JPS59138994A - Reactor water level control system - Google Patents
Reactor water level control systemInfo
- Publication number
- JPS59138994A JPS59138994A JP58012817A JP1281783A JPS59138994A JP S59138994 A JPS59138994 A JP S59138994A JP 58012817 A JP58012817 A JP 58012817A JP 1281783 A JP1281783 A JP 1281783A JP S59138994 A JPS59138994 A JP S59138994A
- Authority
- JP
- Japan
- Prior art keywords
- water level
- reactor
- reactor water
- control system
- signal
- 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
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Control Of Non-Electrical Variables (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、原子炉発電所の原子炉水位制御方式に係り、
特にシステム異常時に、原子炉水位を一定に保ち、連続
自動運転を確保するのに好適な原子炉水位制御に関する
。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a reactor water level control system for a nuclear power plant,
In particular, the present invention relates to reactor water level control suitable for keeping the reactor water level constant and ensuring continuous automatic operation in the event of a system abnormality.
第１図の如く原子炉給水・再循環流量制御系の協調制御
に関する報告がある。As shown in Figure 1, there is a report on the coordinated control of the reactor water supply/recirculation flow rate control system.
本方式は、発電要求信号１４を、炉水位備差信号８で補
償した制御信号１６でもってＭ−Ｇセット１９を駆動し
、再循環ポンプ２２０回転数を変化させ王蒸気流ｔ３’
＆−制御する方式である。本方式によれば、システム正
常時には炉水位５変動の少ない安定した制御を行う事が
出来るが、給水制御系の給水流量操作部１１をロックす
る様なシステム異常が発生し、給水の制御が出来ない場
合には、自動による炉水位一定値制御が出来ないと云っ
た欠点があった。In this method, the power generation request signal 14 is compensated with the control signal 16 using the reactor water level difference signal 8 to drive the M-G set 19, change the rotational speed of the recirculation pump 220, and change the rotational speed of the main steam flow t3'.
&- This is a method of controlling. According to this method, when the system is normal, it is possible to perform stable control with little fluctuation in the reactor water level 5, but if a system abnormality occurs that locks the water supply flow rate control section 11 of the water supply control system, the water supply cannot be controlled. Otherwise, there was a drawback that automatic control of the reactor water level to a constant value was not possible.
御が出来なくなった状態で、原子炉の安全確保の為に炉
水位一定制ａ１′ｆｒ、行い、かつ、システム異常が発
生した時点の発電能力に見合った出力で、連続自動運転
が出来る様な制御を提供する事にある。In order to ensure the safety of the reactor, a constant reactor water level control a1'fr is carried out to ensure the safety of the reactor, and continuous automatic operation is possible at an output commensurate with the power generation capacity at the time the system abnormality occurs. The purpose is to provide control.
原子炉水位は、原子炉安全確保の為、いかなる場合にも
一定に保つ必要がある。この原子炉水位は、通常運転中
は主に原子炉給水流量と主蒸気流量がバランスする事に
よシ一定に保たれる。しがし、システム異常等により、
給水制御が出来なくなり一定流量しか給水流量を流す事
が出来なくなった場合、原子炉水位は一定に保てなくな
る。この時、原子炉出力量である主蒸気流量を原子炉に
給水可能な給水流量とバランスする様に制御すれば原子
炉水位を一定に保てる事に着目したものである。The reactor water level must be kept constant under any circumstances to ensure reactor safety. During normal operation, this reactor water level is kept constant mainly by the balance between the reactor feed water flow rate and the main steam flow rate. However, due to system abnormalities, etc.
If water supply control becomes impossible and only a constant flow rate of water can flow, the reactor water level will not be able to be maintained at a constant level. At this time, we focused on the fact that the reactor water level can be kept constant by controlling the main steam flow rate, which is the reactor output amount, to be balanced with the water supply flow rate that can be supplied to the reactor.
以下本発明の一実施例を第１図、第２図によシ説明する
。原子炉の安全の為に、いかなる場合も炉水位５は一定
に保つ必要がある。An embodiment of the present invention will be explained below with reference to FIGS. 1 and 2. For reactor safety, the reactor water level 5 must be kept constant under any circumstances.
これは、炉水位設定値信号７と炉水位信号４の偏差信号
８を比例・積分器９で比例積分した制御信号１０でもっ
てタービン駆動給水ポンプ１２０回転数を変化させ給水
流量１３を制御する事によシ通常運転中は行っている。This is to control the feed water flow rate 13 by changing the rotation speed of the turbine-driven feed water pump 120 using a control signal 10 obtained by proportionally integrating the reactor water level set value signal 7 and the deviation signal 8 of the reactor water level signal 4 using a proportional/integrator 9. This is normally done during normal driving.
一方、原子炉の出力制御は、発電要求信号１４に基づき
Ｍ−Ｇセット１９０発電機の出力電源周波数を変化させ
再循環ポンプ２２０回転数を制御する事により行ってい
る。即ち、再循環ポンプ２２の回転数が増加すれば主蒸
気流蓋３も増加する事になる。On the other hand, the output of the nuclear reactor is controlled by changing the output power frequency of the MG set 190 generator based on the power generation request signal 14 and controlling the rotation speed of the recirculation pump 220. That is, if the rotational speed of the recirculation pump 22 increases, the main steam flow lid 3 will also increase.
ここで何らかの異常でタービン駆動給水ポンプ１２がロ
ックされると給水流量１３は制御信号１０に無関係に一
定流量しか流す革が出来ず炉水位５の制御が出来なくな
る。この為ロック発生と同時に原子力出力系の制御信号
と炉水位偏差信号８をゲイン変換器２３でゲイン補正し
た偏差信号２４に切換えて、この偏差信号２４で再循環
ポンプ２２回転数を変化させ主蒸気流ｉ３を制御してや
れば炉水位５を一定に制御する事が出来る。従って本実
施例によれば、給水制御系の操作部ロックが発生した場
合でも、その時の発電能力に見合った連続自動運転が出
来る様になる。If the turbine-driven feed water pump 12 is locked due to some abnormality, the feed water flow rate 13 will not be able to flow at a constant flow rate regardless of the control signal 10, making it impossible to control the reactor water level 5. Therefore, at the same time as a lock occurs, the control signal of the nuclear power output system and the reactor water level deviation signal 8 are switched to the deviation signal 24 whose gain has been corrected by the gain converter 23, and the rotation speed of the recirculation pump 22 is changed using this deviation signal 24. By controlling the flow i3, the reactor water level 5 can be controlled to be constant. Therefore, according to this embodiment, even if the operation section of the water supply control system is locked, continuous automatic operation can be performed in accordance with the power generation capacity at that time.
本発明によれば、原子炉給水流量制御が出来なくなって
も、主蒸気流量の制御によシ、炉水位を一定に保つ事が
出来、連続自動運転が出来るので、システムの安全、稼
動率の向上を図る事が出来る。According to the present invention, even if reactor feed water flow rate control becomes impossible, the reactor water level can be kept constant by controlling the main steam flow rate, and continuous automatic operation can be performed, thereby improving system safety and availability. You can try to improve it.
第１図は、原子力発電所の原子炉給水・再循環流量制御
系の従来制御系統図、第２図は、本発明の制御系統図で
ある。
ｌ・・・原子炉圧力容器、２・・・タービン、３・・・
主蒸気流量、４・・・原子炉水位信号、５・・・原子炉
水位、６・・・原子炉水位設定器、７・・・原子炉水位
設定信号、８・・・原子炉水位偏差信号、９・・・比例
・積分器、１０・・・操作部制御信号、１１・−・給水
ポンプ駆動用タービン、１２・・・タービン駆動給水ポ
ンプ、１３・・・原子炉給水流量、１４・・・発電要求
信号、１５・・・減算器、１６・・・Ｍ−Ｇセット回転
数指令偏差信号、１７・・・比例・積分器、１８・・・
Ｍ−Ｇ上２１回転数指令信号、１９・・・Ｍ−Ｇセット
、２０・・・Ｍ−Ｇセット回転数信号、２１・・・再循
環ポンプ駆動用電動機、２２・・・再循環ポンプ、２３
・・・ゲイン変換器、２４・・・原子炉水位補正偏差信
号、２５・・・信号切換器。
第１図
第２目FIG. 1 is a conventional control system diagram of a reactor feed water/recirculation flow rate control system of a nuclear power plant, and FIG. 2 is a control system diagram of the present invention. l...Reactor pressure vessel, 2...Turbine, 3...
Main steam flow rate, 4...Reactor water level signal, 5...Reactor water level, 6...Reactor water level setter, 7...Reactor water level setting signal, 8...Reactor water level deviation signal , 9... Proportional/integrator, 10... Operating unit control signal, 11... Water supply pump driving turbine, 12... Turbine driven water supply pump, 13... Reactor feed water flow rate, 14... - Power generation request signal, 15... Subtractor, 16... M-G set rotation speed command deviation signal, 17... Proportional/integrator, 18...
21 rotation speed command signal on M-G, 19...MG set, 20...MG set rotation speed signal, 21...Recirculation pump driving electric motor, 22...Recirculation pump, 23
...Gain converter, 24...Reactor water level correction deviation signal, 25...Signal switch. Figure 1 2nd eye
Claims (1)
給水量を制御するタービン駆動給水ポンプが何らかの異
常でロックされた時、原子炉の出力を制御している再循
環ポンプの回転数を、炉水位偏差信号で炉水位が一定に
なる様に制御する事により、その時の発電能力に見合っ
た状態で連続自動運転を行う事を特徴とする原子炉水位
制御方式。1. At a nuclear power plant, when the turbine-driven water pump that controls the amount of water supplied to the reactor pressure vessel is locked due to some abnormality, the rotation speed of the recirculation pump that controls the reactor output is , a reactor water level control system that is characterized by continuous automatic operation in a state commensurate with the power generation capacity at that time by controlling the reactor water level to be constant using a reactor water level deviation signal.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58012817A JPS59138994A (en) | 1983-01-31 | 1983-01-31 | Reactor water level control system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58012817A JPS59138994A (en) | 1983-01-31 | 1983-01-31 | Reactor water level control system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59138994A true JPS59138994A (en) | 1984-08-09 |
Family
ID=11815934
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58012817A Pending JPS59138994A (en) | 1983-01-31 | 1983-01-31 | Reactor water level control system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59138994A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0346596A (en) * | 1989-07-14 | 1991-02-27 | Hitachi Ltd | Method and device for controlling output of nuclear reactor |
-
1983
- 1983-01-31 JP JP58012817A patent/JPS59138994A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0346596A (en) * | 1989-07-14 | 1991-02-27 | Hitachi Ltd | Method and device for controlling output of nuclear reactor |
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