JPS60101407A - Feedwater controller - Google Patents
Feedwater controllerInfo
- Publication number
- JPS60101407A JPS60101407A JP58208982A JP20898283A JPS60101407A JP S60101407 A JPS60101407 A JP S60101407A JP 58208982 A JP58208982 A JP 58208982A JP 20898283 A JP20898283 A JP 20898283A JP S60101407 A JPS60101407 A JP S60101407A
- Authority
- JP
- Japan
- Prior art keywords
- water level
- water
- water supply
- recirculation valve
- reactor
- 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
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
- Earth Drilling (AREA)
- Paper (AREA)
- Revetment (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】
〔発明の利用分野〕
本発明は、給水制御装置に係り、特に、給水ポンプの再
循環弁が開閉する際に生じる原子炉水位の変動？小さく
抑えるに好適な給水制御装置に関する。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a water supply control system, and in particular, to fluctuations in reactor water level that occur when a recirculation valve of a water supply pump opens and closes. The present invention relates to a water supply control device suitable for being kept small.
従来より給水ポンプには、再循環弁が設置されており、
給水ポンプ流量が低下するとポンプのキャビテーション
保護のため再循環弁が開き、最低限の流量を確保するよ
うにしている。Traditionally, water pumps have been equipped with recirculation valves.
When the water pump flow rate decreases, the recirculation valve opens to protect the pump from cavitation, ensuring a minimum flow rate.
前記再循環弁が開閉すると、原子炉に供給している給水
流量が増減するため原子炉水位に変動全米たす。When the recirculation valve opens and closes, the flow rate of water supplied to the reactor increases or decreases, causing fluctuations in the reactor water level.
特に、前記再循環弁の容量が大きければ大きい程、原子
炉水位の変動も大きくなる傾向を示す。In particular, the larger the capacity of the recirculation valve, the greater the fluctuation in the reactor water level.
従来の給水制御装置では、前記糊循環弁の開閉動作に何
ら係り？もっていない。すなイ９も、再循環弁の開閉に
よって生じる水位変動？とらえて、水位制御することに
なり、どうしても水位変動が大きくなる傾向にある。In the conventional water supply control device, does it have anything to do with the opening/closing operation of the glue circulation valve? I don't have it. Sunai 9 is also a water level fluctuation caused by opening and closing of the recirculation valve? As a result, water level fluctuations inevitably tend to increase.
このため、容量の大きい再循環弁を有する給水システム
では再循環弁の開閉による原子炉水位変動で、水位高／
低の警報が発生する可能性もあり、運転上好ｉしくない
。For this reason, in a water supply system with a large-capacity recirculation valve, fluctuations in the reactor water level due to the opening and closing of the recirculation valve can cause the water level to rise/rise.
There is a possibility that a low warning will occur, which is not good for driving.
本発明の目的は、前記再循環弁開閉時の原子炉水位変動
？小さく抑えることにより、良好な水位制御を行ない得
る給水制御装置を提供するにある。The purpose of the present invention is to change the reactor water level when the recirculation valve is opened and closed? It is an object of the present invention to provide a water supply control device that can perform good water level control by keeping the water level small.
本発明は、前記再循環弁開閉時の原子炉水位変動音あら
かじめ予測できることから、再循環弁の開閉要求信号を
直接とらえ、一時的に給水制御装置の主水位制御器設定
値全変更するようにしたものである。Since the reactor water level fluctuation sound when the recirculation valve is opened and closed can be predicted in advance, the present invention directly captures the recirculation valve opening/closing request signal and temporarily changes all the settings of the main water level controller of the water supply control device. This is what I did.
第１図に原子炉給水システムの概略を示す。 Figure 1 shows an outline of the reactor water supply system.
原子炉ｌへの給水は、給水ポンプ２によって供給される
。給水ポンプ２け蒸気タービン３にて駆動されている。Water is supplied to the reactor l by a water pump 2. Two water pumps are driven by a steam turbine 3.
給水流量の調節は、蒸気タービン３の速度、すなわち給
水ポンプ２の回転敷金制御することにより行われる。The feed water flow rate is adjusted by controlling the speed of the steam turbine 3, that is, the rotation of the water feed pump 2.
前記給水ポンプ２の速度制御は、原子炉ｌの水位を一定
に維持するように、給水制御装置４にて行われる。給水
制御装置では原子炉水位を検出する水位検出器５からの
水位信号６と、主蒸気流量信号７＆び給水流量信号８を
フィードバックする三侠素制御が行われる。Speed control of the water supply pump 2 is performed by the water supply control device 4 so as to maintain the water level in the reactor l constant. The feed water control device performs three-way control in which a water level signal 6 from a water level detector 5 that detects the reactor water level, a main steam flow rate signal 7, and a feed water flow rate signal 8 are fed back.
上記三要素制御信号と水位設定値９との偏差が主水位制
御器１０に入力され、その出力は、蒸気タービン３の速
度要求信号となる。The deviation between the three-element control signal and the water level set value 9 is input to the main water level controller 10, the output of which becomes the speed request signal for the steam turbine 3.
給水制御？具体的に説明するため、−例として原子炉出
カケ上昇させた場合を考える。Water supply control? For concrete explanation, consider a case where the nuclear reactor output is increased as an example.
原子炉出カケ上昇させると、主蒸気流量が増加するため
給水流量との間にアンバランスが生じ原子炉水位が低下
する。また出力増加に伴い原子炉圧力も上昇するため、
原子炉内の気泡（ボイド）會つぶし、さらに水位低下ケ
来たすことになる。When the reactor output is increased, the main steam flow rate increases, creating an imbalance with the feed water flow rate and lowering the reactor water level. Also, as the reactor pressure increases as the output increases,
This will cause the voids inside the reactor to collapse and the water level to drop further.
このため、給水制御装置にフィードバックされている原
子炉水位、主蒸気流量の信号６．７が変化し、水位設定
値９との偏差が増加する。この結果、主水位制御器ｉｏ
の出力信号が増加し、給水ポンプ２の速度が上昇するた
め給水が増加することになる。Therefore, the reactor water level and main steam flow rate signals 6.7 fed back to the water supply control device change, and the deviation from the water level set value 9 increases. As a result, the main water level controller io
The output signal increases, and the speed of the water supply pump 2 increases, resulting in an increase in water supply.
給水ポンプ２は、特性上、キャビテーションゲ防止する
ため最低流量があり、この流量以下まで給水ポンプ２の
流量が低下しないよう、再循環弁１１が開くようになっ
ている。・
一般に、この再循環弁１１は、給水ポンプ２の吸込流ｂ
１（］−検出して、流量低で開、流量高で閉になるよう
０Ｎ１０ＦＦ制御される。Due to its characteristics, the water supply pump 2 has a minimum flow rate to prevent cavitation, and the recirculation valve 11 is opened to prevent the flow rate of the water supply pump 2 from decreasing below this flow rate. - In general, this recirculation valve 11 is used to control the suction flow b of the water supply pump 2.
1(]- is detected and 0N10FF is controlled so that it opens when the flow rate is low and closes when the flow rate is high.
このため、吸込側に流量検出器１２を設置している。For this reason, a flow rate detector 12 is installed on the suction side.
例えば、原子炉出カケ減少させていくと、前記説明のよ
うに原子炉水位を一定に維持するよう、給水流計も減少
する。For example, when the reactor output is reduced, the feedwater flow meter is also reduced to maintain the reactor water level constant as described above.
給水ポンプ２の吸込流量が、再循環弁１１の開設定値以
下まで低下すると、流量検出器１２が動作して、再循環
弁１１が開き、冷却水が再び復水器ホットウェル１３に
戻される。When the suction flow rate of the water pump 2 falls below the opening set value of the recirculation valve 11, the flow rate detector 12 is activated, the recirculation valve 11 is opened, and the cooling water is returned to the condenser hotwell 13 again.
この時、再循環弁からは、はぼ一定の流量が流れるため
、原子炉への給水は減少することになる。At this time, since a fairly constant flow flows from the recirculation valve, the water supply to the reactor will decrease.
この結果、原子炉水位が低下する。給水制御装置４は、
水位？一定に維持するよう動作するため、給水ポンプ２
の速度が上昇し、水位は再び回復して整定する。As a result, the reactor water level decreases. The water supply control device 4 is
Water level? Water supply pump 2 operates to maintain a constant level.
speed increases and the water level recovers and stabilizes again.
上記水位変動幅は、主に給水制御システムの応答特性に
依存するが、一般的に、再循環弁の容量に比例して、大
きくなる。The width of the water level fluctuation mainly depends on the response characteristics of the water supply control system, but generally increases in proportion to the capacity of the recirculation valve.
再循環弁１１が開いた時の挙動の一例を第２図に示す。An example of the behavior when the recirculation valve 11 is opened is shown in FIG.
従来技術では、第２図に示すように再循環弁開時の水位
変化が大きくなる。In the prior art, as shown in FIG. 2, the water level changes greatly when the recirculation valve is opened.
これに対して、本発明の採用した場合、下記のように改
善される。On the other hand, when the present invention is adopted, the following improvements can be made.
第３図は、本発明による給水制御装置である。FIG. 3 is a water supply control device according to the present invention.
接点１４は通常”開”の状態にあり、再循環弁１１の開
閉要求信号が出ると接点が閉する。接点１４が閉すると
同時に、水位設定演算器１５のプログラム関数が動作し
始める。The contact 14 is normally in an "open" state, and when a signal requesting opening/closing of the recirculation valve 11 is issued, the contact closes. At the same time as the contact 14 closes, the program function of the water level setting calculator 15 begins to operate.
上記水位設定演算器１５は、時間依存の水位設定値で、
再循環弁開時には、原子炉水位が低下するため、水位設
定点ケ一時的に上げることにエリ、先行的に給水流量を
増加させ、原子炉水位の変動音できるだけ抑える。The water level setting calculator 15 has a time-dependent water level setting value.
When the recirculation valve opens, the reactor water level drops, so it is necessary to temporarily raise the water level setting point, and increase the water supply flow rate in advance to suppress the noise of fluctuations in the reactor water level as much as possible.
逆に、再循環弁閉時には、原子炉水位が上昇するため、
水位設定点を一時的に下げることにより、先行的に給水
流量を減少させ、原子炉水位の変動をできるだけ抑える
。Conversely, when the recirculation valve is closed, the reactor water level rises,
By temporarily lowering the water level set point, the feed water flow rate is reduced in advance and fluctuations in the reactor water level are suppressed as much as possible.
水位設定演算器１５のプログラム関数は、あらかじめ解
析等により最も効果的な値に設定しておく。その−例？
第４図に示す。The program function of the water level setting calculator 15 is set in advance to the most effective value through analysis or the like. An example?
It is shown in Figure 4.
第５図は、本発明に基づく再循環弁開時の挙動水したも
のである。原子炉水位の変化幅は従来の約１／２以下と
なり効果のあることがわかる。FIG. 5 shows the behavior of the recirculation valve when it is opened according to the present invention. The range of change in the reactor water level is about 1/2 or less compared to the conventional method, indicating that it is effective.
本発明によれば、給水ポング用再循環弁の開閉時、原子
炉水位変化を小さく抑制できるのでプラン）ｋ安定に運
転する面で効果がある。According to the present invention, changes in the reactor water level can be suppressed to a small level when the water supply pump recirculation valve is opened and closed, which is effective in stably operating the reactor.
第１図は沸騰水形原子力発電プラントの給水システムケ
説明する概略図、第２図は従来技術に基づく再循環弁開
時のプラント挙動を示す図、第３図は本発明による給水
制御装置金示す図、第４図は本発明による水位設定演算
器のプログラム関数例を示す図、第５図は本発明に基づ
く再循環弁開時のプラント挙動を示す図である。
６・・・水位信号、７・・・主蒸気流量信号、８・・・
給水流液信号、９・・・水位設定値、１０・・・主“水
位制御器、１１・・・再循環弁、１２・・・流量検出器
、１３・・・復水十４図
ｇ４間けりFig. 1 is a schematic diagram illustrating the water supply system of a boiling water nuclear power plant, Fig. 2 is a diagram showing the behavior of the plant when the recirculation valve is opened based on the prior art, and Fig. 3 is a diagram illustrating the water supply system according to the present invention. FIG. 4 is a diagram showing an example of a program function of the water level setting calculator according to the present invention, and FIG. 5 is a diagram showing plant behavior when the recirculation valve is opened according to the present invention. 6...Water level signal, 7...Main steam flow rate signal, 8...
Supply water flow signal, 9...Water level setting value, 10...Main water level controller, 11...Recirculation valve, 12...Flow rate detector, 13...Condensate 14 figure g4 Kicking
Claims (1)
給水流ｔａ＝ を制御する給水制御装置において、前記
給水ポンプ用再循環弁の開閉要求信号ケ受けて、一時的
に水位設定点を変更する演算機能を設けたこと全特徴と
する給水制御装置。 ２、特許請求の範囲第１項において、前記演算機能は、
前記再循環弁の開または閉のそれぞれに対応した時間関
数の水位設定点波ｑ−であること全特徴とする給水制御
装置。[Claims] 1. In a water supply control device that controls a water supply pump that supplies cooling water to a nuclear reactor or a boiler and a water supply flow ta=, in response to an opening/closing request signal of the recirculation valve for the water supply pump, A water supply control device that is characterized by a calculation function that changes the water level set point. 2. In claim 1, the arithmetic function is:
A water supply control system characterized in that the water level set point wave q- is a function of time corresponding to each opening or closing of the recirculation valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58208982A JPS60101407A (en) | 1983-11-09 | 1983-11-09 | Feedwater controller |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58208982A JPS60101407A (en) | 1983-11-09 | 1983-11-09 | Feedwater controller |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS60101407A true JPS60101407A (en) | 1985-06-05 |
Family
ID=16565370
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58208982A Pending JPS60101407A (en) | 1983-11-09 | 1983-11-09 | Feedwater controller |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60101407A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016008724A (en) * | 2014-06-20 | 2016-01-18 | 三浦工業株式会社 | Drain recovery system |
| CN109681443A (en) * | 2018-11-20 | 2019-04-26 | 中广核研究院有限公司 | A kind of revolution speed control system and method for nuclear power station turbine driven feedwater pump |
-
1983
- 1983-11-09 JP JP58208982A patent/JPS60101407A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016008724A (en) * | 2014-06-20 | 2016-01-18 | 三浦工業株式会社 | Drain recovery system |
| CN109681443A (en) * | 2018-11-20 | 2019-04-26 | 中广核研究院有限公司 | A kind of revolution speed control system and method for nuclear power station turbine driven feedwater pump |
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