuation of the reactor water level is controlled in advance.
ミスマッチ量32を水位相当信号26に換算する方法は、
ある一定のゲインを水位換算機によりミスマッチ量32に
掛け合わせることにより行われる。The method of converting the mismatch amount 32 into the water level equivalent signal 26 is as follows.
This is performed by multiplying the mismatch amount 32 by a certain gain using a water level converter.
従来方式では、このゲインは１種類しか用意されてお
らず、最も一般的な運転状態である定格運転時に最適に
なるような換算定数が設定されていた。したがって、負
荷急変時のゲインとしては必ずしも最適な値にはなって
おらず、制御性能が低下してしまうというおそれがあっ
た。In the conventional method, only one type of this gain is prepared, and a conversion constant is set so as to be optimal during rated operation, which is the most common operation state. Therefore, the gain at the time of a sudden load change is not always an optimum value, and there is a possibility that the control performance may be reduced.
ここでは、負荷急変時として負荷遮断の発生を想定
し、事象発生時にも最適なゲインを選択できる態様につ
いて説明する。Here, a description will be given of a mode in which the occurrence of load shedding is assumed as a sudden load change, and an optimum gain can be selected even when an event occurs.
負荷遮断が発生すると、タービン保護のために蒸気加
減弁101が速やかに閉じ、ほぼ同時にタービンバイパス
弁102が開くことにより、原子炉１からの蒸気は直接復
水器４に導かれる。また、制御棒104の一部である選択
制御棒（以下、SRIと略す）が原子炉１内に挿入される
ことにより、原子炉出力は減少していく。When load shedding occurs, the steam control valve 101 closes promptly to protect the turbine, and the turbine bypass valve 102 opens almost at the same time, so that steam from the reactor 1 is directly led to the condenser 4. Further, when a selected control rod (hereinafter, abbreviated as SRI), which is a part of the control rod 104, is inserted into the reactor 1, the reactor power decreases.
このときの原子炉水位の定性的な挙動を、第７図に示
す。負荷遮断が発生すると、蒸気加減弁101の閉動作が
タービンバイパス弁102の開動作より通常早く行われる
ことから、原子炉１の圧力は上昇し、これに伴い原子炉
１内の冷却水中に含まれるボイドが消失することによ
り、原子炉水位は低下する方向に動く。またこのとき、
同時にSRIが挿入されることにより、燃料棒からの発熱
量は低下し、これに伴いボイドの発生量も減少すること
になり、原子炉水位はさらに低下する。給水制御部100
は、原子炉水位を改めて定められた範囲である水位低設
定点107以上かつ水位高設定点105以下に制御する働きを
有することから、水位の低下（時刻t1参照）を検出する
と同時に、給水調節弁９への開度要求信号21を増加さ
せ、結果として、原子炉水位を回復させていく。The qualitative behavior of the reactor water level at this time is shown in FIG. When the load shedding occurs, the closing operation of the steam control valve 101 is normally performed earlier than the opening operation of the turbine bypass valve 102, so that the pressure of the reactor 1 increases, and the pressure in the reactor 1 is included in the cooling water in the reactor 1. As the voids disappear, the reactor water level moves in a downward direction. At this time,
At the same time, the amount of heat generated from the fuel rods decreases due to the insertion of the SRI, and the amount of voids decreases accordingly, and the reactor water level further decreases. Water supply control unit 100
At the same time, since it has a function of controlling the reactor water level above the water level low set point 107 is again defined range and below the water level high set point 105, upon detecting a decrease in the water level (see time t 1), water supply The opening request signal 21 to the control valve 9 is increased, and as a result, the reactor water level is recovered.
このとき、従来方式と同様に、定格運転時に最適とな
るようなゲインK1が設定されている水位換算機30を使用
しつづけると、ゲインK1が適切でないことにより、水位
は第７図に示したカーブ106のように、一旦回復したの
ちさらに上昇を続け、水位高設定点105付近まで上昇し
ていく。At this time, similarly to the conventional method, continued use of the water level Converter 30 gain K 1 as the optimum during rated operation is set by a gain K 1 is not appropriate, the water level in Figure 7 As shown by the curve 106, once it recovers, it continues to rise further and rises to near the high water level set point 105.
ところで、選択制御棒による原子炉水位の低下量は、
出力分布の変化に依存する。すなわち、第２図に示す様
に負荷遮断前の出力分布（Ａ）と出力分布の形が相似形
である負荷遮断後の出力分布（Ｂ）では、原子炉水位の
低下量は小さい。逆に、負荷遮断前後の出力分布の形が
異る出力分布（Ｃ）は原子炉水位の低下量は大きなもの
となる。この様な原子炉水位変化に対して、給水制御部
置100は、水位の低下を検出すると同時に給水調整弁９
への開度要求信号21を増加させ原子炉水位を回復させて
ゆく。By the way, the amount of decrease in reactor water level by the selection control rod is
Depends on the change in power distribution. That is, as shown in FIG. 2, in the power distribution before load interruption (A) and the power distribution after load interruption (B) in which the shape of the power distribution is similar, the decrease in the reactor water level is small. Conversely, in the power distribution (C) in which the shape of the power distribution before and after the load shedding is different, the amount of decrease in the reactor water level is large. In response to such a change in the reactor water level, the water supply control unit 100 detects the decrease in the water level and at the same time simultaneously detects the decrease in the water level.
To increase the opening request signal 21 to recover the reactor water level.
この時、単に負荷遮断信号だけでゲイン変更を行う
と、前述の出力分布の変化による水位低下と無関係に制
御ゲインが変更されるため、第３図に示す様に、小幅の
水位低下に対し大きなゲインが設定されて不安定となっ
たり、あるいは大幅な水位低下に対して小さなゲインが
設定される結果、水位変動を十分に抑制できなくなる。At this time, if the gain is changed only by the load shedding signal, the control gain is changed irrespective of the decrease in the water level due to the above-mentioned change in the output distribution. Therefore, as shown in FIG. As a result of the gain being set and becoming unstable, or a small gain being set for a large drop in water level, water level fluctuation cannot be sufficiently suppressed.
本実施例では、負荷遮断発生前後の原子炉１内の出力
分布変化を検出器63にて検出し、その出力信号64をゲイ
ン制御部51に入力し、該ゲイン制御部51に負荷遮断信号
発生信号50が入力したとき、制御信号40が出力される。
そして原子炉１内の出力分布の変化の度合に応じてスイ
ッチ41により水位換算機K1から水位換算機K2あるいはK3
へ切り換え、負荷遮断時に最適となるようなゲインK2あ
るいはK3を使用するものである。ここで、ゲインは以下
の（１）に示す値にあらかじめ設定されており、出力分
布変化が大きい場合には最も大きい値K3に、また出力分
布変化が小さい場合にはまん中の値K2に切り換わる。In the present embodiment, a change in the power distribution in the reactor 1 before and after the occurrence of load shedding is detected by the detector 63, and an output signal 64 is input to the gain control section 51, and the load control signal generation When the signal 50 is input, the control signal 40 is output.
The water level Converter from the water level Converter K 1 by the switch 41 in accordance with the degree of change in the power distribution in the reactor 1 K 2 or K 3
To switching, it is to use a gain K 2 or K 3 such that optimal during load rejection. Here, the gain is preset to the values shown in the following (1), the largest value K 3 when the output distribution change is large, and when the power distribution small change in the value K 2 of the middle Switch.
K3＞K2＞K1 ……（１） 上記のゲイン変更によって、給水流量と主蒸気流量の
ミスマッチ量32を水位低下幅にして水位相当値に換算す
ることから、水位回復後の給水調整弁９の絞り込みが早
く、水位のオーバーシュートを低く抑えるという効果が
有る。K 3 > K 2 > K 1 (1) Since the mismatch 32 between the feed water flow rate and the main steam flow rate is converted into the water level equivalent value by the above gain change, the water supply adjustment after the water level recovery is performed. There is an effect that the narrowing of the valve 9 is quick and the overshoot of the water level is suppressed low.
次に第４図により、出力分布変化の検出並びに判断方
法について説明する。沸騰水型原子力発電プラントの原
子炉には、炉内に検出器（LPRM）63が軸方向４箇所、径
方向約40箇所に設置されている（第１図）。Next, a method for detecting and determining a change in the output distribution will be described with reference to FIG. In a nuclear reactor of a boiling water nuclear power plant, detectors (LPRM) 63 are installed at four locations in the axial direction and about 40 locations in the radial direction (FIG. 1).
そのうち中心部１ストリング、周辺部４ストリングか
ら出力分布判定部にLPRM信号64を入力し、加算機52,53
にて炉心上部及び炉心下部の出力密度加算値を算出す
る。The LPRM signal 64 is input to the output distribution judging unit from one string at the center and four strings at the periphery, and the adders 52 and 53
The power density addition value of the upper core part and the lower core part is calculated by.
（A;上部出力密度加算値、Ｚ下部出力密度加算値） ここで算出された平均出力密度を基に、軸方向出力分
布オフセット量Φを演算機54にて以下の（２）式に示す
通り算出する。 (A; added value of upper power density, added value of Z lower power density) Based on the average power density calculated here, the axial output distribution offset amount Φ is calculated by the arithmetic unit 54 as shown in the following equation (2). calculate.
このオフセット値Φは、出力分布のひずみ量を示す値
であり、上方ピークではプラスに、下方ピークではマイ
ナスとなる。 The offset value Φ is a value indicating the amount of distortion of the output distribution, and is positive at the upper peak and negative at the lower peak.
負荷遮断時の選択制御棒挿入の前後で、第５図に示す
様に出力分布があまり変化しない場合は、オフセット量
Φの変化自在も０に等しいが、第同図に示す出力分布変
化の大きい場合は、オフセット量Φも、Φ前＝−0.10→
Φ後＝0.15と変化する。When the output distribution does not change much before and after the insertion of the selection control rod at the time of load shedding as shown in FIG. 5, the offset amount Φ can be freely changed to 0, but the output distribution change shown in FIG. In this case, the offset amount Φ is also before Φ = -0.10 →
After φ changes to 0.15.
したがって、オフセット変化量｜Φ前後｜＝｜Φ前−
Φ後｜に合わせて、以下の如くミスマッチゲインを切り
換える。Therefore, the amount of offset change | before and after | Φ |
After Φ, the mismatch gain is switched as follows.
｜Φ前後｜＜0.1→ミスマッチゲインK2 ｜Φ前後｜＞0.1→ミスマッチゲインK3 Φ前の値は、負荷遮断信号発生時のオフセット値をメ
モリー56に記憶させ、その値と新たに計算されるΦ後と
の偏差55を連続的に監視し、その偏差55に従い、対応す
るミスマッチゲインの切り換え信号57,58を発生させ
る。61,62はオフセット偏差判定部を示す。│Φ around│ <0.1 → mismatch gain K 2 │around││0.1 → mismatch gain K 3 Φ Before, the offset value when the load shedding signal is generated is stored in the memory 56, and the value is newly calculated. The deviation 55 from the time after φ is continuously monitored, and according to the deviation 55, switching signals 57 and 58 for the corresponding mismatch gain are generated. Reference numerals 61 and 62 denote offset deviation determination units.
また、59はタイマーを示し、負荷遮断直後の原子炉内
の出力分布は第５図右下に示したように整定されていな
いため、その間の出力分布は検出せず、整定後の出力分
布を検出するようにするためのものである。このタイマ
ー時間は通常、負荷遮断後５秒に設定しておくのが望ま
しい。Further, reference numeral 59 denotes a timer. Since the power distribution in the reactor immediately after the load rejection is not settled as shown in the lower right of FIG. 5, the power distribution during the period is not detected, and the power distribution after the settling is determined. It is for detecting. Usually, it is desirable to set the timer time to 5 seconds after the load is cut off.
なお本制御ゲイン切り換えは、負荷遮断発生後約３分
を経過した後は、原子炉水位が通常水位まで復帰するの
で、負荷遮断発生後３分にてリセットを行い通常制御の
安定化を図るようにする。In this control gain switching, the reactor water level returns to the normal water level approximately three minutes after the load shedding occurs, so the reset is performed three minutes after the load shedding occurs to stabilize the normal control. To
本実施例による負荷遮断時の原子炉水位変化を第６図
に示す。負荷遮断と同時に選択制御棒が挿入され、原子
炉水位は低下するが、この時の出力分布オフセット偏差
により給水制御系ミスマッチゲインがK3に変更されるた
め、原子炉水位回復時の水位上昇は抑制され、原子炉水
位は速やかに通常水位に戻る。また、水位変動が小さい
場合にはミスマッチゲインはK1からK2に変更されるため
安定に原子炉水位を制御することができる。そして、３
分後ミスマッチゲインは通常運転時の値K1に戻る。FIG. 6 shows changes in the reactor water level during load shedding according to the present embodiment. Load shedding and is inserted simultaneously selected control rods, although the reactor water level is reduced, since the water supply control system mismatch gain by the power distribution offset deviation when this is changed to K 3, the water level rise during reactor water level recovery It is suppressed and the reactor water level quickly returns to the normal water level. Further, mismatch gain when the water level variation is small can be controlled stably reactor water level to be changed from K 1 to K 2. And 3
Minute after the mismatch gain returns to the value K 1 during normal operation.
なお、上記いずれの実施例も換算部は３つの換算機か
らなる場合を示したが、４つ以上の換算機で構成しても
よいことはもちろんである。あるいは、換算機自体は１
つとし、この換算機に複数のゲインを設定し、負荷急変
信号により判別プログラム等を利用して切り替え可能に
しても同様の効果が得られる。In each of the above embodiments, the conversion unit includes three converters. However, it is needless to say that four or more converters may be used. Alternatively, the converter itself is 1
The same effect can be obtained even if a plurality of gains are set in the converter and switching can be performed using a discrimination program or the like by a sudden load change signal.
また、上記の説明では、物理量がミスマッチ量32と水
位相熱信号26となる換算部に本発明を適用した例を示し
たが、他の物理量の換算部であってもよいことはもちろ
んである。Further, in the above description, the example in which the present invention is applied to the conversion unit in which the physical quantity becomes the mismatch amount 32 and the water phase heat signal 26 is shown, but it is needless to say that the conversion unit may be another physical quantity conversion unit. .
本発明によれば、給水制御部のゲインを原子炉出力分
布変化に対応させて切り替えるので、負荷遮断時の原子
炉水位変動を抑制し、最適ゲインで運転させることがで
きる。従って、負荷急変後に原子炉水位は速やかに通常
水位に戻り、スクラムの発生を防止できるので、プラン
トの稼動率向上の効果が有る。According to the present invention, since the gain of the water supply control unit is switched according to the change in the reactor power distribution, it is possible to suppress the fluctuation of the reactor water level when the load is cut off and to operate the reactor with the optimum gain. Therefore, the reactor water level quickly returns to the normal water level after a sudden change in load, and the generation of scram can be prevented, which has the effect of improving the plant operation rate.
第１図は本発明の一実施例に係る給水制御装置の概略構
成図、第２図は原子炉出力分布変化が原子炉水位に及ぼ
す影響を示した図、第３図は従来制御方式での負荷遮断
時の原子炉水位変化を示した図、第４図は本発明の一実
施例によるゲイン制御部の詳細構成図、第５図は原子炉
出力分布変化とオフセット値の関係を示した図、第６図
は本発明の一実施例による給水制御装置の動作による負
荷遮断時・原子炉水位変化図、第７図は異なる従来方式
での負荷遮断時の原子炉水位変化を示した図である。 １……原子炉、30……水位換算機（換算部）、51……ゲ
イン制御部、52,53……出力密度加算器、54……出力分
布オフセット演算器、55……オフセット値の偏差、56…
…メモリー、57,58……ゲイン切り換え信号、59……タ
イマ、61,62……オフセット偏差判定部、63……検出
器、100……給水制御部。FIG. 1 is a schematic configuration diagram of a water supply control device according to an embodiment of the present invention, FIG. 2 is a diagram showing an influence of a reactor power distribution change on a reactor water level, and FIG. 3 is a diagram showing a conventional control system. FIG. 4 is a diagram showing a reactor water level change at the time of load interruption, FIG. 4 is a detailed configuration diagram of a gain control unit according to an embodiment of the present invention, and FIG. 5 is a diagram showing a relationship between a reactor power distribution change and an offset value. FIG. 6 is a diagram showing a change in the reactor water level when the load is cut off by the operation of the water supply control device according to one embodiment of the present invention, and FIG. 7 is a diagram showing a change in the reactor water level when the load is cut off in a different conventional method. is there. 1 ... Reactor, 30 ... Water level converter (converter), 51 ... Gain controller, 52,53 ... Power density adder, 54 ... Output distribution offset calculator, 55 ... Offset value deviation , 56…
... Memory, 57,58 ... Gain switching signal, 59 ... Timer, 61,62 ... Offset deviation determination unit, 63 ... Detector, 100 ... Water supply control unit.
Claims (5)
備え、この給水制御部は原子炉内の水位変動に関係する
物理量を他の物理量に換算する換算部を有し、この換算
を経て前記給水量が定まる原子力発電プラントの給水制
御装置において、前記換算部の換算定数または換算関数
を換算量を異ならせて複数設け、原子炉内に出力分布変
化の検出器を設け、原子力発電プラントの負荷急変前後
の前記検出器からの出力信号により他の換算定数または
換算関数に切り替え可能に形成したことを特徴とする原
子力発電プラントの給水制御装置。A water supply control unit for controlling a water supply amount to a nuclear reactor, the water supply control unit having a conversion unit for converting a physical quantity related to a water level fluctuation in the reactor into another physical quantity. In the water supply control device for a nuclear power plant in which the amount of water supply is determined via the above, a plurality of conversion constants or conversion functions of the conversion unit are provided with different conversion amounts, and a detector of a power distribution change is provided in the reactor, A water supply control device for a nuclear power plant, characterized in that it can be switched to another conversion constant or another conversion function by an output signal from the detector before and after a sudden change in the load of the plant.
後の原子炉内の出力分布の検出は、出力分布整定後とす
るタイマーを設けた原子力発電プラントの給水制御装
置。2. The water supply control device for a nuclear power plant according to claim 1, wherein a timer is provided for detecting the power distribution in the reactor after the sudden change in the load by the detector.
への給水流量と原子炉から出る主蒸気流量の差を原子炉
水位相当信号に変更し、換算定数又は換算関数の切り替
えは負荷遮断の発生を示す信号で行なう原子力発電プラ
ントの給水制御装置。3. The conversion unit according to claim 1, wherein the conversion unit changes a difference between a water supply flow rate to the reactor and a main steam flow rate flowing out of the reactor to a signal corresponding to a reactor water level, and the conversion of the conversion constant or the conversion function is performed by a load. A water supply control device for a nuclear power plant that uses a signal indicating the occurrence of shutoff.
からなり、各換算後は換算量の異なる換算定数または換
算関数が設定されている原子力発電プラントの給水制御
装置。4. The water supply control device for a nuclear power plant according to claim 1, wherein the conversion unit includes a plurality of conversion units, and after each conversion, conversion constants or conversion functions having different conversion amounts are set.
からなり、この換算機に複数の換算定数または換算関数
が設定されている原子力発電プラントの給水制御装置。5. The water supply control device for a nuclear power plant according to claim 1, wherein the conversion unit comprises one converter, and a plurality of conversion constants or conversion functions are set in the converter.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63021670A JP2627524B2 (en) | 1988-02-01 | 1988-02-01 | Water supply control device for nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63021670A JP2627524B2 (en) | 1988-02-01 | 1988-02-01 | Water supply control device for nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01196598A JPH01196598A (en) | 1989-08-08 |
| JP2627524B2 true JP2627524B2 (en) | 1997-07-09 |
Family
ID=12061479
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63021670A Expired - Lifetime JP2627524B2 (en) | 1988-02-01 | 1988-02-01 | Water supply control device for nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2627524B2 (en) |
-
1988
- 1988-02-01 JP JP63021670A patent/JP2627524B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH01196598A (en) | 1989-08-08 |
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