JPH03216592A - Cooling water supplying device of boiling water nuclear reactor - Google Patents

Cooling water supplying device of boiling water nuclear reactor

Info

Publication number
JPH03216592A
JPH03216592A JP2010570A JP1057090A JPH03216592A JP H03216592 A JPH03216592 A JP H03216592A JP 2010570 A JP2010570 A JP 2010570A JP 1057090 A JP1057090 A JP 1057090A JP H03216592 A JPH03216592 A JP H03216592A
Authority
JP
Japan
Prior art keywords
water
reactor
cooling system
core cooling
pressure core
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
JP2010570A
Other languages
Japanese (ja)
Inventor
Makoto Akinaga
秋永 誠
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 JP2010570A priority Critical patent/JPH03216592A/en
Publication of JPH03216592A publication Critical patent/JPH03216592A/en
Pending legal-status Critical Current

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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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To improve safety by opening an open/close valve, when a cooling water supply from a high pressure core cooling system into a nuclear reactor pressure vessel is not conducted even though the water level of the nuclear reactor lowers below a specific level by which the high pressure core cooling system should be actuated. CONSTITUTION:A flow meter 8 of a high pressure core cooling system, a water level meter 2 of a nuclear reactor and an open/close valve 13 are electrically connected to a control device 13 of the open/close valve. The control device 13 of the open/close valve feeds a flow rate signal S1 from a flow meter 8 of the high pressure core cooling system, and a water level signal S2 from the water level meter 2 of the nuclear reactor, and thereafter, in case that it is confirmed that no cooling water is supplied into a nuclear reactor vessel from the high pressure core cooling system even though the water level of the nuclear reactor lowers below a specific level by which the high pressure core cooling system should be actuated, the open/close valve 12 is controlled to be opened. Accordingly, even if function of the high pressure core cooling system is lost and pressure reduction of the nuclear reactor fails, an emergency water source in a condensate water storage tank can be used as a water source for a control rod drive mechanism and therefore safety is enhanced.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は原子炉圧力容器に冷却水を供給する沸騰水型原
子炉の冷却水補給装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Field of Application) The present invention relates to a cooling water supply system for a boiling water reactor that supplies cooling water to a reactor pressure vessel.

(従来の技術) 一般に、沸騰水型原子炉においては何等かの原因により
原子炉水位が低下した場合、原子炉を緊急停止させる原
子炉スクラム系、及び原子炉圧力容器内に非常用冷却水
を供給する非常用炉心冷却系が設置されている。
(Prior art) In general, in a boiling water reactor, when the reactor water level drops for some reason, a reactor scram system is used to make an emergency shutdown of the reactor, and emergency cooling water is pumped into the reactor pressure vessel. An emergency core cooling system has been installed to supply the reactor.

第2図は従来の沸騰水型原子炉の概略構成図を示すもの
で、図において原子炉圧力容器1内には核燃料が装荷さ
れ、ここで核エネルギを得た冷却水は蒸気となり、この
蒸気は主蒸気管を経てタービンに導かれる。さらにター
ビンを駆動した蒸気はコンデンサーにおいて復水とされ
、給水系を経て再び原子炉へ戻される。
Figure 2 shows a schematic configuration diagram of a conventional boiling water reactor. In the figure, nuclear fuel is loaded into the reactor pressure vessel 1, and the cooling water that has obtained nuclear energy here turns into steam. is led to the turbine via the main steam pipe. Furthermore, the steam that drives the turbine is condensed in a condenser and returned to the reactor via the water supply system.

以上のように構成された沸騰水型原子炉において、例え
ば給水系から原子炉への給水が停止するような異常事態
が発生した場合には、原子炉圧力容器1内の水位が低下
するため、原子炉水位計2からの水位信号により、原子
炉スクラム系が作動し制御棒駆動系によって制御棒が原
子炉に挿入されることにより原子炉は緊急停止される。
In the boiling water reactor configured as described above, if an abnormal situation occurs, such as stopping the water supply from the water supply system to the reactor, the water level in the reactor pressure vessel 1 will drop. The reactor scram system is activated by the water level signal from the reactor water level gauge 2, and the control rod drive system inserts the control rods into the reactor, thereby causing an emergency shutdown of the reactor.

制御棒駆動装置3は復水貯蔵タンク4を水源として制御
棒駆動水ポンプ5により常時復水貯蔵タンク出口配管I
llを経て供給され、結果的に冷却水は原子炉へ注水さ
れている。さらに原子炉水位が低下すると高圧炉心冷却
系が作動し、高圧炉心冷却ポンプ6により復水貯蔵タン
ク4あるいはサブレッションプール7を水源として原子
炉へ冷却水が補給される。9は高圧炉心冷却系の復水貯
蔵タンク出口配管である。さらに、高圧炉心冷却系によ
る注水が不能な場合には、原子炉を減圧させることによ
って低圧炉心冷却系によりサブレッションプール7を水
源として原子炉へ冷却水が注水される。このように、何
等かの原因により原子炉の水位が低下した場合において
も、原子炉の核反応を停止し、炉心を十分に冷却するこ
とによって原子炉は安定な状態に保たれる。
The control rod drive device 3 uses the condensate storage tank 4 as a water source and uses the control rod drive water pump 5 to constantly connect the condensate storage tank outlet piping I.
As a result, cooling water is injected into the reactor. When the reactor water level further decreases, the high-pressure core cooling system is activated, and the high-pressure core cooling pump 6 supplies cooling water to the reactor using the condensate storage tank 4 or subreduction pool 7 as a water source. 9 is a condensate storage tank outlet pipe of the high pressure core cooling system. Furthermore, if water injection by the high-pressure core cooling system is not possible, by depressurizing the reactor, cooling water is injected into the reactor by the low-pressure core cooling system using the subreduction pool 7 as a water source. In this way, even if the water level in the reactor drops for some reason, the reactor can be kept in a stable state by stopping the nuclear reaction in the reactor and sufficiently cooling the reactor core.

なお、高圧炉心冷却系への復水貯蔵タンクの出口ノズル
位置は、高圧炉心冷却系に必要な水量を非常用水源とし
て復水貯蔵タンクの底部に貯え、多系統でいかに復水補
給水を使用しても必ず水量を保持できるように、制御棒
駆動系への出口ノズル位置よりも低い位置に設置されて
いる。
The location of the outlet nozzle of the condensate storage tank to the high-pressure core cooling system is such that the amount of water required for the high-pressure core cooling system is stored at the bottom of the condensate storage tank as an emergency water source, and the condensate make-up water is used in multiple systems. It is installed at a lower position than the exit nozzle position to the control rod drive system so that the amount of water can be maintained even when the control rod drive system is in use.

(発明が解決しようとする課題) 以上のように構成された沸騰水型原子炉において、例え
ば給水系からの原子炉への給水が停止し原子炉圧力容器
内の水位が低下するような異常事態が発生した場合に、
何等かの原因により高圧炉心冷却系による原子炉への注
水が不能となり、かつ原子炉の減圧にも失敗した場合に
おいても、制御棒駆動系からの冷却水の補給によって原
子炉はある程度冷却される。しかしながら、その後復水
貯蔵タンクへの冷却水補給が行われずに復水貯蔵タンク
水位が制御棒駆動系への出口ノズル位置まで低下すると
、復水貯蔵タンクの底部には非常用水源が保持されてい
るにもかかわらず、制御棒駆動系からの原子炉への補給
水も喪失し、その結果炉心の冷却が不十分となり炉心損
傷を招く恐れがある。
(Problems to be Solved by the Invention) In a boiling water reactor configured as described above, an abnormal situation occurs in which, for example, water supply from the water supply system to the reactor stops and the water level in the reactor pressure vessel decreases. If this occurs,
Even if water injection into the reactor by the high-pressure core cooling system becomes impossible for some reason and reactor depressurization also fails, the reactor will be cooled to some extent by replenishing cooling water from the control rod drive system. . However, if cooling water is not refilled to the condensate storage tank after that and the water level of the condensate storage tank drops to the outlet nozzle position to the control rod drive system, an emergency water source is maintained at the bottom of the condensate storage tank. Despite this, make-up water from the control rod drive system to the reactor is also lost, resulting in insufficient cooling of the reactor core, which may lead to core damage.

本発明はかかる事情に対処してなされたもので、原子炉
圧力容器内の水位が低下するような異常事態が発生し、
高圧炉心冷却系の機能が喪失し、原子炉の減圧に失敗す
るような事故に至った場合においても、復水貯蔵タンク
の非常用水源を制御棒駆動系の水源として利用でき、原
子炉の安全性を向上させる沸騰水型原子炉の冷却水補給
装置を提供することを目的とするものである。
The present invention was made in response to such circumstances, and when an abnormal situation occurs such as a drop in the water level in the reactor pressure vessel,
Even in the event of an accident in which the high-pressure core cooling system loses its function and fails to depressurize the reactor, the emergency water source in the condensate storage tank can be used as a water source for the control rod drive system, ensuring the safety of the reactor. The object of the present invention is to provide a cooling water replenishment device for a boiling water reactor that improves performance.

[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、本発明の沸騰水型原子炉の
冷却水補給装置は、高圧炉心冷却系への復水貯蔵タンク
出口配管と制御棒駆動系への復水貯蔵タンク出口配管と
を接続する通常閉なる開閉弁の配設された連結管と、原
子炉水位計信号と高圧炉心冷却系の流量信号とを入力し
、原子炉水位が高圧炉心冷却系が作動すべき所定水位よ
り低下したにもかかわらず高圧炉心冷却系から原子炉圧
力容器内への冷却水供給が実施されない時に前記開閉弁
を開とする制御装置を備えたことを特徴とするものであ
る。
[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the boiling water reactor cooling water replenishment system of the present invention includes condensate storage tank outlet piping to the high-pressure core cooling system. Input the connecting pipe equipped with a normally closed on-off valve that connects the condensate storage tank outlet pipe to the control rod drive system, the reactor water level gauge signal, and the flow rate signal of the high-pressure core cooling system. A control device is provided that opens the on-off valve when cooling water is not supplied from the high-pressure core cooling system into the reactor pressure vessel even though the water level has fallen below a predetermined water level at which the high-pressure core cooling system should operate. It is characterized by this.

(作 用) 本発明の沸騰水型原子炉の冷却水補給装置によれば、原
子炉圧力容器内の水位が低下するような異常事態が発生
し、高圧炉心冷却系の機能が喪失し、原子炉の減圧に失
敗するような事故に至り、復水貯蔵タンクへの冷却水の
補給が実施されない場合においても、復水貯蔵タンクの
非常用水源を制御棒駆動系の水源として利用可能となり
、制御棒駆動系による原子炉への冷却水補給可能な時間
を延長することができる。
(Function) According to the boiling water reactor cooling water replenishment system of the present invention, an abnormal situation such as a drop in the water level in the reactor pressure vessel occurs, the function of the high pressure core cooling system is lost, and the Even if an accident occurs in which the reactor fails to depressurize and cooling water is not refilled to the condensate storage tank, the emergency water source in the condensate storage tank can be used as a water source for the control rod drive system, allowing control It is possible to extend the time during which cooling water can be supplied to the reactor by the rod drive system.

(実施例) 以下、本発明の実施例を図面を参照して説明する。(Example) Embodiments of the present invention will be described below with reference to the drawings.

第1図は本発明の一実施例の概略構成図である。FIG. 1 is a schematic diagram of an embodiment of the present invention.

同図に示すように、原子尿圧力容器1内には核燃料が装
荷され、ここで核エネルギを得た冷却水は蒸気となり、
この蒸気は主蒸気管を経てタービンに導かれる。タービ
ンを駆動した蒸気はコンデンサーにおいて復水とされ、
給水系を経て再び原子炉へ戻される。
As shown in the figure, nuclear fuel is loaded into the nuclear urine pressure vessel 1, and the cooling water that has obtained nuclear energy becomes steam.
This steam is led to the turbine via the main steam pipe. The steam that drove the turbine is condensed in a condenser,
It is returned to the reactor via the water supply system.

以上のように構成された沸騰水型原子炉において、例え
ば給水系から原子炉への給水が停止するような異常事態
が発生した場合には、原子炉圧力容器1内の水位が低下
するため、原子炉水位計2からの水位信号により、原子
炉スクラム系が作動し制御棒駆動系によって制御棒が原
子炉に挿入される、原子炉は緊急停止される。制御棒駆
動装置3は復水貯蔵タンク4を水源として制御棒駆動水
ポンプ5により常時冷却水が供給され、結果的に冷却水
は原子炉へ注水されている。さらに原子炉水位が低下す
ると高圧炉心冷却系が作動し、高圧炉心冷却ポンプ6に
より復水貯蔵タンク4あるいはサブレッションプール7
を水源として原子炉へ冷却水が補給される。さらに、高
圧炉心冷却系による注水が不能な場合には、原子炉を減
圧させることによって低圧炉心冷却系によりサブレッシ
ョンプール7を水源として原子炉へ冷却水が注水される
In the boiling water reactor configured as described above, if an abnormal situation occurs, such as stopping the water supply from the water supply system to the reactor, the water level in the reactor pressure vessel 1 will drop. In response to the water level signal from the reactor water level gauge 2, the reactor scram system is activated and the control rod drive system inserts the control rods into the reactor, and the reactor is brought to an emergency shutdown. The control rod driving device 3 is constantly supplied with cooling water by a control rod driving water pump 5 using a condensate storage tank 4 as a water source, and as a result, cooling water is injected into the reactor. When the reactor water level further decreases, the high-pressure core cooling system is activated, and the high-pressure core cooling pump 6 is activated by the condensate storage tank 4 or the subrection pool 7.
Cooling water is supplied to the reactor using this water source. Furthermore, if water injection by the high-pressure core cooling system is not possible, by depressurizing the reactor, cooling water is injected into the reactor by the low-pressure core cooling system using the subreduction pool 7 as a water source.

上記したように、何等かの原因により原子炉の水位が低
下した場合においても、原子炉の核反応を停止させ、炉
心を十分に冷却することによって原子炉は安定な状態に
保たれる。
As mentioned above, even if the water level in the reactor drops for some reason, the reactor can be kept in a stable state by stopping the nuclear reaction in the reactor and sufficiently cooling the reactor core.

ところで、本実施例では、さらに高圧炉心冷却系の復水
貯蔵タンク出口配管9と制御棒駆動系への復水貯蔵タン
ク出口配管IOは連結管11によって接続されており、
この連結管11には通常閉なる開閉弁l2が配設されて
いる。開閉弁制御装置13には高圧炉心冷却系の流量計
8、原子炉水位計2及び開閉弁I2が電気的に接続され
ている。すなわち、開閉弁制御装置13は高圧炉心冷却
系の流量計8からの流量信号S1と原子炉水位計2から
の水位信号S2を入力し、原子炉水位が高圧炉心冷却系
が作動すべき所定の水位より低下したにもかかわらず高
圧炉心冷却系からの原子炉容器内への冷却水供給がない
ことが確認された場合には、開閉弁12を開となるよう
に制御する。
By the way, in this embodiment, the condensate storage tank outlet pipe 9 of the high-pressure core cooling system and the condensate storage tank outlet pipe IO to the control rod drive system are further connected by a connecting pipe 11.
This connecting pipe 11 is provided with an on-off valve l2 that is normally closed. A high-pressure core cooling system flow meter 8, a reactor water level gauge 2, and an on-off valve I2 are electrically connected to the on-off valve control device 13. That is, the on-off valve control device 13 inputs the flow rate signal S1 from the flow meter 8 of the high-pressure core cooling system and the water level signal S2 from the reactor water level gauge 2, and adjusts the reactor water level to a predetermined level at which the high-pressure core cooling system should operate. If it is confirmed that there is no cooling water supplied into the reactor vessel from the high-pressure core cooling system even though the water level has fallen below the water level, the on-off valve 12 is controlled to be opened.

本実施例は上記したように構成されているので、原子炉
圧力容器内の水位が低下するような異常事態が発生し、
高圧炉心冷却系の機能が喪失し、原子炉の減圧に失敗す
るような事故に至り、復水貯蔵タンクへの冷却水の補給
が実施されない場合においても、復水貯蔵タンクの非常
用水源を制御棒駆動系の水源として利用することが可能
となり、制御棒駆動系による原子炉へ冷却水補給の持続
時間が延長され、炉心の健全性の信頼性を向上させるこ
とができる。
Since this embodiment is configured as described above, an abnormal situation such as a drop in the water level in the reactor pressure vessel may occur.
Controls the emergency water source of the condensate storage tank even in the event of an accident in which the high-pressure core cooling system loses its function and fails to depressurize the reactor, and cooling water is not refilled to the condensate storage tank. It becomes possible to use it as a water source for the rod drive system, extending the duration of cooling water supply to the reactor by the control rod drive system, and improving the reliability of the core health.

[発明の効果] 以上説明したように、本発明の沸騰水型原子炉の冷却水
補給装置によれば、原子炉圧力容器内の水位が低下する
ような異常事態が発生し、高圧炉心冷却系の機能が喪失
し、原子炉の減圧に失敗するような事故に至り、復水貯
蔵タンクへの冷却水の補給が実施されない場合において
も、制御棒駆動系による原子炉へ冷却水補給が長時間可
能となり、従来に比べて安全性を向上させることができ
るので、原子炉の信頼性の向上に繋がる。
[Effects of the Invention] As explained above, according to the boiling water reactor cooling water replenishment system of the present invention, an abnormal situation such as a drop in the water level in the reactor pressure vessel occurs, and the high pressure core cooling system Even if an accident occurs in which the reactor loses its function and fails to depressurize the reactor, and the condensate storage tank is not refilled with cooling water, the control rod drive system will not be able to replenish the reactor with cooling water for a long time. This makes it possible to improve safety compared to conventional methods, leading to improved reliability of nuclear reactors.

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

第1図は本発明の一実施例の概略構成図、第2図は従来
の沸騰水型原子炉の冷却水補給装置の概略構成図である
。 1・・・原子炉圧力容器 2・・・水位計 3・・・制御棒駆動装置 4・・・復水貯蔵タンク 5・・・制御棒駆動ポンプ 6・・・高圧炉心冷却ポンプ 7・・・サブレッションプール 8・・・流量計 9・・・高圧炉心冷却系配管 10・・・制御棒駆動系配管 11・・・連結管 12・・・開閉弁 I3・・・制御装置 (8733)代理人 弁理士 猪 股 祥(ほか 1名)
FIG. 1 is a schematic diagram of an embodiment of the present invention, and FIG. 2 is a schematic diagram of a conventional boiling water reactor cooling water supply system. 1...Reactor pressure vessel 2...Water level gauge 3...Control rod drive device 4...Condensate storage tank 5...Control rod drive pump 6...High pressure core cooling pump 7... Subrection pool 8...Flow meter 9...High pressure core cooling system piping 10...Control rod drive system piping 11...Connecting pipe 12...Opening/closing valve I3...Control device (8733) agent Patent attorney Sho Inomata (and 1 other person)

Claims (1)

【特許請求の範囲】[Claims] (1)復水貯蔵タンク水を原子炉圧力容器内へ供給する
高圧炉心冷却系への復水貯蔵タンク出口配管と、復水貯
蔵タンク水を制御棒駆動装置へ供給する制御棒駆動系へ
の復水貯蔵タンク出口配管と、前記両復水貯蔵タンク出
口配管を接続する通常閉なる開閉弁の配設された連結管
と、原子炉水位計からの水位信号と高圧炉心冷却系の流
量信号とを入力し、原子炉水位が高圧炉心冷却系が作動
すべき所定の水位より低下したにもかかわらず高圧炉心
冷却系から原子炉圧力容器内への冷却水供給が実施され
ない時に前記開閉弁を開とする制御装置とを備えたこと
を特徴とする沸騰水型原子炉の冷却水補給装置。
(1) Condensate storage tank outlet piping to the high-pressure core cooling system that supplies condensate storage tank water into the reactor pressure vessel, and condensate storage tank outlet piping to the control rod drive system that supplies condensate storage tank water to the control rod drive device. A condensate storage tank outlet pipe, a connecting pipe with a normally closed on-off valve that connects the condensate storage tank outlet pipes, a water level signal from a reactor water level gauge, and a flow rate signal of a high pressure core cooling system. is input, and the on-off valve is opened when cooling water is not being supplied from the high pressure core cooling system to the reactor pressure vessel even though the reactor water level has fallen below the predetermined water level at which the high pressure core cooling system should operate. A cooling water supply system for a boiling water reactor, characterized in that it is equipped with a control device.
JP2010570A 1990-01-22 1990-01-22 Cooling water supplying device of boiling water nuclear reactor Pending JPH03216592A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2010570A JPH03216592A (en) 1990-01-22 1990-01-22 Cooling water supplying device of boiling water nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2010570A JPH03216592A (en) 1990-01-22 1990-01-22 Cooling water supplying device of boiling water nuclear reactor

Publications (1)

Publication Number Publication Date
JPH03216592A true JPH03216592A (en) 1991-09-24

Family

ID=11753901

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2010570A Pending JPH03216592A (en) 1990-01-22 1990-01-22 Cooling water supplying device of boiling water nuclear reactor

Country Status (1)

Country Link
JP (1) JPH03216592A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015040809A (en) * 2013-08-23 2015-03-02 中国電力株式会社 Emergency reactor core cooling backup system
CN105788670A (en) * 2016-06-01 2016-07-20 中国核动力研究设计院 Improved structure of reactor core water compensating box simulator

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015040809A (en) * 2013-08-23 2015-03-02 中国電力株式会社 Emergency reactor core cooling backup system
CN105788670A (en) * 2016-06-01 2016-07-20 中国核动力研究设计院 Improved structure of reactor core water compensating box simulator

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