JPS60259995A - Emergency core cooling device - Google Patents

Emergency core cooling device

Info

Publication number
JPS60259995A
JPS60259995A JP59115414A JP11541484A JPS60259995A JP S60259995 A JPS60259995 A JP S60259995A JP 59115414 A JP59115414 A JP 59115414A JP 11541484 A JP11541484 A JP 11541484A JP S60259995 A JPS60259995 A JP S60259995A
Authority
JP
Japan
Prior art keywords
reactor
pressure vessel
storage tank
water storage
water
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
JP59115414A
Other languages
Japanese (ja)
Inventor
治 菊池
石山 武則
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 JP59115414A priority Critical patent/JPS60259995A/en
Publication of JPS60259995A publication Critical patent/JPS60259995A/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

  • Heating, Cooling, Or Curing Plastics Or The Like In General (AREA)
  • Details Of Measuring And Other Instruments (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】 〔発明の技術分野〕 この発明は沸騰水型原子炉・加圧水型原子炉および自然
循環型原子炉などの水冷却タイプの軽水型原子炉におけ
る非常用炉心冷却装置に係り、特に−次系配管破断等の
冷却材喪失事故時に冷却材を積極的に補給するようにし
た非常用炉心冷却装置に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] This invention relates to an emergency core cooling system for water-cooled light water reactors such as boiling water reactors, pressurized water reactors, and natural circulation reactors. In particular, the present invention relates to an emergency core cooling system that actively replenishes coolant in the event of a loss of coolant accident such as a rupture of secondary system piping.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

一般に軽水型原子炉は水を冷却材として利用したもので
、沸騰水型原子炉・加圧水型原子炉および自然循環型原
子炉などに大別される。このうち、自然循環型原子炉は
、第4図に示すように構成され、原子炉圧力容器1内に
円筒状のシュラウド2が同心的に配設され、このシュラ
ウド2内に核燃利を装架した炉心3が形成される。炉心
3の上方にはライザ部4が形成され、このライザ部4を
介して、制御棒駆動機構5により制御棒が炉心3に出し
入れされ、炉出力が調節される。
Generally, light water reactors use water as a coolant and are broadly divided into boiling water reactors, pressurized water reactors, natural circulation reactors, etc. Among these, the natural circulation reactor is constructed as shown in Fig. 4, in which a cylindrical shroud 2 is disposed concentrically within a reactor pressure vessel 1, and nuclear fuel is installed within this shroud 2. A reactor core 3 is formed. A riser section 4 is formed above the reactor core 3, and a control rod drive mechanism 5 moves control rods into and out of the reactor core 3 via the riser section 4, thereby adjusting the reactor power.

一方、原子炉圧力容器1の内周壁面とシュラウド2との
間に横断面環状のダウンカマ部6が画成され、このダウ
ンカマ部6の上方に複数の熱交換器7が設りられる。
On the other hand, a downcomer section 6 having an annular cross section is defined between the inner peripheral wall surface of the reactor pressure vessel 1 and the shroud 2, and a plurality of heat exchangers 7 are provided above the downcomer section 6.

しかして、原子炉圧力容器1内に充填された冷却材は、
炉心3で発生した熱により加熱されて沸騰しつつライザ
部4を通って上昇し、ここで発生しIC蒸気は熱交換器
7で熱交換されて凝縮し、ダウンカマ部6に落下せしめ
られる。
Therefore, the coolant filled in the reactor pressure vessel 1 is
The IC steam is heated by the heat generated in the reactor core 3 and rises through the riser section 4 while boiling, and the IC steam generated here is heat exchanged in the heat exchanger 7, condensed, and falls into the downcomer section 6.

ダウンカマ部6に落下せしめられた凝縮水は、この部分
の冷却材と炉心3およびライザ部4の浴却材との間の密
度差により駆動力が生じ、この結果原子炉圧力容器1内
の冷却材は自然循環せしめられる。この自然循環により
、ダウンカマ部6の冷却材は下降して炉心の下部に案内
され、続いて炉心下部から炉心3内に流入せしめられる
The condensed water that has fallen into the downcomer section 6 generates a driving force due to the density difference between the coolant in this section and the bath coolant in the reactor core 3 and riser section 4, and as a result, the cooling inside the reactor pressure vessel 1 is reduced. The wood is allowed to circulate naturally. Due to this natural circulation, the coolant in the downcomer section 6 descends and is guided to the lower part of the reactor core, and then flows into the reactor core 3 from the lower part of the reactor core.

このような原子炉において、1次系配管の破断等による
冷却材喪失事故時には非常用炉心冷却系が作動し、原子
炉の炉心冷却を充分に行ない、核燃料棒の健全性を維持
するようになっている。従来の非常用炉心冷却系8は第
5図に示すように原子炉圧力容器1よりも高所に冷却材
貯水タンク9が設置されており、貯溜タンク9内の冷却
材を重力によって、非常用炉心冷却系配管9aを通して
原子炉圧力容器1内に補給し、冷却材喪失事故時にも、
炉心冠水状態を保つように構成されている。
In such reactors, in the event of a loss of coolant accident due to a rupture in the primary system piping, the emergency core cooling system is activated to sufficiently cool the reactor core and maintain the integrity of the nuclear fuel rods. ing. In the conventional emergency core cooling system 8, as shown in FIG. 5, a coolant water storage tank 9 is installed at a higher place than the reactor pressure vessel 1. It is supplied into the reactor pressure vessel 1 through the core cooling system piping 9a, and even in the event of a loss of coolant accident,
It is configured to maintain the core flooding condition.

しかしながら、冷却材貯水タンク9は上端が開放されて
いるため、重力作用による冷却材の供給だけでは、必ず
しも充分に冷却材を補給することができず、原子炉圧ノ
j容器1内の圧力が充分に下がるまで冷却材を供給する
ことができなかった。
However, since the upper end of the coolant storage tank 9 is open, it is not always possible to replenish the coolant sufficiently just by supplying the coolant by gravity, and the pressure inside the reactor pressure vessel 1 increases. It was not possible to supply coolant until it was sufficiently low.

また、冷却材供給開始後の冷却材流量は、原子炉圧力容
器1内の圧力が貯水タンク9内の圧力を土石るため、次
第に減少し、冷却材の迅速かつ充分な供給が行なわれな
い恐れがあった。
In addition, the flow rate of coolant after the start of coolant supply gradually decreases because the pressure in the reactor pressure vessel 1 overwhelms the pressure in the water storage tank 9, and there is a risk that the coolant will not be supplied quickly and sufficiently. was there.

〔発明の目的〕[Purpose of the invention]

この発明は上述した事情を8虞してなされたもので、冷
却材喪失事故時には原子炉圧力容器内の圧ノj如何にか
かわらず、この圧力容器内に冷却材を充分かつ迅速に補
給さゼることかでき、原子炉の信頼性、安全性を向上さ
せた非常用炉心冷却装置を提供することを目的とする。
This invention was made in consideration of the above-mentioned circumstances, and it is designed to ensure that, in the event of a loss of coolant accident, coolant is sufficiently and quickly replenished into the reactor pressure vessel regardless of the pressure inside the reactor pressure vessel. The purpose is to provide an emergency core cooling system that can improve the reliability and safety of a nuclear reactor.

C発明のf、?要〕 この発明は、上述した目的を達成J−るために、原子炉
圧力容器よりも高所に非富用炉心冷W系貯水タンクを設
置づるとともに、上記貯水タンクと原子炉圧力容器とを
注水弁を備えた注水配管で接続し、原子炉の冷却材喪失
事故時に、注水弁を開さ゛、重力作用により貯水タンク
内の冷却材を原子炉圧力容器内に補給するようにした非
常用炉心、冷ノJI装置にa5いて、前記貯水タンクは
、密閉形圧力容器として構成され、均圧管を介して原子
炉圧力容器に連通され、前記貯水タンクを原子炉圧力容
器内とほぼ同じ圧力に常時保つようにしたものである。
C invention f,? Summary] In order to achieve the above-mentioned object, this invention installs a non-rich core cold W system water storage tank at a higher location than the reactor pressure vessel, and also connects the water storage tank and the reactor pressure vessel. An emergency reactor core that is connected by water injection piping equipped with a water injection valve, and in the event of a reactor loss of coolant accident, the water injection valve is opened and the coolant in the water storage tank is replenished into the reactor pressure vessel by the action of gravity. , in the cold JI equipment, the water storage tank is configured as a closed pressure vessel, and is communicated with the reactor pressure vessel via a pressure equalization pipe, so that the water storage tank is always maintained at approximately the same pressure as the inside of the reactor pressure vessel. It was designed to be kept.

(発明の実施例) 以下、この発明に係る非常用炉心冷却装置の一実施例に
ついて添付図面を参照して説明する。
(Embodiment of the Invention) Hereinafter, an embodiment of the emergency core cooling system according to the present invention will be described with reference to the accompanying drawings.

第1図において符号1oは沸騰水型原子炉や自然循環型
原子炉等の軒水型原子炉の原子炉圧力容器を示し、この
原子炉圧力容器10に非常用炉心冷却装置11が設【プ
られる。非常用炉心冷却装置11は原子炉圧力容器10
より高所に設置された冷却材貯水タンク12を有し、こ
の貯水タンク12の底部には非常用炉心冷却系配管とし
ての注水配管13が接続されている。注水配@13は途
中に注水弁14が設(プられ、その他端は原子炉圧力容
器10の下部側壁に接続され、貯水タンク12と原子炉
圧力容器10とが連通可能に保持される。
In FIG. 1, reference numeral 1o indicates a reactor pressure vessel of an eaves water type nuclear reactor such as a boiling water type reactor or a natural circulation type reactor, and an emergency core cooling system 11 is installed in this reactor pressure vessel 10. It will be done. The emergency core cooling system 11 is a reactor pressure vessel 10
It has a coolant water storage tank 12 installed at a higher location, and a water injection pipe 13 as an emergency core cooling system pipe is connected to the bottom of this water storage tank 12. A water injection valve 14 is provided in the middle of the water injection distribution @ 13, and the other end is connected to the lower side wall of the reactor pressure vessel 10, so that the water storage tank 12 and the reactor pressure vessel 10 are maintained in communication with each other.

注水配管13は貯水タンク12がら原子炉圧力容器10
に向って連続して下向きあるいは部分的に水平方向に配
設される。
The water injection pipe 13 is connected to the reactor pressure vessel 10 from the water storage tank 12.
It is arranged continuously downward or partially horizontally.

一方、貯水タンク12は密閉形状の圧力容器からなり、
タンク頂部は均圧管15を介して原子炉圧力容器10の
上部側壁に接続される。均圧管15はタンク頂部から上
方に延びる立上り管15aど、この立上り管15aの上
端からこれに続く立下り管15bとを有し、立下り管1
5bの他端は原子炉圧力容器10の上部側壁に、通常の
水面レベルより上方位置で接続されている。この接続に
より、貯水タンク12内は原子炉圧力容器10内の圧ツ
ノとほぼ同圧に保たれる。
On the other hand, the water storage tank 12 consists of a sealed pressure vessel,
The top of the tank is connected to the upper side wall of the reactor pressure vessel 10 via a pressure equalization pipe 15. The pressure equalizing pipe 15 has a riser pipe 15a extending upward from the top of the tank, and a fall pipe 15b continuing from the upper end of the riser pipe 15a.
The other end of 5b is connected to the upper side wall of the reactor pressure vessel 10 at a position above the normal water level. With this connection, the pressure inside the water storage tank 12 is maintained at approximately the same pressure as the pressure horn inside the reactor pressure vessel 10.

次に、非常用炉心冷却装置の作用について説明する。Next, the operation of the emergency core cooling system will be explained.

通常の原子炉運転時には、非常用炉心冷却装置11の注
水配管13、貯水タンク12および立上り管15aは冷
却水で満されており、貯水タンク12と原子炉圧ノ〕容
器10とは均圧管15としての立上り管15aおよび立
下り管15bで連通され、はぼ同じ圧力に保たれる。こ
のとき、原子炉圧力容器10内の冷却材は炉心(図示せ
ず)での発熱作用によって高温になり、発生ずる蒸気は
その圧力の飽和温度となっている。
During normal reactor operation, the water injection pipe 13, water storage tank 12, and riser pipe 15a of the emergency core cooling system 11 are filled with cooling water, and the water storage tank 12 and the reactor pressure container 10 are filled with the pressure equalization pipe 15. They are communicated by a rising pipe 15a and a falling pipe 15b, and are maintained at approximately the same pressure. At this time, the coolant in the reactor pressure vessel 10 reaches a high temperature due to heat generation in the reactor core (not shown), and the generated steam has a saturation temperature of its pressure.

一方、貯水タンク12は、タンク周辺の温度と等しいた
め、立上り管15aおよび立下り管15b内の蒸気は冷
却されて若干凝縮するが、立上り管15aは細いので貯
水タンク12内への凝縮水による熱移動は充分に阻止さ
れる。このため、立上り管15aの水面では飽和温度近
くなるが、貯水タンク12内の水温は周囲温度とほぼ等
しく、充分に低い温度に保たれる。
On the other hand, since the temperature of the water storage tank 12 is equal to the temperature around the tank, the steam in the riser pipe 15a and the fall pipe 15b is cooled and slightly condensed. Heat transfer is largely prevented. Therefore, although the water surface of the riser pipe 15a is close to the saturation temperature, the water temperature in the water storage tank 12 is maintained at a sufficiently low temperature that is approximately equal to the ambient temperature.

また、原子炉の運転時には、立上り管15aに蒸気凝縮
水が次第にたまっていくため、立上り管15a内の水面
レベルは次第に上昇して上端に達する。それ以後の凝縮
水は立下り管15bから原子炉圧力容器10内に戻され
るため、水面レベルは立上り管15aの上端位置に維持
さ、れる。
Further, during operation of the nuclear reactor, steam condensed water gradually accumulates in the riser pipe 15a, so the water level in the riser pipe 15a gradually rises and reaches the upper end. Since the condensed water thereafter is returned into the reactor pressure vessel 10 from the down pipe 15b, the water surface level is maintained at the upper end position of the rise pipe 15a.

しかして、何らかの原因で1次系配管等が破断し、冷却
材喪失事故が発生すると、この冷却材喪失事故を検知し
て注水弁14が直ちに開かれる。
If the primary system piping or the like breaks for some reason and a coolant loss accident occurs, the coolant loss accident is detected and the water injection valve 14 is immediately opened.

注水弁14が開かれると、貯水タンク12および原子炉
圧力容器10内の圧力は均一であるので水頭差に基づく
重力作用により、貯水タンク12内の水は、原子炉圧力
容器10内に直ちに流入せしめられる。
When the water injection valve 14 is opened, the pressure in the water storage tank 12 and the reactor pressure vessel 10 is uniform, so the water in the water storage tank 12 immediately flows into the reactor pressure vessel 10 due to gravity based on the water head difference. I am forced to do it.

したがって、1次系配管破断後の冷却材の供給量は、第
2図に実線の冷却材供給曲線Aで示されるように安定的
に原子炉圧力容器10内に補給される。7J′なわち、
非常用炉心冷却装置11を第1図に示したように構成す
ることにより、1点鎖線Bで示される原子炉圧ノ〕容器
10内の圧力変化にかかわらず、常時はぼ一定流量の冷
却材が原子炉圧力容器10内に安定的に流入せしめられ
る。従来の原子炉におりる冷却材供給曲線は破線Cで示
される通りであり、原子炉圧力容器10内の圧力が充分
に下がらないと、冷却材の供給が開始されなかった。
Therefore, the amount of coolant supplied after the primary system piping is ruptured is stably replenished into the reactor pressure vessel 10, as shown by the solid line coolant supply curve A in FIG. 7J′, that is,
By configuring the emergency core cooling system 11 as shown in FIG. 1, a nearly constant flow of coolant is always maintained regardless of pressure changes in the reactor pressure vessel 10, which is indicated by a dashed line B. is allowed to stably flow into the reactor pressure vessel 10. The coolant supply curve for a conventional nuclear reactor is as shown by the broken line C, and the supply of coolant was not started until the pressure within the reactor pressure vessel 10 was sufficiently lowered.

また、非常用炉心冷却装置11を第1図に示すように構
成することにより、原子炉圧力容器10内の圧力が高い
時期にも、貯水タンク12内の冷却材は原子炉圧力容器
10内に安定的かつスムーズに供給される。このため、
原子炉圧力容器10内の炉水位低下を第3図に実線りで
示すように最小限に押えることができる。従来の原子炉
プラン1−においては点線Eで示すように炉水位が低下
し、炉心(炉心の最上部は1点鎖線Fで表わされている
。)が露呈する恐れがあった。しかし、この発明におい
ては、原子炉圧力容器10内の炉水位の低下を最小限に
押えることができるので、炉心の冷却を有効的に行なう
ことができ、また、炉水位の回復に要する時間も短縮さ
れる。
Furthermore, by configuring the emergency core cooling system 11 as shown in FIG. Stable and smooth supply. For this reason,
The drop in the reactor water level in the reactor pressure vessel 10 can be kept to a minimum as shown by the solid line in FIG. In the conventional reactor plan 1-, the reactor water level decreased as shown by the dotted line E, and there was a risk that the reactor core (the top of the core is represented by the dashed line F) would be exposed. However, in the present invention, since the drop in the reactor water level in the reactor pressure vessel 10 can be suppressed to a minimum, the core can be cooled effectively, and the time required for recovering the reactor water level can also be reduced. be shortened.

なお、この発明の一実施例では、非常用炉心冷却装置を
沸騰水型原子炉や自然循環型原子炉に適用した例につい
て説明したが、この冷却装置は加圧木型原子炉にも同様
に適用することができる。
In one embodiment of the present invention, an example in which the emergency core cooling system is applied to a boiling water reactor or a natural circulation reactor has been described, but this cooling system can also be applied to a pressurized wooden reactor. Can be applied.

〔発明の効果〕〔Effect of the invention〕

以上に述べたようにこの発明に係る非常用炉心冷却装置
は、貯水タンクが密閉形圧力容器として構成され、上記
貯水タンクは均圧管を介して原子炉圧力容器と接続され
、貯水タンクを原子炉圧力容器内とほぼ同じ圧力に保つ
ようにしたから、原子炉の冷却材喪失事故時には、原子
炉圧力容器内の圧力如何にかかわらず、貯水タンク内の
冷却水を重力作用により安定的かつスムーズに原子炉圧
力容器内に補給することができ、原子炉圧力容器内の炉
水位の低下を最小限に押えることができる。
As described above, in the emergency core cooling system according to the present invention, the water storage tank is configured as a closed pressure vessel, the water storage tank is connected to the reactor pressure vessel via a pressure equalizing pipe, and the water storage tank is connected to the reactor pressure vessel. Since the pressure is maintained at almost the same level as inside the pressure vessel, in the event of a reactor loss of coolant accident, the cooling water in the water storage tank can be stably and smoothly supplied by gravity, regardless of the pressure inside the reactor pressure vessel. It can be replenished into the reactor pressure vessel, and the drop in the reactor water level in the reactor pressure vessel can be kept to a minimum.

したがって、原子炉の炉心部を積極的に冷却し、炉心部
の過熱現象を未然にかつ確実に防止できる。
Therefore, the core of the nuclear reactor can be actively cooled and overheating of the core can be prevented in advance and reliably.

また、原子炉の冷却材喪失事故時に貯水タンク内の多量
の冷却材を迅速かつスムーズに原子炉圧ツノ容器内に供
給することができるので、炉水位回復に要する時間を短
縮させることができる。
Further, in the event of a reactor loss of coolant accident, a large amount of coolant in the water storage tank can be quickly and smoothly supplied into the reactor pressure vessel, thereby reducing the time required to recover the reactor water level.

さらに、貯水タンク内の冷却材を供給するのに、ポンプ
等の動力を必要としないため、信頼性が高く、原子炉の
安全性を向上させることができる。
Furthermore, since no power such as a pump is required to supply the coolant in the water storage tank, reliability is high and the safety of the nuclear reactor can be improved.

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

第1図はこの発明に係る非常用炉心冷却装置の一実施例
を示す図、第2図は原子炉の冷却材喪失事故時における
貯水タンクからの冷却材供給量の変化を示すグラフ、第
3図は原子炉の冷却材喪失事故時における原子炉圧力容
器内の炉水位の変化を示すグラフ、第4図は軽水型原子
炉としての従来の自然循環型原子炉を示す縦断面図、第
5図は従来の非常用炉心冷却装置を示す図である。 10・・・原子炉圧力容器、11・・・非常用炉心冷却
装置、12・・・貯水タン汐・′、13・・・注水配管
、14・・・注水弁、15・・・均圧管、15a・・・
立上り管、15b・・・立上り管。 出願人代理人 波多野 久 第1図 第2図 第3図 石序1木斤イ表峙間(1) 第4図 第5図
FIG. 1 is a diagram showing an embodiment of the emergency core cooling system according to the present invention, FIG. 2 is a graph showing changes in the amount of coolant supplied from a water storage tank during a loss of coolant accident in a nuclear reactor, and FIG. Figure 4 is a graph showing changes in reactor water level in the reactor pressure vessel during a reactor loss of coolant accident, Figure 4 is a vertical cross-sectional view showing a conventional natural circulation reactor as a light water reactor, Figure 5 The figure shows a conventional emergency core cooling system. DESCRIPTION OF SYMBOLS 10... Reactor pressure vessel, 11... Emergency core cooling system, 12... Water tank Shio, 13... Water injection pipe, 14... Water injection valve, 15... Pressure equalization pipe, 15a...
Rising pipe, 15b... rising pipe. Applicant's agent Hisashi Hatano Figure 1 Figure 2 Figure 3 Stone sequence 1 Wood surface (1) Figure 4 Figure 5

Claims (1)

【特許請求の範囲】 1、原子炉圧力容器よりも高所に非常用炉心冷却系貯水
タンクを設置するとともに、上記貯水タンクと原子炉圧
力容器とを注水弁を備えた注水配管で接続し、原子炉の
冷却材喪失事故時に、注水弁を開き、重力作用により貯
水タンク内の冷却材を原子炉圧力容器内に補給するよう
にした非常用炉心冷却装置において、前記貯水タンクは
、密閉形圧力容器どして構成され、均圧管を介して原子
炉圧力容器に連通され、前記貯水タンクを原子炉圧力容
器内とほぼ同じ圧力に常時保つようにしたことを特徴と
する非常用炉心冷却装置。 2、均圧管は貯水タンクの頂部から上方に延びる立上り
管と、この立上り管の上端から続く立下り管とを有する
特許請求の範囲第1項に記載の非常用炉心冷却装置。 3、均圧管は貯水タンクの頂部から延び、その先端が原
子炉圧力容器の上部側壁に、その圧力容器内の水面レベ
ルにり高い位置で接続された特許請求の範囲第1項に記
載の非常用炉心冷却装置。
[Claims] 1. An emergency core cooling system water storage tank is installed at a higher location than the reactor pressure vessel, and the water storage tank and the reactor pressure vessel are connected by a water injection pipe equipped with a water injection valve, In the emergency core cooling system, the water injection valve is opened in the event of a loss of coolant accident in a nuclear reactor, and the coolant in the water storage tank is replenished into the reactor pressure vessel by the action of gravity. 1. An emergency core cooling system, characterized in that the water storage tank is configured as a container, communicates with the reactor pressure vessel via a pressure equalization pipe, and is configured to constantly maintain the water storage tank at substantially the same pressure as the inside of the reactor pressure vessel. 2. The emergency core cooling system according to claim 1, wherein the pressure equalization pipe has a riser pipe extending upward from the top of the water storage tank and a fall pipe continuing from the upper end of the riser pipe. 3. The emergency system according to claim 1, wherein the pressure equalizing pipe extends from the top of the water storage tank, and its tip is connected to the upper side wall of the reactor pressure vessel at a high position above the water surface level in the pressure vessel. Reactor core cooling system.
JP59115414A 1984-06-07 1984-06-07 Emergency core cooling device Pending JPS60259995A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59115414A JPS60259995A (en) 1984-06-07 1984-06-07 Emergency core cooling device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59115414A JPS60259995A (en) 1984-06-07 1984-06-07 Emergency core cooling device

Publications (1)

Publication Number Publication Date
JPS60259995A true JPS60259995A (en) 1985-12-23

Family

ID=14661979

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59115414A Pending JPS60259995A (en) 1984-06-07 1984-06-07 Emergency core cooling device

Country Status (1)

Country Link
JP (1) JPS60259995A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62148890A (en) * 1985-12-24 1987-07-02 株式会社東芝 Cooling spray system of container for nuclear reactor
US5120490A (en) * 1988-09-21 1992-06-09 Hitachi, Ltd. Liquid filling method for a high-temperature and high-pressure vessel and apparatus therefor
US5217680A (en) * 1988-09-21 1993-06-08 Hitachi, Ltd. Liquid filling method for a high-temperature and high-pressure vessel and apparatus therefor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62148890A (en) * 1985-12-24 1987-07-02 株式会社東芝 Cooling spray system of container for nuclear reactor
US5120490A (en) * 1988-09-21 1992-06-09 Hitachi, Ltd. Liquid filling method for a high-temperature and high-pressure vessel and apparatus therefor
US5217680A (en) * 1988-09-21 1993-06-08 Hitachi, Ltd. Liquid filling method for a high-temperature and high-pressure vessel and apparatus therefor

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