JPS6038507A - Controller for heating steam for feedwater heater - Google Patents

Controller for heating steam for feedwater heater

Info

Publication number
JPS6038507A
JPS6038507A JP58146554A JP14655483A JPS6038507A JP S6038507 A JPS6038507 A JP S6038507A JP 58146554 A JP58146554 A JP 58146554A JP 14655483 A JP14655483 A JP 14655483A JP S6038507 A JPS6038507 A JP S6038507A
Authority
JP
Japan
Prior art keywords
steam
feed water
pressure
water heater
turbine
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP58146554A
Other languages
Japanese (ja)
Inventor
政志 中本
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to JP58146554A priority Critical patent/JPS6038507A/en
Publication of JPS6038507A publication Critical patent/JPS6038507A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Control Of Steam Boilers And Waste-Gas Boilers (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 「発明の技術分野」 本発明は例えば原子力発電プラントの原子炉に入る給水
温度を調整する給水加熱器の加熱蒸気制御装置に関する
DETAILED DESCRIPTION OF THE INVENTION TECHNICAL FIELD OF THE INVENTION The present invention relates to a heating steam control device for a feed water heater that adjusts the temperature of feed water entering a reactor of a nuclear power plant, for example.

[発明の技術的前頭とその問題点」 原子力発電プラントでは、プラントの熱IJi’r′の
向上、蒸気発生器(原子炉)での安定な蒸気の発生のた
めに、復水器より原子炉までの給水ライン中に設(プら
れた複数の給水加熱器で給水とタービン抽気の熱交換を
行わせて給水温度を上Rさけ−(いる。原子力発電プラ
ントの給水加熱器(−は、−この加熱蒸気であるタービ
ン抽気がほぼ飽和状態の蒸気であることから、加熱蒸気
の温度は給水加熱器の器内圧力のみの関数と考えてよい
。ま1.:給水加熱器内での熱交換の大部分が蒸気の凝
縮熱によるものであるため、給水加熱器の加熱側のff
+A I(Li 1.L、その器内圧力で決る蒸気の温
度で一様に41つでいる。このために給水の給水加熱器
出し1でのfiilf IFJは、給水加熱器の器内圧
により操作でき、本1内月力を高くするとより高温の給
水温度、器内1f力を低くするとより低温の給水温度が
得られる。
[Technical Overview of the Invention and Its Problems] In nuclear power plants, in order to improve the heat IJi'r' of the plant and to generate stable steam in the steam generator (reactor), it is necessary to use the reactor rather than the condenser. In order to increase the temperature of the feed water by exchanging heat between the feed water and the turbine bleed air, multiple feed water heaters installed in the water supply line up to Since the turbine extracted air, which is this heating steam, is almost saturated steam, the temperature of the heating steam can be considered to be a function only of the internal pressure of the feedwater heater. 1.: Heat exchange within the feedwater heater Most of the ff on the heating side of the feed water heater is due to the heat of condensation of the steam.
+A I (Li 1.L, 41 is uniformly determined by the steam temperature determined by the internal pressure of the vessel.For this reason, the fiilf IFJ at the feed water heater outlet 1 of the feed water is operated by the internal pressure of the feed water heater. By increasing the power inside the vessel, a higher temperature can be obtained, and by lowering the power inside the vessel, a lower temperature can be obtained.

このような特性から発電プラントの給水加熱2:)は、
複数台のものが復水器から原子炉までの給水ラインにも
設けられ、それらに入れる抽気のIF力を順次高くして
おくことにより、給水の温度を段階的に上昇さけている
。給水温度の制御装置は、原子炉に入れる給水の温度を
ある範囲内に保つために設【プられるもので、その従来
例による構成はd3 J3むね第1図のように4111
成されている。
Due to these characteristics, feed water heating in power plants2:) is
Multiple units are also installed in the water supply line from the condenser to the reactor, and by increasing the IF power of the bleed air introduced into them one after another, the temperature of the supply water is gradually raised. The feed water temperature control device is installed to maintain the temperature of the feed water entering the reactor within a certain range, and its conventional configuration is 4111 as shown in Figure 1.
has been completed.

づなわら、第1図において、原子炉の蒸気発生器13か
ら出/’−蒸気1は、蒸気加減弁2を通って蒸気タービ
ン3へ尋かれたのち、逆止弁12bを通って給水加熱器
4に入る。給水器4を出た給水は、原子炉13に送られ
るが、炉に入る給水の温度は、原子炉での蒸発量に対し
て第2図の斜線部で示寸ような範囲にあることが要求さ
れる。給水加熱器4での給水の加熱は、主としてタービ
ン3の抽気によって行われる。タービン抽気の圧力は、
タービンの加減弁2、タービン3を通る蒸気流量によっ
て決まる。またこの蒸気間は、はぼ原子炉の熱光fid
ど等しい。ざらに上Jのように給水の温度は、加熱蒸気
の圧力によって決まるので、タービン抽気のみで給水を
加熱J−ると、給水加熱器4の出力給水温度は、第2図
の特性PQRのような線上を動ぎ、蒸発量の少ない所で
は要求される湿度以下になる。
In FIG. 1, steam 1 from the steam generator 13 of the nuclear reactor passes through the steam control valve 2 to the steam turbine 3, and then passes through the check valve 12b to the feed water heater. Enter 4. The feed water that exits the water supply device 4 is sent to the reactor 13, but the temperature of the feed water entering the reactor is likely to be within the range shown by the shaded area in Figure 2 relative to the amount of evaporation in the reactor. required. The feed water is heated in the feed water heater 4 mainly by extraction air from the turbine 3 . The turbine bleed air pressure is
It is determined by the steam flow rate passing through the turbine control valve 2 and the turbine 3. Also, between this steam is the thermal light fid of the Habo nuclear reactor.
Equal. Roughly speaking, the temperature of the feed water is determined by the pressure of the heating steam, so if the feed water is heated only by the turbine extraction air, the output water temperature of the feed water heater 4 will be as shown in the characteristic PQR in Figure 2. In areas where the amount of evaporation is small, the humidity will be below the required level.

このために給水加熱器4に入るクーヒン抽気j1力を測
定しておいて、タービン抽気圧力が低下し、給水加熱器
4の器内圧力が第2図のQ +A+に相当りる圧ノjま
で低1”−!Iるど、圧力スイッチ55にJす15:号
を発生さばて調節弁6を間し、B 2品、I::+ I
fの1蒸気を逆止弁12aを介して給水加熱iiS 4
にン」大して給水温度を上昇さぼる。逆にタービン抽気
1j力が上昇しQ点に相当づる値以上になると、圧力ス
イッチ45により信号を発生さUて調nD弁0を閉づる
。このような調節弁6の開閉方法は、本説明のような抽
気圧力を測定し圧力スイッチ(゛開閉づる方法、あるい
は給水加熱器4の器内圧力+ ;III定し圧)Jスイ
ッチで開閉する方法、あるいは給水加熱器4の給水出口
温度を測定し渇庶スーrツf −(開閉Jる方法のいず
れにJ3いても同様な)幾能を宋ず。
For this purpose, the Kuchin bleed air j1 force entering the feed water heater 4 is measured, and the turbine bleed air pressure decreases until the internal pressure of the feed water heater 4 reaches a pressure no. j corresponding to Q + A + in Fig. 2. Low 1"-!I, generate JS15: to pressure switch 55, close control valve 6, B2 products, I::+I
1 steam of f through the check valve 12a to heat the feed water iiS 4
The temperature of the water supply will be significantly increased. Conversely, when the turbine extraction force 1j increases and exceeds the value corresponding to the Q point, the pressure switch 45 generates a signal and closes the control valve 0. The method of opening and closing such a control valve 6 is to measure the bleed air pressure as described in this explanation and open and close it with a pressure switch ('opening/closing method, or internal pressure of the feed water heater 4 +; III constant pressure) J switch. method, or measure the water supply outlet temperature of the water supply heater 4 and determine the function of the water supply (same regardless of whether it is opened or closed).

このようないずれの方法においても、調1iii弁ぐ)
には全開、または全開の信号が入るので、AI:l 1
iii Ji’6はそれ自身の固有の速度で全開から全
開、全開から全開へと動作する。このように調節弁6が
働くことによって、主蒸気ラインから多聞の蒸気が給水
加熱器4に流れるため、主蒸気ラインの圧力を低下ざl
るように蝕く。通常の原子カプラントではタービン3の
加減弁2は主蒸気ラインの圧力を一定とするように制御
されているので、このように主蒸気ラインから給水加熱
器4に蒸気を流すと、加減弁2が閉としてタービン3に
流す蒸気mを減じ、主蒸気ラインの圧力を一定とげるよ
うに動くが、この時タービン3に流れる蒸気量が減少す
るためにタービンの出力が低下する。その後、原子炉側
で出力を増加させ、蒸発量を増すことによってタービン
3の加減弁2は元の状態まで間し、出力を元の状態まで
戻すことができるが、調節弁6の開閉速度が早い時には
、原子炉側の制御の遅れによってタービンの出力低下が
大ぎくなる。
In any of these methods,
Since the full open or full open signal is input to the , AI:l 1
iii Ji'6 moves from full to full and from full to full at its own inherent speed. By operating the control valve 6 in this way, a large amount of steam flows from the main steam line to the feed water heater 4, which reduces the pressure in the main steam line.
It eats away at you. In a normal nuclear coupler plant, the regulator valve 2 of the turbine 3 is controlled to keep the pressure in the main steam line constant, so when steam flows from the main steam line to the feedwater heater 4 in this way, the regulator valve 2 When the main steam line is closed, the steam m flowing to the turbine 3 is reduced and the pressure in the main steam line is kept constant, but at this time, the amount of steam flowing to the turbine 3 is reduced, so the output of the turbine is reduced. After that, by increasing the output on the reactor side and increasing the amount of evaporation, the regulating valve 2 of the turbine 3 returns to its original state, and the output can be returned to its original state, but the opening/closing speed of the regulating valve 6 is If it is too early, the turbine output will drop significantly due to delays in reactor-side control.

このように調節弁6の早い開閉は、原子力発電プラント
の出力に外乱を与える。また主蒸気ラインの圧力が低下
すると、原子炉内の圧力も低下するので、炉内にある飽
和水が圧力低下によつC81:騰する。このため炉水位
、核反応に外乱を!jえることになる。
In this way, the rapid opening and closing of the control valve 6 causes a disturbance to the output of the nuclear power plant. Furthermore, when the pressure in the main steam line decreases, the pressure in the reactor also decreases, and the saturated water in the reactor rises due to the pressure decrease. This causes disturbance to the reactor water level and nuclear reaction! I'm going to be able to do it.

[発明の目的] 本発明の目的は、給水温度の制御を11い、かつタービ
ン出力、原子炉制御への外乱を少くりる給水加熱器の加
熱蒸気制御装置を供給りるにある、。
[Object of the Invention] An object of the present invention is to provide a heating steam control device for a feed water heater that can control the feed water temperature and reduce disturbances to turbine output and reactor control.

[発明の概要] 本発明による給水加熱器の加熱蒸気制御、)4 ’rj
は、給水加熱器に入る抽気蒸気の圧力を検知りる月力検
知器、この検出圧ノjと設定値どの比較によ−)(主蒸
気を給水加熱器へ流す蒸気を制御Jる調1tii弁に全
開信号又は全閉信号を発Jる比較器ど、この比較器から
調節弁に送る信号を一定率どりるVk、 If;率制限
器どの組合わせににす、給水加熱器l\の加熱蒸気を抽
気蒸気から主蒸気へ徐々に切り変えるようにしたことを
特徴どする。
[Summary of the invention] Heating steam control of a feed water heater according to the present invention, )4'rj
is a monthly power detector that detects the pressure of bleed steam entering the feedwater heater, and how does this detected pressure compare with the set value? A comparator that sends a fully open signal or a fully closed signal to a valve, and a signal sent from this comparator to a control valve at a constant rate Vk, If; It is characterized in that the heating steam is gradually switched from extraction steam to main steam.

[発明の実施例] 以下本発明を第1図、第3図および425図に示す実施
例について説明する。本発明におい06用する発電プラ
ン1−は、第1図に示す構成と同様であり、本発明では
、このような発電プラントにおける給水加熱器4に対す
る加熱蒸気を抽気蒸気から主蒸気へ切換えるのに徐々に
f)わぜる制御装置20をイ」設したものである。
[Embodiments of the Invention] The present invention will be described below with reference to embodiments shown in FIGS. 1, 3, and 425. The power generation plan 1- used in the present invention is similar to the configuration shown in FIG. A control device 20 that gradually changes f) is installed.

J−なりら、この制御装置は、第3図に示すように圧ノ
j検出器7、比較検出器8、変化率制限器9および電/
空敲換器10を備え、電/空変換器10の空気信号によ
って主蒸気を給水加熱器へ尋く調節弁6を制御するよう
に(111成されている。
As shown in FIG.
An air exchanger 10 is provided, and the air signal from the electric/air converter 10 is used to control the control valve 6 for supplying main steam to the feed water heater (111).

そして圧力検出器7は蒸気タービン3から給水加熱器4
へ導く抽気蒸気の圧力Pを検出するものである。比較検
出器8は、圧力検出器7の検出圧力Pと予め設定してい
る開設定値poおよび閉設定値1)Cどを比較し、検出
圧力l〕が閉設定値pcより高い時(P>Pc )には
、調節弁6を全開とする信号を出ノJし、検出圧力Pが
開設定値poより低い時(P<PO)には、調節弁6を
全開とすぐ る信号を出力し、そして圧力の設定値は、
po<Pcとしてその出力信号はヒステリシス性を持つ
ている。変化率ml限器9は比較検出器8の出力18号
を入力し、この入力信号の変化率を制限して徐々に変化
ザる出力を発する。電/閑変換器10は変化率制限器9
の電気(8号を空気信号に変換しく調節弁6に空気信号
を発するものである。
The pressure detector 7 is connected to the feed water heater 4 from the steam turbine 3.
This is to detect the pressure P of the extracted steam that is led to. The comparison detector 8 compares the detected pressure P of the pressure detector 7 with a preset open set value po and a closed set value 1) C, and when the detected pressure l] is higher than the closed set value pc (P> Pc) outputs a signal to fully open the control valve 6, and when the detected pressure P is lower than the opening set value po (P<PO), outputs a signal to fully open the control valve 6; And the pressure setting value is
As po<Pc, the output signal has hysteresis. The rate of change ml limiter 9 inputs the output No. 18 of the comparison detector 8, limits the rate of change of this input signal, and produces an output that changes gradually. The electric/quiet converter 10 is a rate of change limiter 9
It converts the electricity (No. 8) into an air signal and issues an air signal to the control valve 6.

本発明の制御装置20はこのように4117成さ1して
いるので、タービン3を流れる蒸気量が多く i;Lっ
て抽気圧力Pが開設定値Poよりも11)1いP〉10
時には調節弁6は閉しており、給水加熱iVi 4 +
L、 IJシタ−ン3から抽気蒸気が送られて給水を加
!;!! ’J’る。タービン3を流れる蒸気量が減少
し、抽気1f力Pが低下してlji設定俯Po以下にな
ると、比較検出器8は調節弁6を全開どJる信号を出ノ
J する、。
Since the control device 20 of the present invention is configured in this manner, the amount of steam flowing through the turbine 3 is large.
Sometimes the control valve 6 is closed and the feed water heating iVi 4 +
Bleed steam is sent from L, IJ Sita-3 and feed water is added! ;! ! 'J'ru. When the amount of steam flowing through the turbine 3 decreases and the extraction force P decreases to below the lji setting pressure Po, the comparison detector 8 outputs a signal to fully open the control valve 6.

変化率制限器9は入力信号に対し−(出力信′i:3を
ある変化率以内で変えるので、出力(rlj号は調節弁
0を全開とづる値から徐々に一定率で増加して行く、。
The rate of change limiter 9 changes the input signal -(output signal 'i:3) within a certain rate of change, so the output (rlj) gradually increases at a constant rate from the value when the control valve 0 is fully open. ,.

それに伴って調節弁6も一定率で間覆る。調B11弁6
が間すると、主蒸気ラインがら昌)!Ii!どj、圧の
〃1気が給水加熱器4に送られるが、この流量は調11
ijjr6の開厄によって決まるので、主蒸気ラインが
らの給水加熱器4への加熱蒸気の流量の増加もほぼ一定
率で徐々に増加する。
Accordingly, the control valve 6 also closes at a constant rate. Key B11 valve 6
After that, the main steam line is closed)! Ii! 1 air is sent to the feed water heater 4, but the flow rate is controlled by the regulator 11.
Since it is determined by the opening of ijjr6, the increase in the flow rate of heating steam from the main steam line to the feed water heater 4 also increases gradually at a substantially constant rate.

タービン3を流れる蒸気mが増加してくると、抽気圧力
[〕も高くなって来る。圧力Pが閉設定値Pcよりし高
く、P>Pcとなると比較検出器8は調節弁6を全開と
する信号を出力Jるが、この信号は変化率制限器9によ
って一定率で弁を閉する信号に変えられる。従って調節
弁6は徐々に一定率で閉し、これに伴って主蒸気からの
加熱蒸気も徐々に減少し、給水加熱器4の加熱蒸気は抽
気蒸気に切替わる。
As the steam m flowing through the turbine 3 increases, the extraction pressure [ ] also increases. When the pressure P is higher than the closing set value Pc and P>Pc, the comparison detector 8 outputs a signal to fully open the control valve 6, but this signal is controlled by the rate of change limiter 9 to close the valve at a constant rate. The signal can be changed to Therefore, the control valve 6 gradually closes at a constant rate, and accordingly, the heating steam from the main steam also gradually decreases, and the heating steam of the feed water heater 4 is switched to extraction steam.

このように制御装置が動作するので、給水加熱器4に流
入Jる主蒸気の流量の変化も変化率制限器9で定めた変
化率で変化する。このために変化率制限器9の変化率の
設定を主蒸気流量の変動に対して、タービン3の制御系
および原子炉の制御系が追従するように定めることによ
って、タービンの出力への外乱および原子炉系への影響
を少くすることができる。
Since the control device operates in this manner, the flow rate of the main steam flowing into the feedwater heater 4 also changes at the rate of change determined by the rate of change limiter 9. For this purpose, by setting the rate of change of the rate of change limiter 9 so that the control system of the turbine 3 and the control system of the reactor follow fluctuations in the main steam flow rate, disturbances to the output of the turbine and The impact on the nuclear reactor system can be reduced.

本発明によれば、このように制御が行われるので原子炉
への給水の温度を要求された(iGに自動的にすること
と同時に、原子炉系およびターじン出)jへの影響を少
くすることができる。
According to the present invention, since the control is performed in this way, the temperature of the feed water to the reactor is automatically controlled (at the same time as the temperature of the water supplied to the reactor is automatically controlled, and at the same time, the influence on the reactor system and the turbine exhaust) is reduced. It can be done less.

本発明の他の実施例として、急速に給水ffuf la
か低下づ°ることに対する保護機能を持つものを第11
図によって説明Jる。この実施例の制御装置20は第3
図の構成に加えて、比較検出器8の間設定(直POより
も低いある値Ptl・で変化率制限器90入)jトラッ
キング機能(入力信号をそのまま出力する機能)を作動
させる信号を出ツノJる圧力11へ[・検知器11を設
けでいる。
As another embodiment of the invention, the rapid water supply ffuf la
Items that have a protective function against deterioration are classified as No. 11.
Explain with diagrams. The control device 20 of this embodiment is the third
In addition to the configuration shown in the figure, the comparison detector 8 is set (change rate limiter 90 is entered at a certain value Ptl lower than the direct PO) and a signal is output that activates the tracking function (a function that outputs the input signal as it is). A detector 11 is provided to detect the pressure 11 of the horn.

この制御ll装置20は、°このように構成さ1′と(
いるので、タービン負荷い1ill:lIのJ、うなタ
ーヒン仙気圧が急速に低下するような揚台には、Jj、
す“唱・化率制限器9により一定率で調節弁6を聞どり
ろが、圧力が低下し圧力低下検知器11でl:) < 
1) [rとなると、低下検知器11からの信号により
今生率制限器9を入力I・ラッキングとし、調RO弁G
に全開信号を出し、調節弁6を@速量とりる、。
This control device 20 is configured as follows: 1' and (
Therefore, the turbine load is J of 1ill:lI, Jj,
Although the control valve 6 is controlled at a constant rate by the rate limiter 9, the pressure decreases and the pressure drop detector 11 detects l:)<
1) When [r] is reached, the current rate limiter 9 is set to input I/racking by the signal from the drop detector 11, and the regulating RO valve G is turned on.
Send a full open signal to , and set control valve 6 to @speed.

このように制御が動作するので、抽気jf力のKr下が
ゆるやかな通常のブランl−運用の場合には、変化率制
限器9による一定率で調節弁6が開閉し、給水湿度を要
求範囲内とりる。さらにタービン負荷の降下が急で抽気
圧力の降下が早い時には調節フr 6を怠170ざじる
ので、給水加熱器4への加熱蒸気を2速に主蒸気に切替
えることができ、給水加熱器4の加熱蒸気を?if[(
呆覆ることができる。
Since the control operates in this way, in the case of normal bran l- operation where the Kr of the bleed air jf force is gradually lowered, the control valve 6 opens and closes at a constant rate by the rate of change limiter 9, keeping the feed water humidity within the required range. Take it inside. Furthermore, when the turbine load drops suddenly and the extraction pressure drops quickly, the adjustment lever 6 is ignored, so the heating steam to the feedwater heater 4 can be switched to the main steam in second gear, and the feedwater heater 4 heating steam? if[(
You can be stunned.

本発明によればこのように制御が行われるので、原子炉
およびターモレ出〕jへの影響を少くしかつ給水晶、i
瓜を要求範囲内どすることができる。さらに急速な抽気
圧力の降下のような現象に対しては、調ll1j弁6を
急開Jることによって加熱蒸気をすみやかに切行え、給
水加熱器4の加熱蒸気を確保できる。
According to the present invention, control is performed in this manner, so that the influence on the reactor and the turmoil output]j is reduced, and the supply crystal, i
The melon can be kept within the required range. Furthermore, in response to a phenomenon such as a rapid drop in bleed pressure, the heating steam can be quickly cut off by rapidly opening the control valve 6, and the heating steam for the feed water heater 4 can be secured.

[発明の効果] 以上の説明で明らか′/、rように本発明によれば、原
子力発電プラントにおいて給水加熱器への加熱蒸気を抽
気蒸気から主蒸気へ徐々に切替えるよう構成したことに
より、タービン出力、原子炉への影響を少くし、原子炉
に入る給水温度を要求される範囲に保つ制すIIが実現
できる。。
[Effects of the Invention] As is clear from the above explanation, according to the present invention, in a nuclear power plant, the heating steam to the feed water heater is gradually switched from extracted steam to main steam, so that the turbine It is possible to realize II, which reduces the impact on the output and reactor and maintains the temperature of the feed water entering the reactor within the required range. .

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

第1図は本発明の給水加熱器の加熱熱気制御(10・1
゜置を適用する光電プラントを示ず(既略系統し1、i
12図は要求給水温度と蒸発量の13’J係特1!1μ
m、第;3図は本発明による給水加熱器のIJ11熱蒸
気制’fill fHiiXの一実施例を示リブロック
系統図、第4図は水斤明の他の実施例による制御装置を
示リブ[−1ツク系統図である。 1・・・主蒸気 2・・・蒸気加減ツ1゛3・・・蒸気
タービン 4・・・加熱器、lり1+145・・・圧力
スイッチ 6・・・Rul Dii弁7・・・圧力検出
器 8・・・比較検出z):9・・・変化率制限器 1
0・・・電/空変1φ1il−i11・・・圧力低下検
知器 12a、12b ・・・逆止弁 20・・・制御装置 代理人方理−1則 近 憲Ri(ほか1名)第 1 図 、逮発量 第 3 図
Figure 1 shows the heating hot air control (10.1) of the feed water heater of the present invention.
The photoelectric plant to which the ゜ position is applied is not shown.
Figure 12 shows the 13'J relationship between the required water supply temperature and the amount of evaporation.
Fig. 3 shows an embodiment of the IJ11 thermal steam control 'fill fHiiX' of the feed water heater according to the present invention, and Fig. 4 shows a control device according to another embodiment of the water heater. [-1 Tsuk system diagram. 1...Main steam 2...Steam regulator 1゛3...Steam turbine 4...Heater, 1+145...Pressure switch 6...Rul Dii valve 7...Pressure detector 8... Comparison detection z): 9... Change rate limiter 1
0...Electrical/pneumatic change 1φ1il-i11...Pressure drop detector 12a, 12b...Check valve 20...Control device agent principle - 1 rule Ken Ri Chika (and 1 other person) 1st Figure 3: Number of arrests

Claims (2)

【特許請求の範囲】[Claims] (1)給水加熱器に入る抽気蒸気の圧力を検知する圧力
検出器と、この検出圧力により主蒸気から給水加熱器に
流J゛蒸気制御する調整弁に全開、全開する信号を支え
る比較器と、比較器からの全開、全開信号に対して調整
弁に送る信号を一定率とする変化制限器とを協えたこと
を特徴とする給水加熱器の加熱蒸気制御装置。
(1) A pressure detector that detects the pressure of bleed steam entering the feed water heater, and a comparator that uses this detected pressure to send a signal to fully open and fully open the regulating valve that controls the flow of steam from the main steam to the feed water heater. A heating steam control device for a feed water heater, characterized in that it is equipped with a change limiter that sets a constant rate of a signal sent to a regulating valve in response to a fully open signal from a comparator and a fully open signal from a comparator.
(2)圧力低下で変化率制限器を入力ドラッキングとす
る1幾能を加えたことを特徴とする特許請求の範囲第1
項記載の給水加熱器の加熱蒸気制御装置。
(2) Claim 1 characterized in that one geometric function is added in which the rate of change limiter is input dragging due to pressure drop.
A heating steam control device for a feed water heater as described in 2.
JP58146554A 1983-08-12 1983-08-12 Controller for heating steam for feedwater heater Pending JPS6038507A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58146554A JPS6038507A (en) 1983-08-12 1983-08-12 Controller for heating steam for feedwater heater

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58146554A JPS6038507A (en) 1983-08-12 1983-08-12 Controller for heating steam for feedwater heater

Publications (1)

Publication Number Publication Date
JPS6038507A true JPS6038507A (en) 1985-02-28

Family

ID=15410287

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58146554A Pending JPS6038507A (en) 1983-08-12 1983-08-12 Controller for heating steam for feedwater heater

Country Status (1)

Country Link
JP (1) JPS6038507A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010016286A1 (en) * 2008-08-08 2010-02-11 三浦工業株式会社 Steam system

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010016286A1 (en) * 2008-08-08 2010-02-11 三浦工業株式会社 Steam system

Similar Documents

Publication Publication Date Title
US4474169A (en) Solar heat collector control device
US4650633A (en) Method and apparatus for protection of pump systems
US3247069A (en) Control of nuclear power plant
US4387422A (en) Control system process controller
US5023151A (en) Power plant cogeneration control
JPS6038507A (en) Controller for heating steam for feedwater heater
GB1585557A (en) Heating system
JPS59138705A (en) Controller for temperature of supplied water
JPS5923921Y2 (en) Temperature control device for heated fluid
JPS63295997A (en) Warming control apparatus of plant
JPS5948696A (en) Steam distributing device of reactor plant
JP2668143B2 (en) Steam turbine control device and control method therefor
JP3697316B2 (en) Moisture separator heater protection device for nuclear power plant
JP2501347B2 (en) Nuclear power turbine control device
JPH0128202B2 (en)
SU1269574A1 (en) Method of multistage heating of mains water
JPS6159296A (en) Nuclear power plant
JPS6032082B2 (en) Feed water temperature control device
JPS62138794A (en) Nuclear reactor feedwater-temperature controller
JPS63184098A (en) Generating output control method of boiling water type nuclear power plant
JPS6235002B2 (en)
JPS5869308A (en) Controller for flow rate of feedwater for steam generator
JPS58102197A (en) Device for operating and monitoring feedwater heater bypass valve of reactor
JPH0733891B2 (en) Plant warming controller
JPS6029862B2 (en) Solar thermal steam generator