JPH0241719B2 - - Google Patents
Info
- Publication number
- JPH0241719B2 JPH0241719B2 JP56090767A JP9076781A JPH0241719B2 JP H0241719 B2 JPH0241719 B2 JP H0241719B2 JP 56090767 A JP56090767 A JP 56090767A JP 9076781 A JP9076781 A JP 9076781A JP H0241719 B2 JPH0241719 B2 JP H0241719B2
- Authority
- JP
- Japan
- Prior art keywords
- pressure
- reactor
- control
- steam
- temperature change
- Prior art date
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- Expired - Lifetime
Links
- 238000000034 method Methods 0.000 claims description 21
- 239000002826 coolant Substances 0.000 claims description 19
- 238000013461 design Methods 0.000 claims description 3
- 230000008646 thermal stress Effects 0.000 claims description 3
- 238000001514 detection method Methods 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 238000009530 blood pressure measurement Methods 0.000 description 5
- 238000009835 boiling Methods 0.000 description 4
- 230000001276 controlling effect Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000013459 approach Methods 0.000 description 2
- 230000001105 regulatory effect Effects 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000003340 mental effect Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
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
Landscapes
- Control Of Turbines (AREA)
Description
【発明の詳細な説明】
本発明は沸謄水型原子力発電プラントの原子炉
圧力の制御方法に係り、特に原子炉昇圧時に冷却
材の温度変化率を制限値以内に保つように原子炉
圧力を制御する方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for controlling reactor pressure in a boiling water nuclear power plant, and in particular to a method for controlling reactor pressure in order to maintain the rate of change in coolant temperature within a limit value when boosting the reactor pressure. It concerns a method of control.
沸謄水型原子力発電所における起動の際は、従
来一般に運転員が蒸気圧を調節操作することによ
つて冷却材温度変化率（通常±55℃／Hr）を越
えないように手動的に制御していた。その方法を
第１図乃至第３図を参照しつつ次に述べる。 Conventionally, when starting up a boiling water nuclear power plant, operators manually control the rate of change in coolant temperature (usually ±55°C/Hr) by adjusting the steam pressure. Was. The method will be described below with reference to FIGS. 1 to 3.
第１図において１は原子炉圧力容器、２は炉心
部である。平常運転時には炉心部２で発生した蒸
気がタービン止め弁４を介してタービン５に供給
され、復水器６に回収される。 In FIG. 1, 1 is a reactor pressure vessel, and 2 is a reactor core. During normal operation, steam generated in the reactor core 2 is supplied to the turbine 5 via the turbine stop valve 4 and recovered in the condenser 6.
起動時には上記の止め弁４を止じたままタービ
ンバイパス弁３によつて発生蒸気をバイパスさせ
このバイパス弁３の開度調節によつて蒸気圧力を
制御する。 At startup, the generated steam is bypassed by the turbine bypass valve 3 while the stop valve 4 is stopped, and the steam pressure is controlled by adjusting the opening degree of the bypass valve 3.
原子炉１内の発熱量は上記の圧力制御と関係な
く、核反応の制御によつて定まるが、炉内圧力は
上記の蒸気圧調節によつて定められ、蒸気圧調節
によつて蒸気温度も制御される。 The amount of heat generated within the reactor 1 is determined by the control of the nuclear reaction, regardless of the pressure control described above, but the pressure within the reactor is determined by the steam pressure adjustment described above, and the steam temperature is also determined by the steam pressure adjustment. controlled.
蒸気の圧力は蒸気圧検出器８によつて検出さ
れ、その蒸気圧力信号９はタービン圧力制御装置
７に入力される。上記タービン圧力制御装置７に
は、運転時の手動調節によつて圧力設定信号１１
が与えられ、制御装置７は蒸気圧力信号９と圧力
設定信号１１との偏差が零となるようにバイパス
弁３を開閉作動せしめるように開度要求信号１０
を出力し、蒸気圧力信号９が圧力設定信号１１の
値よりも高くなるとバイパス弁３を開弁させる。 The steam pressure is detected by a steam pressure detector 8, and the steam pressure signal 9 is input to the turbine pressure control device 7. The turbine pressure control device 7 receives a pressure setting signal 11 by manual adjustment during operation.
is given, and the control device 7 outputs an opening request signal 10 to open and close the bypass valve 3 so that the deviation between the steam pressure signal 9 and the pressure setting signal 11 becomes zero.
is output, and when the steam pressure signal 9 becomes higher than the value of the pressure setting signal 11, the bypass valve 3 is opened.
前記の運転員による圧力調節は次記各項の条件
に適合するように行わねばならないので、高度の
熟練と不断の監視とを必要とし、且つ高い精神的
負荷を伴う作業である。即ち、
(イ) 蒸気温が急激に変化すると、原子炉を構成す
る各部材に熱応力、熱変形を生じて危険である
ため、設計基準に於て原子炉冷却材の温度変化
率の制限値が定められている（沸謄水型原子炉
の起動時について言えば、上記の制限値は即ち
蒸気の昇温率許容限度である。以下、制限値と
略称する）。運転操作員は蒸気温度の上昇が制
限値を越えないように操作しなければならな
い。 The above-mentioned pressure adjustment by the operator must be carried out to meet the following conditions, and is therefore a work that requires a high level of skill and constant monitoring, and is accompanied by a high mental load. In other words, (a) A sudden change in steam temperature causes thermal stress and thermal deformation in each component of the reactor, which is dangerous. (For the start-up of a boiling water reactor, the above limit value is the permissible limit for the steam temperature increase rate. Hereinafter, it will be abbreviated as limit value). Operators must operate so that the rise in steam temperature does not exceed the limit value.
(ロ) バイパス弁３は、なるべく閉じたままに保つ
ことが望ましい。その理由は、起動時において
は上記の蒸気圧制御と併行して炉水位制御が行
われるので、バイパス弁を開くと上記炉水位制
御操作に影響を及ぼし、原子炉をスクラムさせ
る虞れがあるからである。(b) It is desirable to keep the bypass valve 3 closed as much as possible. The reason is that during startup, reactor water level control is performed in parallel with the above steam pressure control, so opening the bypass valve may affect the above reactor water level control operation and cause the reactor to scram. It is.
(ハ) 上記各項の制限を守りつつ、運転計画に従つ
て所定の時間内に所定圧まで昇圧させねばなら
ないことは勿論である。(c) It goes without saying that the pressure must be raised to a predetermined pressure within a predetermined time according to the operation plan while observing the restrictions in each of the above items.
このため、運転計画に基づいて原子炉冷却材の
温度変化率目標値（沸謄水型原子炉の起動時につ
いて言えば蒸気温度の昇温率の計画値である。次
下、目標値と略称する）が、前記の制限値の範囲
内で設定され、これに基づいて圧力制御が行われ
る。 For this reason, based on the operation plan, the target value for the temperature change rate of the reactor coolant (for the startup of a boiling water reactor, it is the planned value for the rate of steam temperature increase. ) is set within the above-mentioned limit value, and pressure control is performed based on this.
次に、原子炉における圧力制御方式について第
２図を参照しつつ略述する。 Next, a pressure control system in a nuclear reactor will be briefly described with reference to FIG. 2.
同図の横軸は時間、縦軸は圧力である。蒸気が
飽和状態である場合は蒸気圧は蒸気温度によつて
定まるから、前述の蒸気温度の昇温目標値を蒸気
圧力の昇圧目標値に換算することができる。直線
Ａは昇圧目標を表わす圧力−時間率カーブであ
る。昇圧操作における圧力制御は段階的に圧力設
定値をΔPずつ上昇させて行うので、上記昇圧目
標線Ａに合わせた圧力設定カーブＢは階段状の曲
線となる。同図のTIMEは圧力設定値を変更する
時間間隔である。 In the figure, the horizontal axis is time and the vertical axis is pressure. When the steam is in a saturated state, the steam pressure is determined by the steam temperature, so the aforementioned target value for increasing the steam temperature can be converted into the target value for increasing the steam pressure. Straight line A is a pressure-time rate curve representing a pressure increase target. Since the pressure control in the pressure increase operation is performed by increasing the pressure setting value stepwise by ΔP, the pressure setting curve B that matches the pressure increase target line A becomes a step-like curve. TIME in the figure is the time interval at which the pressure setting value is changed.
上述のように圧力設定カーブＢを定めるには、
時間間隔TIMEを一定値として昇圧値ΔPを目標
線Ａに合わせるように設定することもできる。ま
た、一回の昇圧値ΔPを一定値として時間間隔
TIMEを目標線Ａに合わせるように設定すること
もできる。 To determine the pressure setting curve B as described above,
It is also possible to set the boost value ΔP to match the target line A by setting the time interval TIME to a constant value. In addition, the time interval is
TIME can also be set to match target line A.
蒸気の圧力Ｐ及び圧力設定上昇値ΔPと、温度
上昇値ΔTとの関係は次式で表わされる。 The relationship between the steam pressure P, the pressure setting increase value ΔP, and the temperature increase value ΔT is expressed by the following equation.
ΔT／TIME＝RATE
ΔT＝ｆ（Ｐ＋ΔP）−ｆ(P)
ただし、ｆ；圧力→飽和温度換算係数
RATE；昇温目標値〔℃／Hr〕
そして、TIMEを一定値としてΔPを算出する
には次式による。 ΔT/TIME=RATE ΔT=f(P+ΔP)−f(P) However, f: Pressure→Saturation temperature conversion coefficient RATE: Temperature increase target value [℃/Hr] And to calculate ΔP with TIME as a constant value: According to the following formula.
ΔP＝f-1｛RATE・TIME＋ｆ(P)｝−Ｐ
ただし、f-1；飽和温度→圧力換算係数
また、ΔPを一定値としてTIMEを算出するに
は次式による。 ΔP=f -1 {RATE・TIME+f(P)}-P However, f -1 ; Saturation temperature→pressure conversion coefficient Further, to calculate TIME with ΔP as a constant value, use the following formula.
TIME＝ｆ（Ｐ＋ΔP）−ｆ（Ｐ）／RATE
次に、ΔPを一定値として、圧力設定の時間間
隔TIMEを調節する方式の圧力制御について、従
来一般に行われている方法を第３図に示す。 TIME=f(P+ΔP)-f(P)/RATE Next, Fig. 3 shows a conventional method of pressure control in which the time interval TIME for pressure setting is adjusted while ΔP is a constant value. .
Ａは先に説明した昇圧目標線、Ｂはこれに合わ
せて設定した階段状の圧力制御カーブ、Ｃは蒸気
圧力の上昇カーブ（実測値）である。 A is the previously explained pressure increase target line, B is a stepped pressure control curve set in accordance with this, and C is a steam pressure increase curve (actually measured value).
実際の圧力制御において、蒸気圧力の上昇カー
ブ（実測値）Ｃが圧力制御カーブＢに比して過低
になつた場合と過高になつた場合とに制御圧力の
設定変更を行わねばならないが、このため、実測
値が制御カーブＢよりも下回る場合の許容偏差値
εSを予め設定しておく。 In actual pressure control, the control pressure setting must be changed when the steam pressure rise curve (actually measured value) C becomes too low or too high compared to the pressure control curve B. , Therefore, the allowable deviation value ε S when the actual measured value is lower than the control curve B is set in advance.
本図において、時間軸上のt1時点においては、
圧力実測カーブＣと制御カーブＢとの差がεSより
も小さいので、この時点で設定圧力をP1からP2
までΔPだけ上昇させ、t2時点までの一定時間間
隔T1の間、実測圧力カーブＣの上昇を待機する。
上述の設定圧力をΔPだけ上昇させる操作は第１
図の装置における圧力設定信号１１を手動操作し
て行われる。 In this figure, at time t 1 on the time axis,
Since the difference between the actual pressure measurement curve C and the control curve B is smaller than ε S , the set pressure is changed from P 1 to P 2 at this point.
and waits for the measured pressure curve C to rise during a fixed time interval T1 until time t2 .
The above operation to increase the set pressure by ΔP is the first operation.
This is done by manually operating the pressure setting signal 11 in the device shown in the figure.
t2時点において、実測圧力Ｃは制御圧力Ｂに比
して許容偏差εS以内まで上昇しているので、再び
圧力P3までΔPだけ制御圧力を上げてt3時点まで
のT1時間待機する。 At time t 2 , the measured pressure C has risen to within the allowable deviation ε S compared to the control pressure B, so increase the control pressure by ΔP again to pressure P 3 and wait for T 1 hour until time t 3 . .
t3時点において、実測圧力Ｃは制御圧力Ｂに比
して許容偏差εSよりも大きく下回つている。この
場合は設定圧力の上昇を延期して待機を続ける。 At time t3 , the measured pressure C is much lower than the allowable deviation ε S compared to the control pressure B. In this case, the increase in set pressure is postponed and standby is continued.
t4時点で実測圧力Ｃが制御圧力Ｂに比して許容
偏差εS以内まで上昇しているので、このt4時点で
制御圧力の設定をΔPだけ上げる。A′は、t3時点
からt4時点まで待機時間を延長した後の新たな昇
圧目標線であり、前記の目標線Ａと同じ勾配で、
時間軸の遅れ方向にT2だけずれた形となる。 At time t 4 , the measured pressure C has increased to within the allowable deviation ε S compared to the control pressure B, so at this time t 4 , the control pressure setting is increased by ΔP. A′ is a new boost target line after extending the waiting time from time t 3 to time t 4 , and has the same slope as the target line A,
The shape is shifted by T 2 in the lag direction of the time axis.
この例では、t4時点からt5時点までの間に実測
圧力カーブＣが急上昇し、td時点において制御圧
力設定値P4に達している。このため、Ｄ点にお
いてバイパス弁が開き、実測圧力カーブＣは制御
カーブＢを越えないように調圧される。 In this example, the measured pressure curve C rises rapidly from time t 4 to time t 5 and reaches the control pressure set value P 4 at time t d . Therefore, the bypass valve opens at point D, and the pressure is regulated so that the measured pressure curve C does not exceed the control curve B.
以上のような方式で制御を行う場合、T1時間
ごとに昇圧状態を確認して制御圧力の設定値を
ΔPずつ上げねばならないので、熟練した運転員
が絶えず監視しながら、設定圧力の上昇操作を行
わなければならず、その上、上例のようにＤ点で
バイパス弁が開かれると、他の操作（例えば炉水
位制御）に影響を与えるので余り好ましくない。 When performing control using the above method, it is necessary to check the pressure increase state every hour and increase the set value of the control pressure by ΔP, so a skilled operator must constantly monitor the pressure and increase the set pressure. Furthermore, if the bypass valve is opened at point D as in the above example, this is not very desirable because it affects other operations (for example, reactor water level control).
本発明の目的は、原子炉起動の際、原子炉冷却
材の温度変化率が制限値を越えないように自動的
に制御し、かつ、タービンバイパス弁の開弁を可
能な範囲内で回避し得る原子炉圧力制御方法を提
供しようとするものである。 The purpose of the present invention is to automatically control the temperature change rate of the reactor coolant so that it does not exceed a limit value during reactor startup, and to avoid opening the turbine bypass valve to the extent possible. The purpose of this paper is to provide a method for controlling reactor pressure that achieves the desired results.
上記の目的を達成するため、本発明は、蒸気圧
力を検知することによつて原子炉冷却材の温度上
昇を監視し、原子炉圧力容器の熱応力の制約から
設計的に定まる冷却材温度変化率制限値と、運転
計画に基づいて上記の冷却材温度変化率制限値を
越えない範囲で定められる冷却材温度変化率目標
値との双方を原子炉圧力制御の基準数値として用
い、かつ、原子炉昇圧操作中の各時点ごとに上記
２つの基準数値と冷却材温度変化率実測値との偏
差値をそれぞれ演算して圧力制御装置に入力せし
め、この圧力制御装置により、原子炉冷却材の温
度変化率が前記の冷却材温度変化率制限値に達し
ない状態においては、蒸気加減弁を全閉位置に保
たしめるように制御することを特徴とする。 In order to achieve the above object, the present invention monitors the temperature rise of the reactor coolant by detecting the steam pressure, and the coolant temperature changes determined by design from the thermal stress constraints of the reactor pressure vessel. Both the rate limit value and the coolant temperature change rate target value, which is determined within a range that does not exceed the above-mentioned coolant temperature change rate limit value based on the operation plan, are used as reference values for reactor pressure control, and At each point during the reactor pressure boost operation, the deviation values between the above two reference values and the actual measured value of the coolant temperature change rate are calculated and input to the pressure control device, and the pressure control device controls the temperature of the reactor coolant. In a state where the rate of change does not reach the coolant temperature change rate limit value, the steam control valve is controlled to be kept at the fully closed position.
第４図は本発明に係る制御方法を実施するため
に構成した原子炉の圧力制御機構の一例である。 FIG. 4 is an example of a pressure control mechanism for a nuclear reactor configured to carry out the control method according to the present invention.
従来装置（第１図）と同様の構成部材である圧
力検出器８の出力信号９は従来装置と同様のター
ビン圧力制御装置７、及び本発明を実施するため
に付設した原子炉圧力制御装置１２に入力させ
る。 The output signal 9 of the pressure detector 8, which is a component similar to the conventional device (FIG. 1), is transmitted to the turbine pressure control device 7, which is the same as the conventional device, and the reactor pressure control device 12, which is attached to carry out the present invention. input.
そして、切替器１４は従来装置と同様の人為的
な圧力設定信号１１、または上記の制御装置１２
の出力である圧力設定信号１３の、いずれか一方
をタービン圧力制御装置７に入力させるために設
けた手動・自動切替器である。 The switch 14 is operated by an artificial pressure setting signal 11 similar to the conventional device, or by the control device 12 described above.
This is a manual/automatic switch provided to input either one of the pressure setting signals 13, which are the outputs of the turbine pressure control device 7, to the turbine pressure control device 7.
従つて、上記の切替器１４が手動側に切替えら
れているとき、本装置は従来装置（第１図）と同
様の機能を有する。また、上記の切替器１４が自
動側に切替えられていると、後に詳述するように
本発明に係る方法の制御が行われる。 Therefore, when the above-mentioned switch 14 is switched to the manual side, this device has the same function as the conventional device (FIG. 1). Further, when the above-mentioned switch 14 is switched to the automatic side, the method according to the present invention is controlled as will be described in detail later.
前記の原子炉圧力制御装置１２は予め与えられ
た圧力上昇の制限値と目標値とを記憶していて、
圧力検出信号９を入力されると後述のごとく所定
の演算を行い、演算結果によつて圧力設定信号１
３を出力する機能を有している。 The reactor pressure control device 12 stores predetermined pressure increase limit values and target values, and
When the pressure detection signal 9 is input, a predetermined calculation is performed as described later, and the pressure setting signal 1 is determined based on the calculation result.
It has the function of outputting 3.
本発明方法は、昇温、昇圧の制限値と、昇温、
昇圧の目標値と、２つの数値を管理基準として用
いる。 The method of the present invention has a limit value for temperature rise and pressure rise, and
The target value for boosting the pressure and the two numerical values are used as management standards.
昇温制限値は設計基準によつて定められてお
り、実際の制御においては温度を圧力に換算して
昇圧制限値RATE1を設定し、後述のように制御
する。 The temperature increase limit value is determined by design standards, and in actual control, the temperature is converted into pressure, the pressure increase limit value RATE 1 is set, and the control is performed as described below.
昇温目標値は運転計画に基づき、昇温制限値の
範囲内で適宜に定められる。実際の制御において
は温度を圧力に換算して昇圧目標値RATE2を設
定し、後述のように制御する。 The temperature increase target value is appropriately determined within the temperature increase limit value based on the operation plan. In actual control, temperature is converted into pressure, pressure increase target value RATE 2 is set, and control is performed as described below.
第５図は本発明方法による圧力制御の実施例を
示す。 FIG. 5 shows an embodiment of pressure control according to the method of the invention.
制御開始時点t1において、圧力設定変更待機時
間T1を次式によつて算出する。 At control start time t 1 , pressure setting change waiting time T 1 is calculated using the following equation.
T1＝ｆ（Ｐ＋PS）−ｆ（Ｐ）／RATE2
即ち、T1はRATE2に従つて規定値PSだけ上昇
するに要する時間を意味する。 T 1 =f(P+P S )-f(P)/RATE 2 That is, T 1 means the time required to increase by the specified value P S according to RATE 2 .
第５図の実施例においては実測蒸気圧カーブＣ
が前述のRATE2に比して若干下回つており、制
御を開始したt1時点からT1時間を経過してt2時点
になつた時、圧力実測値Ｃは制御圧力設定値Ｂに
比して許容偏差εS以内の低圧である。このように
ε≦εS（但し、εは制御圧力設定値Ｂに対する実
測値Ｃの偏差）の場合、第７図について後述する
ような自動制御により圧力設定値をP6からP7ま
で規定値PSだけ階段状に上昇させる。この場合の
圧力設定カーブＢの形状は第３図（従来技術）に
おけるt2時点の形状と同様になる。 In the example of FIG. 5, the actually measured vapor pressure curve C
is slightly lower than RATE 2 mentioned above, and when time T 1 has passed since control started at time t 1 and time t 2 has passed, the actual pressure value C is compared to the control pressure set value B. and the pressure is within the tolerance ε S. In this way, when ε≦ε S (where ε is the deviation of the actual measured value C from the control pressure set value B), the pressure set value is set to the specified value from P 6 to P 7 by automatic control as described later with reference to FIG. Only P S is raised in a stepwise manner. The shape of the pressure setting curve B in this case is similar to the shape at time t2 in FIG. 3 (prior art).
上記のようにRATE2に従つて制御圧力カーブ
Ｂを定めると、t2時点において上記のカーブＢ
は、RATE1に比してΔPS(1)の余裕をもつて下回
る。 If the control pressure curve B is determined according to RATE 2 as described above, the above curve B will be
is lower than RATE 1 with a margin of ΔP S (1).
ΔPS(1)＝f-1｛RATE2・T1＋ｆ(P)｝−Ｐ−PS
本図の例のように、実測圧力カーブＣが
RATE2を下回つている場合は、T1時間ごとに設
定圧力を規定圧力PSずつ上昇させ、設定圧力カー
ブＢが常に実測圧力カーブＣよりも高くなるよう
に保つ。従つて、蒸気圧力が制御設定圧力に達し
てバイパス弁が開かれるという状態に至らない。ΔP S (1)=f -1 {RATE 2・T 1 +f(P)}−P−P SAs in the example in this figure, the measured pressure curve C is
If the rate is below RATE 2 , increase the set pressure by the specified pressure P S every hour T to keep the set pressure curve B always higher than the measured pressure curve C. Therefore, a state is not reached where the steam pressure reaches the control set pressure and the bypass valve is opened.
第６図の実施例は、実測蒸気圧カーブＣが
RATE2を越えて上昇した場合である。この場合
には、圧力実測カーブＣが制御カーブＢに対して
バイパス弁開指標値εn以内に接近したtB時点にお
いて、原子炉圧力制御装置が圧力設定値を前述の
余裕温度ΔPS(1)だけ階段的に上昇させる。これに
よりtB時点におけるバイパス弁の開弁が回避さ
れ、圧力実測カーブＣはRATE1を越えない範囲
でRATE2以上になることを許容される。このよ
うにしてT1時間を経過してt2時点に達したとき、
ε≦εnであれば、前述したt1時点における制御圧
力設定カーブＢの設定圧上昇と同様に、設定圧を
PSだけ上昇させる。 In the example shown in FIG. 6, the actually measured vapor pressure curve C is
This is the case when the rate rises above RATE 2 . In this case, at time t B when the actual pressure measurement curve C approaches the control curve B within the bypass valve opening index value ε n , the reactor pressure control system changes the pressure set value to the above-mentioned margin temperature ΔP S (1 ) in a stepwise manner. This prevents the bypass valve from opening at time t B , and allows the actual pressure measurement curve C to exceed RATE 2 without exceeding RATE 1 . In this way, when time T 1 has passed and time t 2 is reached,
If ε≦ε n , the set pressure is increased in the same way as the increase in the set pressure of the control pressure setting curve B at the time t 1 described above.
Increase only PS .
上述の制御方法のフローチヤートを第７図に示
す。 A flowchart of the above-mentioned control method is shown in FIG.
制御開始したとき、最初の１図はステツプ２１
で初期起動であることを判定してステツプ２７ま
で直行し、待機時間Ti+1および圧力設定余裕ΔPS
（ｉ＋１）を算定し、ステツプ２８、同２９を経
て、Δt（通常10〜15秒）後に最初のステツプ２１
に戻る。その後、Δtごとに繰返す各サイクルに
おいては、このステツプ２１を通過して次のステ
ツプ２２で圧力偏差εを計算する。即ち、実測圧
力と設定圧力との差εを算出する。 When control starts, the first diagram is step 21.
It is determined that it is an initial start-up, and the process goes straight to step 27, where the waiting time T i+1 and pressure setting margin ΔP S are determined.
(i+1), goes through steps 28 and 29, and returns to the first step 21 after Δt (usually 10 to 15 seconds).
Return to Thereafter, in each cycle repeated every Δt, this step 21 is passed and the pressure deviation ε is calculated in the next step 22. That is, the difference ε between the measured pressure and the set pressure is calculated.
次のステツプ２３で上記のεと、計算機に記憶
させてあるεnとを比較演算させ、ε＜εnがNOで
あればステツプ２４で待機時間T1が経過したか
否かを判断した後、ステツプ２５でε≦εSを判定
し、これがYESであればステツプ２６で圧力設
定値をPSだけ変更（上昇）するが、このときε≦
εSがNOであればステツプ２８，２９を経てΔt後
に前記と同様の作動を繰返す。このようにして10
〜15秒ごとに繰返し演算しているうちに実測蒸気
圧が制御圧近くまで上昇してきてε＜εnになつた
場合には、ステツプ２３から同３０、同３１に進
み、制御設定圧力を圧力設定余裕ΔPS(i)だけ上昇
させる。この作用を具体的な作動で説明すると、
バイパス弁が開弁する状態（ε＝０）を事前に
（ε＜εnになつたときに）検知して、蒸気温度が
制限値を越えない範囲内で（圧力設定余裕ΔPS(i)
だけ）上昇させて、蒸気加減弁であるバイパス弁
の開弁を抑制するものである。 In the next step 23, the above ε is compared with ε n stored in the computer, and if ε<ε n is NO, it is determined in step 24 whether or not the waiting time T 1 has elapsed. , it is determined in step 25 that ε≦ε S , and if YES, the pressure setting value is changed (increased) by P S in step 26, but at this time ε≦
If ε S is NO, steps 28 and 29 are performed, and the same operation as described above is repeated after Δt. In this way 10
While the calculation is repeated every ~15 seconds, if the measured steam pressure rises close to the control pressure and ε<ε n , proceed from step 23 to step 30 and step 31, and change the control set pressure to Increase by setting margin ΔP S (i). To explain this effect in concrete terms,
The state in which the bypass valve opens (ε = 0) is detected in advance (when ε < ε n ), and the pressure setting margin ΔP S (i) is set within the range where the steam temperature does not exceed the limit value.
) to suppress the opening of the bypass valve, which is a steam control valve.
上述のような制御方法を用いると、蒸気圧力が
制限値を越えない範囲内で自動的にバイパス弁の
開弁が極力回避されるので、誤判断や誤操作のた
めに避け得べき開弁作動が行われる虞れが無い。 By using the control method described above, the opening of the bypass valve is automatically avoided as much as possible within the range where the steam pressure does not exceed the limit value, so that avoidable opening operations due to misjudgment or erroneous operation are avoided. There is no risk that it will be done.
次に、第８図および第９図について本発明方法
の変形例を説明する。 Next, a modification of the method of the present invention will be explained with reference to FIGS. 8 and 9.
本例においては制御開始時点t1において前述と
同様のRATE1、RATE2を設定し、この時点で圧
力PSだけ上昇させた制御圧力カーブＢとRATE1
とが交わる時点t2、及びRATE2と交わる時点t3と
を算定し、上記のt2時点とt3時点とに於いて、圧
力実測値Ｃと制御圧力カーブＢとの比較演算を行
う。第８図の例のように圧力実測カーブＣが
RATE2を越えないときはt2時点では設定圧力の
変更を行わず、t3時点において前回（t1時点）と
同様にして圧力PSだけ設定圧を上昇させるととも
に、前回と同様にしてt4時点、t5時点を算定す
る。このようにして順次に制御圧力設定を上昇さ
せてゆく。 In this example, the same RATE 1 and RATE 2 as described above are set at the control start time t 1 , and the control pressure curve B and RATE 1 are set at this point with the pressure P S increased.
A time point t 2 at which RATE 2 intersects with RATE 2, and a time t 3 at which RATE 2 intersects are calculated, and a comparison calculation is made between the actual pressure measurement value C and the control pressure curve B at the above-mentioned time points t 2 and t 3 . As shown in the example in Figure 8, the actual pressure measurement curve C is
If RATE 2 is not exceeded, the set pressure is not changed at t 2 , and at t 3 the set pressure is increased by pressure P S in the same way as the previous time (t 1 ), and the set pressure is increased by t in the same way as before. Calculate time 4 and time t 5 . In this way, the control pressure setting is increased sequentially.
第９図は蒸気の実測圧力ＣがRATE2を越えた
場合の例である。t7時点においてRATE1と
RATE2とを算定する。t8時点で比較演算したと
き圧力実測値Ｃが制御設定圧力Ｂに比してεn範囲
内に入つていることを検知すると、RATE1を越
えない範囲内で設定圧力をPSだけ上昇させる。詳
しくは、RATE1を内接線とする形状の階段状に
制御圧力設定カーブＢを上昇させる。 Figure 9 shows an example where the measured steam pressure C exceeds RATE 2 . RATE 1 and
Calculate RATE 2 . If it is detected that the actual pressure value C is within the ε n range compared to the control set pressure B when performing a comparison calculation at time t 8 , the set pressure is increased by P S within a range that does not exceed RATE 1 . . Specifically, the control pressure setting curve B is raised in a stepwise manner with RATE 1 as the inscribed line.
前述の第６図の実施例と第９図の変形例との相
異点は次のごとくであり、本質的な差異は無い。
第６図の実施例においてはT1時間の範囲内で、
特に時点を定めないで、圧力実測値Ｃが制御圧力
設定値Ｂに比してεS以内に接近したときに設定圧
力を増加する。第９図の実施例では予め定められ
た時点t8において比較演算を行い、圧力実測値Ｃ
と制御圧力設定値Ｂとの偏差εがεnよりも小さけ
れば設定圧力をPSだけ増加させる。 The differences between the embodiment shown in FIG. 6 and the modification shown in FIG. 9 are as follows, and there is no essential difference.
In the embodiment of FIG. 6, within the range of T 1 hour,
The set pressure is increased when the actual measured pressure value C approaches the control pressure set value B to within ε S without specifying a particular point in time. In the embodiment shown in FIG. 9, a comparison calculation is performed at a predetermined time t8 , and the actual pressure value C
If the deviation ε between the control pressure setting value B and the control pressure setting value B is smaller than ε n , the setting pressure is increased by P S .
上述の第８図、第９図の変形例における作動の
フローチヤートを第１０図に示す。このフローチ
ヤートにおいてステツプ２１、同２２、同２３、
同２５、同２６、同２８および同２９は第７図に
おいて説明したステツプと同様である。第１０図
においては待機時間経過のチエツクを２回に区分
し、ε＜εnのチエツク（ステツプ２３）の前のス
テツプ２４ａにおいてTni経過をチエツクし、未
経過であればステツプ２８、同２９まで直行して
Δt後に繰返し作動する。 FIG. 10 shows a flowchart of the operation in the modification of FIGS. 8 and 9 described above. In this flowchart, steps 21, 22, 23,
Steps 25, 26, 28 and 29 are similar to the steps described in FIG. In FIG. 10, the check for the elapse of the waiting time is divided into two steps, and in step 24a before the check for ε<ε n (step 23), the elapsed time of T ni is checked, and if it has not elapsed, steps 28 and 29 It goes straight to the point and operates repeatedly after Δt.
また、ε＜εnのチエツク（ステツプ２３）の後
のステツプ２４ｂにおいてTsiの経過をチエツク
し、未経過であればΔt後の繰返しに進み、経過
していれば第７図と同様にε＜εs（ステツプ２５）
の比較演算を行う。ステツプ２７′は第７図のス
テツプ２７と類似の作動であるが、本例において
はTni+1と、Tsi+1との２つの待機時間設定を行
う。 Further, in step 24b after checking ε<ε n (step 23), the elapsed time of T si is checked, and if it has not elapsed, the process proceeds to the repetition after Δt, and if it has elapsed, ε <ε s (Step 25)
Performs a comparison operation. Step 27' is a similar operation to step 27 in FIG. 7, but in this example two waiting times, T ni+1 and T si+1 , are set.
以上説明したように、本発明の方法は、制限値
であるRATE1と目標値であるRATE2との両方を
制御の基準数値として用い、原子炉の昇圧操作中
に一定の時間間隔Δtで上記管理基準をそれぞれ
蒸気圧実測値の上昇率とを比較して偏差を算出
し、この偏差値を圧力制御装置に入力せしめて自
動制御を行い、かつ、蒸気実測圧力が制限値を越
えない限り蒸気加減弁の開度を全閉状態に保ちつ
つ蒸気圧力制御を行うことにより、熟練した運転
員による手動操作を要しないで、目標値に近い温
度上昇率となるように自動制御を行い、しかも制
限値を越えることの無い範囲で極力バイパス弁の
開弁を回避することができる。 As explained above, the method of the present invention uses both the limit value, RATE 1 , and the target value, RATE 2 , as reference values for control, and the above values are set at fixed time intervals Δt during the reactor pressurization operation. The deviation is calculated by comparing the control standard with the rate of increase of the actual steam pressure value, and this deviation value is input into the pressure control device to perform automatic control. By controlling the steam pressure while keeping the opening of the regulating valve fully closed, automatic control is performed so that the temperature rise rate is close to the target value without the need for manual operation by skilled operators. Opening of the bypass valve can be avoided as much as possible without exceeding the value.
第１図は従来一般に用いられている原子炉圧力
制御装置の概要的な機構図、第２図および第３図
は同制御方法を示す時間−圧力図表、第４図は本
発明方法を実施するために構成した原子炉圧力制
御装置の一例を示す概要的な機構図、第５図およ
び第６図は本発明方法の実施例を説明するための
時間−圧力図表、第７図は同フローチヤート、第
８図及び第９図は前記と異なる実施例を説明する
ための時間−圧力図表、第１０図は同フローチヤ
ートである。
３……タービンバイパス弁、７……タービン圧
力制御装置、１２……原子炉圧力制御装置。
Figure 1 is a schematic diagram of a conventional reactor pressure control system, Figures 2 and 3 are time-pressure diagrams showing the same control method, and Figure 4 is a diagram showing the method of the present invention. 5 and 6 are time-pressure charts for explaining an embodiment of the method of the present invention, and FIG. 7 is a flowchart of the same. , FIG. 8 and FIG. 9 are time-pressure charts for explaining an embodiment different from the above, and FIG. 10 is a flowchart of the same. 3...Turbine bypass valve, 7...Turbine pressure control device, 12...Reactor pressure control device.
Claims (1)
蒸気加減弁を通して逃がすことにより、前記原子
炉の昇圧時、減圧時の炉内圧力を制御する機構を
備えた原子力発電プラントにおいて、蒸気圧力を
検知することによつて原子炉冷却材の温度変化を
監視し、原子炉圧力容器の熱応力の制約から設計
的に定まる冷却材温度変化率制限値と、運転計画
に基づいて上記の冷却材温度変化率制限値を越え
ない範囲で定められる冷却材温度変化率目標値と
の双方を原子炉圧力制御の基準数値として用い、
かつ、原子炉昇圧操作中の各時点ごとに上記２つ
の基準数値と冷却材温度変化率実測値との偏差値
をそれぞれ演算して圧力制御装置に入力せしめ、
上記の圧力制御装置により、原子炉冷却材の温度
変化率が前記の冷却材温度変化率制限値に達しな
い状態においては蒸気加減弁を全閉位置に保たし
めるように制御することを特徴とする原子炉圧力
制御方法。 ２ 前記の圧力制御装置がタービンバイパス弁を
開弁させるように作動する状態の発生を事前に検
出する手段を備え、この検出手段が作動すると蒸
気温度変化が前記の冷却材温度変化率制限値を越
えない範囲内でタービンバイパス弁の開弁作動を
抑制することを特徴とする特許請求の範囲第１項
に記載の原子炉圧力制御方法。[Scope of Claims] 1. A nuclear power plant equipped with a mechanism for controlling the pressure inside the reactor during pressure increase and pressure reduction by releasing steam generated from the reactor through a steam control valve whose opening degree can be adjusted. At the plant, temperature changes in the reactor coolant are monitored by detecting steam pressure, and based on the coolant temperature change rate limit value determined by design from the thermal stress constraints of the reactor pressure vessel and the operation plan. and the coolant temperature change rate target value, which is determined within a range that does not exceed the above coolant temperature change rate limit value, as the reference value for reactor pressure control,
and calculating the deviation values between the two reference values and the actual measured value of the coolant temperature change rate at each point in time during the reactor pressurization operation, and inputting the calculated values to the pressure control device;
The above pressure control device controls the steam control valve so as to maintain it in the fully closed position when the temperature change rate of the reactor coolant does not reach the coolant temperature change rate limit value. Reactor pressure control method. 2. Means for detecting in advance the occurrence of a condition in which the pressure control device operates to open the turbine bypass valve, and when the detection means is activated, the steam temperature change exceeds the coolant temperature change rate limit value. The reactor pressure control method according to claim 1, characterized in that the opening operation of the turbine bypass valve is suppressed within a range not exceeding the range.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56090767A JPS57206896A (en) | 1981-06-15 | 1981-06-15 | Method of controlling reactor pressure |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56090767A JPS57206896A (en) | 1981-06-15 | 1981-06-15 | Method of controlling reactor pressure |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57206896A JPS57206896A (en) | 1982-12-18 |
| JPH0241719B2 true JPH0241719B2 (en) | 1990-09-19 |
Family
ID=14007752
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56090767A Granted JPS57206896A (en) | 1981-06-15 | 1981-06-15 | Method of controlling reactor pressure |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57206896A (en) |
-
1981
- 1981-06-15 JP JP56090767A patent/JPS57206896A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57206896A (en) | 1982-12-18 |
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