JPH0248880B2 - - Google Patents
Info
- Publication number
- JPH0248880B2 JPH0248880B2 JP56102593A JP10259381A JPH0248880B2 JP H0248880 B2 JPH0248880 B2 JP H0248880B2 JP 56102593 A JP56102593 A JP 56102593A JP 10259381 A JP10259381 A JP 10259381A JP H0248880 B2 JPH0248880 B2 JP H0248880B2
- Authority
- JP
- Japan
- Prior art keywords
- steam
- reheater
- flow rate
- control valve
- heating
- 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
Links
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
- Flow Control (AREA)
Description
【発明の詳細な説明】
本発明はタービンに供給される蒸気の一部を用
いることによつて、高圧タービンからの蒸気を再
熱する再熱器を有する原子力タービンプラントに
関し、特に、再熱器への加熱用蒸気の供給を制御
する原子力タービンプラントの再熱器制御装置に
関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear power turbine plant having a reheater for reheating steam from a high pressure turbine by using a portion of the steam supplied to the turbine, and more particularly to a nuclear power turbine plant having a reheater for reheating steam from a high pressure turbine by using a portion of the steam supplied to the turbine. The present invention relates to a reheater control device for a nuclear turbine plant that controls the supply of heating steam to a nuclear turbine plant.
従来例である特公昭55―38563号公報に示され
た技術は、加熱蒸気の制御弁の出口圧を測定し、
タービンサイクルの圧力との差を取つて加熱蒸気
の制御弁を制御し、急速な温度変化による熱応力
を減少させるものである。 The conventional technology disclosed in Japanese Patent Publication No. 55-38563 measures the outlet pressure of the heating steam control valve,
The difference in pressure from the turbine cycle is taken into account to control the heating steam control valve, thereby reducing thermal stress caused by rapid temperature changes.
これは、再熱器中のサイクル蒸気の温度が負荷
運転中に大きく変動するため、サイクル圧力をと
ることで、再熱器中のサイクル蒸気の温度を代表
させ、再熱器内のサイクル蒸気と加熱蒸気の温度
差を減少させようとするものである。 This is because the temperature of the cycle steam in the reheater fluctuates greatly during load operation, so by taking the cycle pressure, the temperature of the cycle steam in the reheater can be represented, and the cycle steam in the reheater can be compared with the cycle steam in the reheater. The purpose is to reduce the temperature difference between heating steam.
しかしながら、上記従来例の再熱器制御装置に
おいては、高圧タービンからの流量に見合つた加
熱蒸気量の制御が出来ないことから、再熱器で再
熱された蒸気の急激な温度変化を防止することが
出来ないという欠点がある。 However, in the conventional reheater control device described above, it is not possible to control the amount of heated steam commensurate with the flow rate from the high-pressure turbine, so it is difficult to prevent sudden temperature changes in the steam reheated in the reheater. The disadvantage is that it cannot be done.
本発明の目的は、再熱器及び低圧タービンの過
冷却及び大きな温度変化による過大な熱応力の発
生を防止する原子力タービンプラントの再熱器制
御装置を提供することにある。 An object of the present invention is to provide a reheater control device for a nuclear power turbine plant that prevents overcooling of the reheater and low-pressure turbine and the generation of excessive thermal stress due to large temperature changes.
本発明の特徴とするところは、蒸気源から制御
弁を有する配管を通じて加熱蒸気を導く再熱器を
備えた原子力タービンプラントの再熱器制御装置
を、発電機出力を示す検出器と、この検出器より
得られた発電機出力に基づいて再熱器に供給され
る加熱蒸気量を演算する演算装置と、該演算装置
の出力に応じて制御弁の開閉を操作する弁駆動装
置とから構成させ、これによつて常に最適な加熱
蒸気量を再熱器に供給出来るようにしたことにあ
る。 The present invention is characterized in that a reheater control device for a nuclear turbine plant equipped with a reheater that guides heated steam from a steam source through a pipe having a control valve is provided with a detector that indicates the generator output; It consists of a calculation device that calculates the amount of heated steam supplied to the reheater based on the generator output obtained from the generator, and a valve drive device that operates the opening and closing of the control valve according to the output of the calculation device. This makes it possible to always supply the optimum amount of heating steam to the reheater.
次に本発明の一実施例である原子力発電プラン
トの再熱器制御装置を図面を用いて説明する。第
1図は原子力タービンプラントの蒸気サイクルを
示すものである。図において、蒸気発生器1で発
生した蒸気は、主蒸気止め弁2、蒸気加減弁3を
通つて、高圧タービン6に導かれる。主蒸気止め
弁2と蒸気加減弁3は、蒸気タービンローターの
速度検出器4からの速度信号により、目標速度と
なるよう制御装置5により開閉する。高圧タービ
ン6で仕事をし、高圧タービンを駆動した蒸気
は、圧力・温度ともに低下して、蒸気中の湿り分
も増加しているので、湿分分離器7で湿分を分離
した後、再熱器8に導かれる。再熱器8の加熱源
は、蒸気発生器1で発生した蒸気を用い、主蒸気
止め弁2の上流側から分岐する。再熱器8で加熱
蒸気と熱交換し、温度上昇した蒸気は、再熱蒸気
と呼ばれ、低圧タービン9に導かれる。高圧ター
ビン6と低圧タービン9は発電機10に結合さ
れ、発電機10を駆動する。低圧タービン9内で
仕事をし、駆動動力を発生した蒸気は、復水器1
1へ導かれ、凝結して水となつて、給水加熱器1
2へ導かれる。この給水加熱器12には、再熱器
で熱交換した後の加熱蒸気も導かれ、復水器から
の水を加熱する。加熱された水は、蒸気発生器1
へ供給される。 Next, a reheater control device for a nuclear power plant, which is an embodiment of the present invention, will be described with reference to the drawings. FIG. 1 shows the steam cycle of a nuclear turbine plant. In the figure, steam generated in a steam generator 1 is guided to a high-pressure turbine 6 through a main steam stop valve 2 and a steam control valve 3. The main steam stop valve 2 and the steam control valve 3 are opened and closed by the control device 5 so as to reach a target speed based on a speed signal from a speed detector 4 of the steam turbine rotor. The steam that does work in the high-pressure turbine 6 and drives the high-pressure turbine has a lower pressure and temperature and an increased moisture content, so after separating the moisture in the moisture separator 7, the steam is recycled. It is guided to the heating device 8. The heat source of the reheater 8 uses steam generated by the steam generator 1 and branches from the upstream side of the main steam stop valve 2. The steam whose temperature has been increased by exchanging heat with the heated steam in the reheater 8 is called reheated steam, and is led to the low pressure turbine 9. High pressure turbine 6 and low pressure turbine 9 are coupled to generator 10 and drive generator 10 . The steam that has done work in the low pressure turbine 9 and generated driving power is transferred to the condenser 1
1, condenses into water, and feeds water heater 1.
Leads to 2. Heated steam after heat exchange with the reheater is also introduced into the feedwater heater 12, and heats the water from the condenser. The heated water is transferred to steam generator 1
supplied to
再熱器8に導かれる加熱蒸気の配管には、加熱
蒸気制御弁14が設置され、制御装置16及び駆
動装置15により開閉制御されるようになつてい
る。 A heating steam control valve 14 is installed in the heating steam piping led to the reheater 8, and its opening and closing are controlled by a control device 16 and a drive device 15.
つまり、発電機出力(検出器17)の信号L
(第2図参照)が制御装置16に入力し、弁開度
信号となつて制御弁駆動装置15にに送られ、加
熱蒸気制御弁14を開閉することにより加熱蒸気
量が制御される。 In other words, the signal L of the generator output (detector 17)
(see FIG. 2) is input to the control device 16, which is sent as a valve opening signal to the control valve drive device 15, and the amount of heated steam is controlled by opening and closing the heated steam control valve 14.
発電機出力信号Lはタービン負荷とほぼ等し
く、タービン蒸気流量に比例する。低負荷では、
タービン蒸気流量は少なく、したがつて再熱器加
熱蒸気量も少なくてよい。負荷が減少したとき
に、加熱蒸気量をそのままにすると、再熱器8の
内部についてみると、負荷減少と共に、高圧ター
ビン6から出る蒸気温度、即ち再熱器8へ流入す
る被加熱側の温度は下り側向になり、加熱側蒸気
と被加熱側蒸気温度差は大きくなり、再熱器内部
に応力が発生する。したがつて負荷が減少すれ
ば、加熱蒸気制御弁14の開度を絞り、弁の出口
圧を下げることによつて加熱蒸気の温度を下げる
ようにする。また、低圧タービン9のローターの
熱応力についてみると、低圧タービン9の入口蒸
気温度、即ち、再熱器出口蒸気温度の変化が問題
となる。負荷が大きく減少し、高圧タービン6か
らの蒸気流量が減少しても、加熱側蒸気流量をそ
のままとすると、被加熱側流量が減少するが、加
熱側流量はそのままであるから、高圧タービンか
ら出る蒸気温度が若干減少しても、再熱器出口蒸
気温度は加熱側蒸気温度の方に近づき、温度は上
り傾向となり、低圧タービンローターにとつては
応力発生源となることがある。これらのことか
ら、再熱器8への加熱蒸気量はタービン負荷に応
じて増減することが望ましい。また、負荷遮断
時、タービンの蒸気制御弁3は、発電機負荷の急
減信号(図示せず)により、急閉して蒸気を絞
る。このとき、タービン流量が急減するから、再
熱器加熱蒸気も急減させ、被加熱側蒸気なしに加
熱蒸気が流れることがないようにすることが望ま
しく、これは発電機出力を検出して加熱蒸気制御
弁14を開閉制御することが達成できる。 The generator output signal L is approximately equal to the turbine load and is proportional to the turbine steam flow rate. At low loads,
The turbine steam flow rate is small, so the amount of reheater heating steam may also be small. If the amount of heating steam is left unchanged when the load decreases, looking inside the reheater 8, as the load decreases, the temperature of the steam coming out of the high-pressure turbine 6, that is, the temperature of the heated side flowing into the reheater 8, will decrease. is in a downward direction, the temperature difference between the heating side steam and the heated side steam becomes large, and stress is generated inside the reheater. Therefore, when the load decreases, the opening degree of the heating steam control valve 14 is reduced to lower the outlet pressure of the valve, thereby lowering the temperature of the heating steam. Regarding thermal stress in the rotor of the low-pressure turbine 9, changes in the inlet steam temperature of the low-pressure turbine 9, that is, the reheater outlet steam temperature, pose a problem. Even if the load decreases significantly and the steam flow rate from the high-pressure turbine 6 decreases, if the heating side steam flow rate remains the same, the heated side flow rate will decrease, but the heating side flow rate will remain the same, so steam will not flow out from the high-pressure turbine. Even if the steam temperature decreases slightly, the reheater outlet steam temperature approaches the heating side steam temperature, and the temperature tends to rise, which may become a source of stress for the low-pressure turbine rotor. For these reasons, it is desirable that the amount of heating steam supplied to the reheater 8 is increased or decreased depending on the turbine load. Further, when the load is cut off, the steam control valve 3 of the turbine is suddenly closed to throttle the steam in response to a signal (not shown) for a sudden decrease in the generator load. At this time, since the turbine flow rate suddenly decreases, it is desirable to rapidly decrease the reheater heating steam so that the heating steam does not flow without steam on the heated side.This is done by detecting the generator output and Controlling the opening and closing of the control valve 14 can be achieved.
第2図は、前述の再熱器の制御機構をブロツク
図で示したものである。検出された発電機出力の
信号Lは、加熱蒸気制御弁14の制御器内で次の
演算により加熱蒸気制御弁14の開閉信号Vに変
換される。発電機出力信号Lには適当なバイアス
信号Bがバイアス設定器16aによりかけられ
る。これは、併入後の初負荷(5%程度)など、
起動後の低負荷では、再熱器8の内部及び低圧タ
ービン9のローター共温度が低いため、再熱器内
に加熱蒸気を通すと大きな温度差が発生するの
で、それを防止するため、一定負荷以下では加熱
蒸気の流入を止めるためのものである。次にバイ
アス後の発電機出力信号に対し、加熱蒸気量f1を
関数発生器16bで求める。関数発生器16bの
例は、バイアスをさし引いた後の発電機出力信号
と、加減弁流量信号を比例されるもので、第3図
に示す。次に、加熱蒸気制御弁14の弁開度と弁
流量の特性から関数発生器16cを用いて加熱蒸
気量信号f1から、加熱蒸気制御弁開度信号Vを出
す。関数発生器16cの例を第4図に示す。この
弁開度信号が、制御弁駆動装置15に送られ、制
御弁14が要求開度まで開閉制御されることにな
る。 FIG. 2 is a block diagram showing the control mechanism of the reheater described above. The detected generator output signal L is converted into an opening/closing signal V for the heating steam control valve 14 by the following calculation within the controller of the heating steam control valve 14. An appropriate bias signal B is applied to the generator output signal L by a bias setter 16a. This includes the initial load after joining (about 5%), etc.
When the load is low after startup, the internal temperature of the reheater 8 and the rotor of the low-pressure turbine 9 are both low, so a large temperature difference will occur when heated steam is passed through the reheater. This is to stop the inflow of heating steam when the load is below. Next, the amount of heated steam f 1 is determined by the function generator 16b based on the biased generator output signal. An example of the function generator 16b is shown in FIG. 3, in which the generator output signal after the bias is subtracted is proportional to the control valve flow signal. Next, based on the characteristics of the valve opening degree and valve flow rate of the heating steam control valve 14, a heating steam control valve opening degree signal V is generated from the heating steam amount signal f1 using the function generator 16c. An example of the function generator 16c is shown in FIG. This valve opening degree signal is sent to the control valve driving device 15, and the control valve 14 is controlled to open and close to the required opening degree.
次に本発明の他の実施例である原子力タービン
プラントの再熱器制御装置を説明する。 Next, a reheater control device for a nuclear turbine plant, which is another embodiment of the present invention, will be described.
発電機出力に加え、加熱蒸気制御弁14の後流
側の蒸気圧力を検出して、加熱蒸気制御弁14の
開度を制御することも、本発明の一つの実施例で
ある。この実施例を第5図に示す。第1図との相
違部分のみを説明すると、加熱蒸気制御弁14の
後流側の蒸気圧力検出器18にて蒸気圧力Pを検
出し、これから制御装置16にて加熱蒸気流量を
演算して弁開度を補正するようにしたものであ
る。第6図にその制御機構のブロツク図を示す。
第6図の例では、第5図のものに加えて制御弁駆
動装置15から実際の弁開度信号V0を導き、蒸
気圧力検出器18から導かれたことによつて流量
演算器16dにて実流量信号f0を演算し、この信
号f0と関数発生器16bで演算した加熱蒸気の流
量信号f1との偏差をとり、係数Kを乗じて、流量
補正を行ない、これにより、制御弁4の弁開度を
補正するようにしたものである。 In one embodiment of the present invention, in addition to the generator output, the steam pressure on the downstream side of the heating steam control valve 14 is detected to control the opening degree of the heating steam control valve 14. This embodiment is shown in FIG. To explain only the differences from FIG. 1, the steam pressure detector 18 on the downstream side of the heated steam control valve 14 detects the steam pressure P, and from this, the control device 16 calculates the heated steam flow rate to control the valve. The opening degree is corrected. FIG. 6 shows a block diagram of the control mechanism.
In the example shown in FIG . 6, in addition to the signal shown in FIG. to calculate the actual flow rate signal f 0 , take the deviation between this signal f 0 and the heating steam flow rate signal f 1 calculated by the function generator 16b, and multiply by a coefficient K to correct the flow rate. The valve opening degree of the valve 4 is corrected.
また、実流量信号f0から関数発生器16cにて
弁開度信号Vを演算し加熱蒸気流量信号f1から求
めた弁開度信号との偏差をとつて制御弁14の開
度を補正するようにしても良い。 Further, the function generator 16c calculates the valve opening signal V from the actual flow rate signal f0 , and corrects the opening of the control valve 14 by taking the deviation from the valve opening signal obtained from the heated steam flow rate signal f1 . You can do it like this.
本発明によれば、再熱器及び低圧タービンの過
冷却及び過大な熱応力の発生を防止しうる原子力
タービンプラントの再熱器制御装置を実現出来る
という効果を奏する。 According to the present invention, it is possible to realize a reheater control device for a nuclear turbine plant that can prevent overcooling of the reheater and the low-pressure turbine and generation of excessive thermal stress.
第1図は本発明の一実施例である原子力タービ
ンプラントの制御装置を表わす系統図、第2図は
第1図の制御装置の詳細を示すブロク図、第3図
は第2図のブロツク図に示す加熱蒸気流量を演算
する関数発生器の特性図、第4図は第2図のブロ
ツク図に示す制御弁開度を演算する関数発生器の
特性図、第5図は本発明の他の実施例である原子
力タービンプラントの制御装置を表わす系統図、
第6図は第5図の制御装置の詳細を示すブロツク
図である。
1…蒸気発生器、2…主蒸気止め弁、3…蒸気
加減弁、4…速度検出器、5…制御装置、6…高
圧タービン、7…湿分分離器、8…再熱器、9…
低圧タービン、10…発電機、14…加熱蒸気制
御弁、15…駆動装置、16…制御装置、16a
…バイアス設定器、16b,16c…関数発生
器、16d…流量演算器、17…負荷検出器、1
8…圧力検出器。
Fig. 1 is a system diagram showing a control device for a nuclear turbine plant which is an embodiment of the present invention, Fig. 2 is a block diagram showing details of the control device in Fig. 1, and Fig. 3 is a block diagram of Fig. 2. 4 is a characteristic diagram of a function generator that calculates the flow rate of heated steam shown in FIG. 4, a characteristic diagram of a function generator that calculates the control valve opening shown in the block diagram of FIG. 2, and FIG. A system diagram showing a control device of a nuclear turbine plant as an example,
FIG. 6 is a block diagram showing details of the control device of FIG. 5. DESCRIPTION OF SYMBOLS 1...Steam generator, 2...Main steam stop valve, 3...Steam control valve, 4...Speed detector, 5...Control device, 6...High pressure turbine, 7...Moisture separator, 8...Reheater, 9...
Low pressure turbine, 10... Generator, 14... Heating steam control valve, 15... Drive device, 16... Control device, 16a
...Bias setting device, 16b, 16c...Function generator, 16d...Flow rate calculator, 17...Load detector, 1
8...Pressure detector.
Claims (1)
れ、該加熱蒸気により主蒸気を加熱する再熱器を
備えた原子力タービンプラントの再熱器制御装置
において、 タービンプラントの発電機出力を検出する出力
検出器と、 該検出器により得られた信号に基づき、発電機
出力に応じた再熱器の加熱蒸気流量を演算する演
算装置と、 該演算装置の出力に応じて前記制御弁を操作す
る弁駆動装置と、 を備えたことを特徴とする原子力タービンプラン
トの再熱器制御装置。 2 再熱器を得た加熱蒸気の状態量を検出する検
出装置を備え、この検出装置の検出信号と発電機
出力信号とに基づいて前記演算装置により加熱蒸
気流量を演算するようにしたことを特徴とする特
許請求の範囲第1項記載の原子力タービンプラン
トの再熱器制御装置。[Scope of Claims] 1. A reheater control device for a nuclear turbine plant equipped with a reheater in which heated steam is guided from a steam source via a control valve and which heats main steam with the heated steam, comprising: an output detector that detects the generator output; a calculation device that calculates the heating steam flow rate of the reheater according to the generator output based on the signal obtained by the detector; and a calculation device that calculates the heating steam flow rate of the reheater according to the generator output; A reheater control device for a nuclear turbine plant, comprising: a valve drive device that operates the control valve; 2. A detection device for detecting the state quantity of the heated steam obtained from the reheater is provided, and the heating steam flow rate is calculated by the calculation device based on the detection signal of the detection device and the generator output signal. A reheater control device for a nuclear turbine plant according to claim 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56102593A JPS582795A (en) | 1981-06-30 | 1981-06-30 | Nuclear turbine plant reheater control device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56102593A JPS582795A (en) | 1981-06-30 | 1981-06-30 | Nuclear turbine plant reheater control device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS582795A JPS582795A (en) | 1983-01-08 |
| JPH0248880B2 true JPH0248880B2 (en) | 1990-10-26 |
Family
ID=14331529
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56102593A Granted JPS582795A (en) | 1981-06-30 | 1981-06-30 | Nuclear turbine plant reheater control device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS582795A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0624698B2 (en) * | 1985-08-06 | 1994-04-06 | 新東工業株式会社 | Steel plate surface treatment method |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4150546A (en) * | 1976-12-03 | 1979-04-24 | General Electric Company | Method and apparatus for load following with a single-cycle boiling moderator-coolant nuclear reactor |
-
1981
- 1981-06-30 JP JP56102593A patent/JPS582795A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS582795A (en) | 1983-01-08 |
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