JPH0242395A - Nuclear reactor feed water flow rate controller - Google Patents

Nuclear reactor feed water flow rate controller

Info

Publication number
JPH0242395A
JPH0242395A JP63192700A JP19270088A JPH0242395A JP H0242395 A JPH0242395 A JP H0242395A JP 63192700 A JP63192700 A JP 63192700A JP 19270088 A JP19270088 A JP 19270088A JP H0242395 A JPH0242395 A JP H0242395A
Authority
JP
Japan
Prior art keywords
flow rate
feed water
reactor
reactor feed
control device
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
JP63192700A
Other languages
Japanese (ja)
Inventor
Masatoshi Abe
正俊 阿部
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 JP63192700A priority Critical patent/JPH0242395A/en
Publication of JPH0242395A publication Critical patent/JPH0242395A/en
Pending legal-status Critical Current

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

  • Control Of Non-Positive-Displacement Pumps (AREA)
  • Structures Of Non-Positive Displacement Pumps (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】 ［発明の目的］ 〈産業上の利用分野） 本発明は沸騰水型原子力発電所における原子炉給水流量
制御装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] <Industrial Application Field> The present invention relates to a reactor feed water flow rate control device in a boiling water nuclear power plant.

（従来の技術） 沸騰水型原子力発電プラントにおいては、原子炉で発生
した蒸気は主タービンに送られ、ここで仕事をした後、
主復水器で冷却、ｉ縮されて復水となり、復水ポンプ、
給水加熱器、原子炉給水ポンプよりなる原子炉１次給水
系を経て再び原子炉へ給水される。(Prior art) In a boiling water nuclear power plant, the steam generated in the nuclear reactor is sent to the main turbine, where it does work and then
It is cooled and condensed in the main condenser to become condensate, and the condensate pump,
Water is supplied to the reactor again through the reactor primary water supply system consisting of a feedwater heater and a reactor feedwater pump.

ところで、原子炉給水流量は原子炉水位を一定に維持す
るように原子炉給水制御装置により自動制御されており
、主蒸気流量とほぼ同じ流量になるように制御されてい
る。また、復水ポンプから下流側で主復水器へ分枝する
流れがない場合は、復水流量と原子炉給水流量とはほぼ
等しくなるが、分岐する流れが生じると復水流量はその
分岐流■分だけ原子炉給水流量より多くなるように設計
されている。Incidentally, the reactor feed water flow rate is automatically controlled by a reactor feed water control device to maintain the reactor water level constant, and is controlled to be approximately the same flow rate as the main steam flow rate. Additionally, if there is no flow branching downstream from the condensate pump to the main condenser, the condensate flow rate and the reactor feed water flow rate will be approximately equal, but if a branching flow occurs, the condensate flow rate will be It is designed so that the flow rate is greater than the reactor feed water flow rate by the amount of flow.

（発明が解決しようとする課題） 従来、原子炉給水ポンプによる最小流量は主復水器へ流
していたため、給水ポンプの流量減少。(Problem to be solved by the invention) Conventionally, the minimum flow rate by the reactor feed water pump was sent to the main condenser, which resulted in a decrease in the flow rate of the feed water pump.

切替え、試運転等で原子炉給水ポンプ最小流量弁を開と
した場合、前記したように復水流量が増加していた。こ
の復水流量の増加は、主タービンから給水加熱器への抽
気蒸気量の増加による発電機出力の低下と、復水ポンプ
吐出圧力の低下による原子炉水位の変動を引き起すとい
う不具合があった。When the minimum flow rate valve of the reactor feed water pump was opened during changeover, trial run, etc., the condensate flow rate increased as described above. This increase in condensate flow rate had the disadvantage of causing a decrease in generator output due to an increase in the amount of steam extracted from the main turbine to the feedwater heater, and fluctuations in the reactor water level due to a decrease in condensate pump discharge pressure. .

本発明は上記事情に鑑みてなされたもので、その目的は
、原子炉給水ポンプ最小流量弁を開いても給水流量が増
加しないように構成した原子炉給水流量制御装置を提供
することにある。The present invention has been made in view of the above circumstances, and an object thereof is to provide a reactor feed water flow rate control device configured so that the feed water flow rate does not increase even if the reactor feed water pump minimum flow valve is opened.

［発明の構成］ （課題を解決するための手段） 上記目的を達成するために、本発明は原子炉で発生した
蒸気をタービン、主復水器、復水ポンプ。[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention utilizes steam generated in a nuclear reactor in a turbine, a main condenser, and a condensate pump.

給水加熱器、最小流量制御装置を経て再び原子炉へ給水
するようにした原子炉１次給水系統において、前記最小
流量制御装置はタービン駆動による原子炉給水ポンプと
、電動機駆動による原子炉給水ポンプとからなり、ざら
に前記電動機駆動による原子炉給水ポンプの下流側に設
けた最小流量弁の開条件のときその流量の一部を前記主
復水器へ流すために前記最小流量制御装置と前記主復水
器との間に分岐配管を設けて原子炉への給水流量を増加
しないように構成したことを特徴とするものである。In a reactor primary water supply system in which water is supplied to the reactor again via a feedwater heater and a minimum flow rate control device, the minimum flow rate control device includes a reactor feed water pump driven by a turbine and a reactor feed water pump driven by an electric motor. Roughly speaking, the minimum flow rate control device and the main condenser are configured to flow a part of the flow rate to the main condenser when the minimum flow rate valve provided on the downstream side of the reactor feed water pump driven by the electric motor is open. This system is characterized in that a branch pipe is provided between the reactor and the condenser so as not to increase the flow rate of water supplied to the reactor.

（作　用） 本発明の原子炉給水流量制御装置によれば、原子炉給水
ポンプの最小流量弁を開いてもその流罪の一部は分岐配
管を経て原子炉給水ポンプ吸込配管へ流れるので、原子
炉への給水流量は増加しない。また、電動機駆動による
原子炉給水ポンプを最小流量付近でかつ他の原子炉給水
ポンプが停止している状態で長時間にわたり運転する場
合には、最小流量の一部を主復水器へ流すことによりキ
Ｖビテーション発生を防止することができる。(Function) According to the reactor feed water flow rate control device of the present invention, even if the minimum flow valve of the reactor feed water pump is opened, a portion of the waste flows through the branch pipe to the reactor feed water pump suction pipe, so that the The water flow rate to the furnace does not increase. In addition, when operating a reactor feed water pump driven by an electric motor for a long period of time at around the minimum flow rate and with other reactor feed water pumps stopped, a part of the minimum flow rate must be sent to the main condenser. This makes it possible to prevent the occurrence of vitiation.

（実施例） 本発明の一実施例を図面を参照して説明する。(Example) An embodiment of the present invention will be described with reference to the drawings.

第１図は本発明の一実施例の系統構成図である。FIG. 1 is a system configuration diagram of an embodiment of the present invention.

原子炉１で発生した蒸気は主蒸気管２を通って主タービ
ン３に送られ、この主タービン３で仕事をしたのち主復
水器４で冷却されて復水となる。この復水は復水ポンプ
５で昇圧、給水加熱器６で加熱され、原子炉給水ポンプ
吸込配管７を通り最小流量制御装置°８内で昇圧した後
、原子炉給水ポンプ吐出配管９を通り再び原子炉１へ給
水される。Steam generated in the nuclear reactor 1 is sent to the main turbine 3 through the main steam pipe 2, and after doing work in the main turbine 3, it is cooled in the main condenser 4 and becomes condensate. This condensate is pressurized by the condensate pump 5, heated by the feed water heater 6, passes through the reactor feed water pump suction pipe 7, increases the pressure within the minimum flow rate control device °8, and then passes through the reactor feed water pump discharge pipe 9 again. Water is supplied to reactor 1.

また、最小流量制御装置８と主復水器４との間には分岐
配管１０が接続されている。Further, a branch pipe 10 is connected between the minimum flow rate control device 8 and the main condenser 4.

次に、第２図の接続構成図を参照して最小流量制御装置
８の詳細を説明する。Next, details of the minimum flow rate control device 8 will be explained with reference to the connection diagram of FIG. 2.

最小流量制御装置８はタービン（ｌｌａ、１ｌｂ）駆動
による原子炉給水ポンプ１２ａ、　１２ｂと、電動機（
１３ａ、１３ｂ）駆動による原子炉給水ポンプ１４ａ、
　１４ｂと、タービン側の最小流量弁１５ａ、　１５ｂ
と電動機側の最小流量弁１６ａ、　１６ｂとから構成さ
れている。The minimum flow rate control device 8 includes reactor feed water pumps 12a, 12b driven by turbines (lla, 1lb), and an electric motor (
13a, 13b) driven reactor feed water pump 14a,
14b, and minimum flow valves 15a and 15b on the turbine side.
and minimum flow valves 16a and 16b on the motor side.

通常運転において、原子炉１から発生する蒸気の圧力と
流量に応じて電動機駆動による原子炉給水ポンプ１４ａ
、１４ｂのうち１台、タービン駆動による原子炉給水ポ
ンプ１２ａ、　１２ｂのうち１台または２台と切替えが
行なわれている。During normal operation, the reactor feed water pump 14a is driven by an electric motor according to the pressure and flow rate of steam generated from the reactor 1.
, 14b, and one or two of the turbine-driven reactor feed water pumps 12a, 12b.

ところで、原子炉給水ポンプの切替え時または流量の減
少時にポンプ最小流量を確保するために、タービン駆動
による原子炉給水ポンプ１２ａ、　１２ｔ）のそれぞれ
に最小流量弁１５ａ、１５ｂ　＠設けており、また、電
動機駆動による原子炉給水ポンプ１４ａ、　１４ｂのそ
れぞれに最小流量弁１６ａ、１６ｂを設けている。By the way, in order to ensure the minimum pump flow rate when switching reactor feed water pumps or when the flow rate decreases, minimum flow valves 15a and 15b are provided for each of the turbine-driven reactor feed water pumps 12a and 12t. A minimum flow valve 16a, 16b is provided for each of the reactor feed water pumps 14a, 14b driven by an electric motor.

ざらに、それぞれの最小流量弁１５ａ、　１５ｂおよび
最小流量弁１６ａ、　１６ｂから原子炉給水ポンプ吸込
配管７には配管１７ａ、１７ｂおよび１８ａ、１８ｂが
設けられている。電動機駆動による原子炉給水ポンプ１
４ａ。Roughly speaking, pipes 17a, 17b and 18a, 18b are provided from the minimum flow valves 15a, 15b and the minimum flow valves 16a, 16b to the reactor feed water pump suction pipe 7. Reactor feed water pump 1 driven by electric motor
4a.

１４ｂは最小流量付近でかつ他の原子炉給水ポンプ１２
ａ、　１２ｂが停止している状態のとき長時間にわたっ
て運転することがあり、キャビテーション発生防止のた
め最小流量の一部を最小流量弁１６ａ、１６ｂを経て主
復水器４へ流せるように連絡配管１９ａ。14b is near the minimum flow rate and other reactor feed water pumps 12
When valves a and 12b are stopped, it may be operated for a long time, so connecting piping is installed so that a part of the minimum flow can flow to the main condenser 4 via the minimum flow valves 16a and 16b to prevent cavitation. 19a.

１９ｂと連絡弁２０が設けられている。19b and a communication valve 20 are provided.

次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.

原子炉給水ポンプの切替え操作時または流量減少等で最
小流量を確保するために最小流量弁１５ａ。A minimum flow valve 15a is provided to ensure the minimum flow rate when switching the reactor feed water pump or when reducing the flow rate.

１５ｂおよび１６ａ　１６ｂのいずれかを開いた場合、
その一部の流量が配管１７ａ、１７ｂおよび１８ａ、１
８ｂを経て原子炉給水ポンプ吸込配管７へ流れるため復
水流量、復水ポンプ吐出圧力に変化はない。また電動機
駆動による原子炉給水ポンプ１４ａ、　１４ｂだけで最
小流ｍ附近で長時間にわたり運転する場合には弁１６ａ
、１６ｂを開いてその流量の一部を連絡配管１９ａ、１
９ｂと連絡弁２０を介して主復水器４へ流すようにして
いるので、キャビテーション発生を防止することができ
る。15b and 16a If either 16b is opened,
The flow rate of some of the pipes 17a, 17b and 18a, 1
8b to the reactor feed water pump suction pipe 7, there is no change in the condensate flow rate or condensate pump discharge pressure. In addition, when only the reactor feed water pumps 14a and 14b driven by electric motors are operated for a long time near the minimum flow m, the valve 16a is
, 16b is opened and a part of the flow rate is transferred to the connecting pipes 19a, 1.
9b and the communication valve 20 to the main condenser 4, cavitation can be prevented from occurring.

［発明の効果］ 以上説明したように、本発明によれば原子炉給水ポンプ
最小流量弁を開いても復水流量、復水ポンプ吐出力は変
化しないので、発電機出力の低下。[Effects of the Invention] As explained above, according to the present invention, even if the reactor feed water pump minimum flow valve is opened, the condensate flow rate and the condensate pump discharge force do not change, so the generator output decreases.

原子炉水位の変動がないためプラント設備の利用率と運
転性が向上し、また、タービン駆動による原子炉給水ポ
ンプの最小流量配管の長さを短くできるので、コスト低
減につながり、さらに誤って最小流量弁が開いても復水
ポンプがランアウトする心配はなくなる等の効果を秦す
る。Since there is no fluctuation in the reactor water level, the utilization rate and operability of plant equipment are improved.In addition, the minimum flow piping length of the turbine-driven reactor feed water pump can be shortened, leading to cost reductions. Even if the flow valve is opened, there is no need to worry about the condensate pump running out.

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

第１図は本発明の一実施例の系統構成図、第２図は第１
図の最小流量制御装置の接続構成図である。 １・・・原子炉　　　　　２・・・主蒸気管３・・・主
タービン　　　４・・・主復水器５・・・復水ポンプ　
　　６・・・給水加熱器７・・・吸込配管　　　　８・
・・最小流量制御装置９・・・吐出配管　　　　１０・
・・分岐配管１１ａ、ｌｌｂ　−・・タービン １２ａ、１２ｂ、１４ａ、１４ｂ　・・・原子炉給水ホ
ンフ１３ａ、１３ｂ　−・・電動機 １５ａ、１５ｂ、１６ａ、１６ｂ　・・・最小流量弁１
７ａ、　１７ｂ、　１８ａ、　１８ｂ　・・・配管１９
ａ、　１９ｂ・・・連絡配管　２０・・・連絡弁代理人
　弁理士　則　近　憲　佑 同　　第子丸　健 第１図 第２図Fig. 1 is a system configuration diagram of one embodiment of the present invention, and Fig. 2 is a system configuration diagram of an embodiment of the present invention.
FIG. 3 is a connection configuration diagram of the minimum flow rate control device shown in FIG. 1... Nuclear reactor 2... Main steam pipe 3... Main turbine 4... Main condenser 5... Condensate pump
6... Feed water heater 7... Suction piping 8.
...Minimum flow rate control device 9...Discharge piping 10.
・・Branch piping 11a, llb ・・・Turbine 12a, 12b, 14a, 14b ・・Reactor water supply phonf 13a, 13b ・・・Electric motor 15a, 15b, 16a, 16b ・・Minimum flow valve 1
7a, 17b, 18a, 18b...Piping 19
a, 19b... Connecting pipe 20... Liaison attorney Patent attorney Noriyuki Ken Yudo Daishimaru Ken Figure 1 Figure 2

Claims (1)

【特許請求の範囲】[Claims] （１）原子炉で発生した蒸気をタービン、主復水器、復
水ポンプ、給水加熱器、最小流量制御装置を経て再び原
子炉へ給水するようにした原子炉１次給水系統において
、前記最小流量制御装置はタービン駆動による原子炉給
水ポンプと、電動機駆動による原子炉給水ポンプとから
なり、さらに前記電動機駆動による原子炉給水ポンプの
下流側に設けた最小流量弁の開条件のときその流量の一
部を前記主復水器へ流すために前記最小流量制御装置と
前記主復水器との間に分岐配管を設けて原子炉への給水
流量を増加しないように構成したことを特徴とする原子
炉給水流量制御装置。(1) In the reactor primary water supply system in which steam generated in the reactor is supplied to the reactor again through the turbine, main condenser, condensate pump, feed water heater, and minimum flow rate control device, the minimum The flow rate control device consists of a turbine-driven reactor feed water pump and an electric motor-driven reactor feed water pump, and further controls the flow rate when a minimum flow valve provided downstream of the electric motor-driven reactor feed water pump is open. A branch pipe is provided between the minimum flow rate control device and the main condenser so that a portion of the water flows to the main condenser, so that the flow rate of water supplied to the reactor is not increased. Reactor feed water flow control device.
JP63192700A 1988-08-03 1988-08-03 Nuclear reactor feed water flow rate controller Pending JPH0242395A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63192700A JPH0242395A (en) 1988-08-03 1988-08-03 Nuclear reactor feed water flow rate controller

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63192700A JPH0242395A (en) 1988-08-03 1988-08-03 Nuclear reactor feed water flow rate controller

Publications (1)

Publication Number Publication Date
JPH0242395A true JPH0242395A (en) 1990-02-13

Family

ID=16295595

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63192700A Pending JPH0242395A (en) 1988-08-03 1988-08-03 Nuclear reactor feed water flow rate controller

Country Status (1)

Country Link
JP (1) JPH0242395A (en)

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