JPH0427896A - Emergency condenser - Google Patents

Emergency condenser

Info

Publication number
JPH0427896A
JPH0427896A JP2132560A JP13256090A JPH0427896A JP H0427896 A JPH0427896 A JP H0427896A JP 2132560 A JP2132560 A JP 2132560A JP 13256090 A JP13256090 A JP 13256090A JP H0427896 A JPH0427896 A JP H0427896A
Authority
JP
Japan
Prior art keywords
reactor pressure
opening degree
nuclear reactor
limit value
valve
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
JP2132560A
Other languages
Japanese (ja)
Inventor
Ryoichi Hamazaki
亮一 濱崎
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 JP2132560A priority Critical patent/JPH0427896A/en
Publication of JPH0427896A publication Critical patent/JPH0427896A/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To maintain nuclear reactor pressure within an appropriate range and to facilitate lessening operators' work load, prevention of miss operation and improvement of nuclear reactor safety by providing a low regulating valve on a condensate return pipe and controlling opening degree of the value in relation to the nuclear reactor pressure. CONSTITUTION:A flow regulation valve 8 is provided and the value is controlled by a control device 10 of valve opening degree when pressure signal 9 of a nuclear reactor is fed for controlling. The control device 10 of valve opening degree generates control signal of valve opening degree 0%, under a condition of nuclear reactor pressure less than lower controlling limit value A, and generates the control signal of valve opening degree 100%, under a condition of nuclear reactor pressure higher than upper controlling limit value B. The device 10 generates the control signal demanding proportional opening degree to difference between the nuclear reactor pressure and the aforementioned lower controlling limit value A, under a condition of the reactor pressure staying between the lower controlling limit value A and the upper controlling limit value B. The control device 10 of valve opening degree controls the flow regulating valve 8 and there is no possibility that pressure in a nuclear reactor pressure vessel 1 excessively drops down even though letting steam and condensate circulate under natural convection basis.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は原子力発電所において原子炉隔離が発生し通常
の復水器が使用不能となった場合に、原子炉の崩壊熱を
除去するのに使用する非常用復水器に係り、特に原子炉
圧力を過度に低下させることなく崩壊熱の除去をなし得
る非常用復水器に管する。
[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention is designed to prevent the collapse of a nuclear reactor when reactor isolation occurs in a nuclear power plant and a normal condenser becomes unusable. It relates to an emergency condenser used to remove heat, and in particular, to an emergency condenser that can remove decay heat without excessively lowering the reactor pressure.

(従来の技術) 非常用復水器は、主蒸気隔離弁閉鎖事象のように原子炉
隔離が発生し、主復水器が使用不能となった場合に原子
炉の崩壊熱を格納容器外に除熱する機能を有するもので
ある。
(Prior art) An emergency condenser is used to transfer reactor decay heat outside the containment vessel when reactor isolation occurs, such as a main steam isolation valve closure event, and the main condenser becomes unusable. It has the function of removing heat.

第4図は従来の非常用復水器の模式図である。FIG. 4 is a schematic diagram of a conventional emergency condenser.

この図において、原子炉圧力容器1−内には炉心2が収
容され、原子炉圧力容器1内の気相領域は蒸気供給管3
によって冷却水貯蔵槽4内の伝熱管束5に連通されてい
る。前記伝熱管束5は復水戻り管6によって原子炉圧力
容器1の液相領域に連通されている。なお、前記復水戻
り管6には隔離弁7が設けられている。
In this figure, a reactor core 2 is housed in a reactor pressure vessel 1-, and a gas phase region inside the reactor pressure vessel 1 is connected to a steam supply pipe 3.
It is connected to the heat exchanger tube bundle 5 in the cooling water storage tank 4 by. The heat transfer tube bundle 5 is communicated with the liquid phase region of the reactor pressure vessel 1 by a condensate return pipe 6 . Note that the condensate return pipe 6 is provided with an isolation valve 7.

上記構成の非常用復水器の作動は次の通りである。原子
炉隔離事象が発生すると、原子炉はスクラムされる。と
ころが、崩壊熱による蒸気の発生は継続され原子炉圧力
は上昇する。原子炉圧力が成る限度に達すると圧力高信
号が発せられ、この信号により隔離弁7が開放される。
The operation of the emergency condenser with the above configuration is as follows. When a reactor isolation event occurs, the reactor is scrammed. However, the generation of steam due to decay heat continues and the reactor pressure increases. When the reactor pressure reaches a certain limit, a high pressure signal is generated, which causes the isolation valve 7 to open.

原子炉圧力容器1内の蒸気は蒸気供給管3から冷却水貯
蔵槽4内の伝熱管束5に導かれ、ここで除熱され凝結、
復水される。この復水は復水戻り管6、隔離弁7を経由
して原子炉圧力容器1内に戻される。上記の一連の過程
を継続することにより、冷却水貯蔵槽4内の冷却水は伝
熱管束5から伝達された熱により昇温され、終には沸騰
することとなり、これにより発生した蒸気は大気中にベ
ントされる。
The steam in the reactor pressure vessel 1 is led from the steam supply pipe 3 to the heat transfer tube bundle 5 in the cooling water storage tank 4, where it is heat removed and condensed.
The water is condensed. This condensate is returned into the reactor pressure vessel 1 via a condensate return pipe 6 and an isolation valve 7. By continuing the above series of processes, the temperature of the cooling water in the cooling water storage tank 4 is raised by the heat transferred from the heat transfer tube bundle 5, and eventually boils, and the steam generated thereby is released into the atmosphere. Vented inside.

而して、前記冷却水貯蔵槽4を含む非常用復水器の設置
位置は原子炉の上方としてあり、何等外部動力に依存す
ることなく、蒸気供給管3内の蒸気と復水戻り管6内の
復水との密度差により、重力に基づく自然循環によって
蒸気および復水の循環を生じさせ、崩壊熱の除去を行わ
せる。
Therefore, the installation position of the emergency condenser including the cooling water storage tank 4 is above the reactor, and the steam in the steam supply pipe 3 and the condensate return pipe 6 are connected to each other without depending on any external power. Due to the difference in density between the steam and condensate, natural circulation based on gravity generates circulation of steam and condensate, allowing decay heat to be removed.

(発明が解決しようとする課題) 上記のように、従来の非常用復水器は重力による自然循
環によって崩壊熱の除去を行うようにしている。また、
伝熱管の汚れ等により除熱性能が低下するのを見込んで
、設計上所要値を上回る除熱性能が得られるようにして
いた。そのため、伝熱管に汚れのない場合には過度の除
熱がなされることとなり、原子炉圧力の過度の低下が見
られることとなる。このような原子炉圧力の過度の低下
は、m子炉圧力容器の健全性維持上好ましくない。
(Problems to be Solved by the Invention) As described above, conventional emergency condensers remove decay heat through natural circulation due to gravity. Also,
Anticipating that heat removal performance would deteriorate due to contamination of heat exchanger tubes, etc., the design was designed to provide heat removal performance that exceeds the required value. Therefore, if the heat exchanger tubes are clean, excessive heat will be removed, resulting in an excessive drop in reactor pressure. Such an excessive decrease in reactor pressure is undesirable in terms of maintaining the integrity of the reactor pressure vessel.

よって、上記のような原子炉圧力容器の過度の低下があ
った場合には、運転員の手動の操作により隔離弁7を閉
鎖させて除熱量を低下させ、前記過度の圧力低下を防止
するようにしていた。このように従来の非常用復水器に
おいては、運転員による手動の操作を必要とすることが
あった。
Therefore, if there is an excessive drop in the reactor pressure vessel as described above, the operator manually closes the isolation valve 7 to reduce the amount of heat removal and prevent the excessive pressure drop. I was doing it. As described above, conventional emergency condensers sometimes require manual operation by an operator.

本発明は上記の事情に基づきなされたもので、伝熱管束
の汚れ等に基づく伝熱性能の経年変化に対応できるとと
もに、原子炉圧力容器内の圧力の過度の低下を生じるこ
となく、運転員よる手動の操作を必要としない非常用復
水器を提供することを目的としている。
The present invention has been made based on the above circumstances, and is capable of coping with aging changes in heat transfer performance due to contamination of heat transfer tube bundles, etc., and without causing an excessive drop in pressure within the reactor pressure vessel. The purpose is to provide an emergency condenser that does not require manual operation.

[発明の構成] (課題を解決するための手段) 本発明の非常用復水器は、冷却水貯蔵槽と、この冷却水
貯蔵槽内の伝熱管束と、この伝熱管束に原子炉圧力容器
内の蒸気を供給する蒸気供給管と、前記伝熱管束におい
て蒸気が凝結して生成された復水を原子炉圧力容器内に
帰戻させる復水戻り管とを有するものにおいて、前記復
水戻り管に流量調整弁を設け、この流量調整弁の開度を
原子炉圧力信号を制御入力とする弁開度制御装置により
制御することを特徴とする。
[Structure of the Invention] (Means for Solving the Problems) The emergency condenser of the present invention includes a cooling water storage tank, a heat transfer tube bundle in the cooling water storage tank, and a reactor pressure applied to the heat transfer tube bundle. A device comprising a steam supply pipe that supplies steam in the vessel, and a condensate return pipe that returns condensate generated by condensation of steam in the heat transfer tube bundle to the reactor pressure vessel, wherein the condensate The return pipe is provided with a flow rate adjustment valve, and the opening degree of the flow rate adjustment valve is controlled by a valve opening degree control device that receives a reactor pressure signal as a control input.

(作用) 上記構成の本発明非常用復水器においては、弁開度制御
装置は原子炉圧力が制御下限値以下では弁開度O%の制
御信号を発出し、制御上限値以上では弁開度100%の
制御信号を発出する。また、制御下限値Aと制御上限値
との間にある時は、原子炉圧力と前記制御下限値との差
に比例した開度を要求する制御信号を発出する。
(Function) In the emergency condenser of the present invention having the above configuration, the valve opening degree control device issues a control signal of the valve opening degree 0% when the reactor pressure is below the control lower limit value, and opens the valve when it is above the control upper limit value. Emit a control signal with 100% accuracy. Further, when the value is between the control lower limit value A and the control upper limit value, a control signal is issued that requests an opening proportional to the difference between the reactor pressure and the control lower limit value.

流量調整弁の開度は上記のように制御されるので、自然
循環に委ねて蒸気および復水の循環をさせても原子炉圧
力が過度に低下するおそれはない。
Since the opening degree of the flow rate regulating valve is controlled as described above, there is no fear that the reactor pressure will drop excessively even if the steam and condensate are circulated by natural circulation.

(実施例) 第4図と同一部分には同一符号を付した第1図は本発明
一実施例の模式図、第2図は前記実施例における隔離弁
制御器の制御特性を示す線図、第3図は前記実施例作動
時の原子炉圧力容器内の圧力変化を、従来の非常用復水
器において作業員による隔離弁操作がなされなかった場
合と比較して示す線図である。
(Embodiment) FIG. 1, in which the same parts as in FIG. 4 are given the same reference numerals, is a schematic diagram of an embodiment of the present invention, and FIG. FIG. 3 is a diagram showing the pressure change inside the reactor pressure vessel during the operation of the above-mentioned embodiment in comparison with a case where the isolation valve is not operated by a worker in a conventional emergency condenser.

第1図において、前記実施例の隔離弁7に代え流量調整
弁8が設けられ、この流量調整弁は原子炉圧力信号9を
制御入力とする弁開度制御装置10によって制御される
In FIG. 1, a flow rate adjustment valve 8 is provided in place of the isolation valve 7 of the previous embodiment, and this flow rate adjustment valve is controlled by a valve opening degree control device 10 which receives a reactor pressure signal 9 as a control input.

第2図は前記弁開度制御装置10の制御特性を示す。す
なわち、弁開度制御装置1oは原子炉圧力が制御下限値
A以下では弁開度0%の制御信号を発出し、制御上限値
B以上では弁開度100%の制御信号を発出する。また
、制御下限値Aと制御上限値Bとの間にある時は、原子
炉圧力と前記制御下限値Aとの差に比例した開度を要求
する制御信号を発出する。
FIG. 2 shows the control characteristics of the valve opening control device 10. That is, the valve opening control device 1o issues a control signal with a valve opening of 0% when the reactor pressure is below the control lower limit value A, and issues a control signal with a valve opening of 100% when it is above the control upper limit B. Further, when the control value is between the control lower limit value A and the control upper limit value B, a control signal is issued that requests an opening proportional to the difference between the reactor pressure and the control lower limit value A.

弁開度制御装置f10は上記のように流量調整弁8を制
御するから、自然循環に委ねて蒸気および復水の循環を
させても、原子炉圧力容器1内の圧力が過度に低下する
おそれはない。すなわち、本発明の非常用復水器によれ
ば第3図に実線の曲線C1で示すように、原子炉隔離事
象の発生時に一時的に原子炉圧力が上昇した後は、原子
炉圧力はほぼ一定に保持される。これに対して、第4図
に示した従来の非常用復水器において、隔離弁7の操作
がなされなかった場合には、第3図に一点鎖線の曲線C
2で示すように原子炉圧力は隔離弁7の開放後、徐々に
且つ連続的に低下していき、終には原子炉圧力容器の健
全性維持上不都合な過度の低下を示すこととなる。
Since the valve opening control device f10 controls the flow rate regulating valve 8 as described above, even if the steam and condensate are circulated by natural circulation, the pressure in the reactor pressure vessel 1 will not decrease excessively. That's not it. That is, according to the emergency condenser of the present invention, as shown by the solid curve C1 in FIG. held constant. On the other hand, in the conventional emergency condenser shown in FIG. 4, if the isolation valve 7 is not operated, the dashed line curve C in FIG.
As shown in 2, the reactor pressure gradually and continuously decreases after the isolation valve 7 is opened, and eventually shows an excessive decrease that is inconvenient for maintaining the integrity of the reactor pressure vessel.

C発明の効果コ 上記から明らかなように本発明の非常用復水器において
は、復水戻り管に流量調整弁が設けてあり、この弁の開
度を原子炉圧力との関連で制御するようにしている。そ
のため、従来の非常用復水器のように運転員の手動によ
る隔離弁の操作を必要とすることなく、M子炉圧力を適
正範囲に維持することができ、運転員の負担の軽減およ
び誤操作の防止、原子炉の安全性の向上を図ることがで
きる。
C. Effects of the Invention As is clear from the above, in the emergency condenser of the present invention, a flow rate adjustment valve is provided in the condensate return pipe, and the opening degree of this valve is controlled in relation to the reactor pressure. That's what I do. Therefore, unlike conventional emergency condensers, operators do not have to manually operate isolation valves, and the M reactor pressure can be maintained within an appropriate range, reducing the burden on operators and causing errors in operation. It is possible to prevent this and improve the safety of nuclear reactors.

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

第1図は本発明一実施例の模式図、第2図は前記実施例
における隔離弁制御器の制御特性を示す線図、第3図は
前記実施例作動時の原子炉圧力容器内の圧力変化を、従
来の非常用復水器において作業員による隔離弁操作がな
されなかった場合と比較して示す線図、第4図は従来の
非常用復水器の模式図である。 1・・・・・・原子炉圧力容器 2・・・・・・炉心 
3・・・・蒸気供給管 4・・・・・・冷却水貯蔵槽 
5  ・伝熱管束6・・・・・・復水戻り管 7・・・
・・隔離弁 8・・・流量調整弁 9・・・・・・原子
炉圧力信号 10・・・・・弁開度制御装置 A・・・
・・・制御下限値 B・・・・制御上限値C工、C2・
・・・・・曲線
Fig. 1 is a schematic diagram of one embodiment of the present invention, Fig. 2 is a diagram showing the control characteristics of the isolation valve controller in the embodiment, and Fig. 3 is the pressure inside the reactor pressure vessel during operation of the embodiment. FIG. 4 is a diagram showing changes in a conventional emergency condenser in comparison with a case where the isolation valve is not operated by a worker in a conventional emergency condenser. FIG. 4 is a schematic diagram of the conventional emergency condenser. 1...Reactor pressure vessel 2...Reactor core
3...Steam supply pipe 4...Cooling water storage tank
5 ・Heat transfer tube bundle 6... Condensate return pipe 7...
... Isolation valve 8 ... Flow rate adjustment valve 9 ... Reactor pressure signal 10 ... Valve opening control device A ...
... Control lower limit value B... Control upper limit value C, C2.
·····curve

Claims (1)

【特許請求の範囲】[Claims] 冷却水貯蔵槽と、この冷却水貯蔵槽内の伝熱管束と、こ
の伝熱管束に原子炉圧力容器内の蒸気を供給する蒸気供
給管と、前記伝熱管束において蒸気が凝結して生成され
た復水を原子炉圧力容器内に帰戻させる復水戻り管とを
有するものにおいて、前記復水戻り管に流量調整弁を設
け、この流量調整弁の開度を原子炉圧力信号を制御入力
とする弁開度制御装置により制御することを特徴とする
非常用復水器。
A cooling water storage tank, a heat transfer tube bundle in the cooling water storage tank, a steam supply pipe that supplies steam in the reactor pressure vessel to the heat transfer tube bundle, and steam condensed and generated in the heat transfer tube bundle. and a condensate return pipe for returning condensate to the reactor pressure vessel, the condensate return pipe is provided with a flow rate adjustment valve, and the opening degree of the flow rate adjustment valve is controlled and inputted using a reactor pressure signal. An emergency condenser characterized by being controlled by a valve opening control device.
JP2132560A 1990-05-24 1990-05-24 Emergency condenser Pending JPH0427896A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2132560A JPH0427896A (en) 1990-05-24 1990-05-24 Emergency condenser

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2132560A JPH0427896A (en) 1990-05-24 1990-05-24 Emergency condenser

Publications (1)

Publication Number Publication Date
JPH0427896A true JPH0427896A (en) 1992-01-30

Family

ID=15084152

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2132560A Pending JPH0427896A (en) 1990-05-24 1990-05-24 Emergency condenser

Country Status (1)

Country Link
JP (1) JPH0427896A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011174774A (en) * 2010-02-24 2011-09-08 Hitachi-Ge Nuclear Energy Ltd Isolation cooling system in nuclear power plant
JP2012013558A (en) * 2010-07-01 2012-01-19 Hitachi-Ge Nuclear Energy Ltd Isolation cooling system of nuclear power plant
JP2013140079A (en) * 2012-01-05 2013-07-18 Hitachi-Ge Nuclear Energy Ltd Reactor isolation cooler
JP2020525789A (en) * 2017-06-28 2020-08-27 ジーイー−ヒタチ・ニュークリア・エナジー・アメリカズ・エルエルシーGe−Hitachi Nuclear Energy Americas, Llc Emergency condenser for a very simplified boiling water reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011174774A (en) * 2010-02-24 2011-09-08 Hitachi-Ge Nuclear Energy Ltd Isolation cooling system in nuclear power plant
JP2012013558A (en) * 2010-07-01 2012-01-19 Hitachi-Ge Nuclear Energy Ltd Isolation cooling system of nuclear power plant
JP2013140079A (en) * 2012-01-05 2013-07-18 Hitachi-Ge Nuclear Energy Ltd Reactor isolation cooler
JP2020525789A (en) * 2017-06-28 2020-08-27 ジーイー−ヒタチ・ニュークリア・エナジー・アメリカズ・エルエルシーGe−Hitachi Nuclear Energy Americas, Llc Emergency condenser for a very simplified boiling water reactor

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