JPS6117319B2 - - Google Patents

Info

Publication number
JPS6117319B2
JPS6117319B2 JP54153354A JP15335479A JPS6117319B2 JP S6117319 B2 JPS6117319 B2 JP S6117319B2 JP 54153354 A JP54153354 A JP 54153354A JP 15335479 A JP15335479 A JP 15335479A JP S6117319 B2 JPS6117319 B2 JP S6117319B2
Authority
JP
Japan
Prior art keywords
water
reactor
valve
storage tank
water storage
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.)
Expired
Application number
JP54153354A
Other languages
Japanese (ja)
Other versions
JPS5676096A (en
Inventor
Kenzo Gunyasu
Hideki Hara
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
Nippon Genshiryoku Jigyo KK
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
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, Nippon Genshiryoku Jigyo KK filed Critical Toshiba Corp
Priority to JP15335479A priority Critical patent/JPS5676096A/en
Publication of JPS5676096A publication Critical patent/JPS5676096A/en
Publication of JPS6117319B2 publication Critical patent/JPS6117319B2/ja
Granted 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)

Description

【発明の詳細な説明】 本発明は、原子炉停止時又は原子炉事故時等に
作動して原子炉に冷却水を送り原子炉を冷却する
ための原子炉冷却装置に関る。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor cooling system that operates when a nuclear reactor is shut down or in the event of a nuclear reactor accident to send cooling water to the nuclear reactor to cool the reactor.

一般に、原子炉には、その事故時又は停止時に
作動して原子炉を冷却するための原子炉冷却装置
が設けられ、この原子炉冷却装置は原子炉建屋外
に設けられた水貯蔵タンク、原子炉下方に設けら
れたサプレツシヨンプール、これら水貯蔵タン
ク、サプレツシヨンプール内の冷却水を原子炉に
送給するための冷却水移送ポンプおよびこれら各
機器を接続するための配管等からなつている。
Generally, a nuclear reactor is equipped with a reactor cooling system that operates in the event of an accident or shutdown to cool the reactor. It consists of a suppression pool installed below the reactor, these water storage tanks, a cooling water transfer pump for supplying the cooling water in the suppression pool to the reactor, and piping to connect each of these devices. ing.

そして、通常の場合は、前記水貯蔵タンクの冷
却水を原子炉内に供給し、水貯蔵タンク内の水位
が設定値よりも下がると、弁の切換えにより前記
サプレツシヨンプール内の水を原子炉に供給する
ようになつている。
In normal cases, the cooling water in the water storage tank is supplied into the reactor, and when the water level in the water storage tank falls below a set value, the water in the suppression pool is switched to the nuclear reactor by switching a valve. It is designed to supply the furnace.

〓〓〓〓〓
ところが、このような原子炉冷却装置におい
て、地震時に水貯蔵タンクと原子炉とを接続して
いる配管が破損した場合、水貯蔵タンク内の水位
が上記設定値よりも下がるまで水を原子炉に供給
することが出来ないばかりか、冷却水移送ポンプ
が破損する恐れもある。このため水源をサプレツ
シヨンプールに切り換えたとしても原子炉の冷却
機能が停止する恐れがある。また切り換わるまで
原子炉の冷却機能が停止してしまうという問題が
あつた。本発明は、かかる点に鑑み、通常時にも
地震時にも原子炉の冷却機能が停止することがな
い原子炉冷却装置を提供することを目的とする。
〓〓〓〓〓
However, in such a reactor cooling system, if the piping connecting the water storage tank and the reactor is damaged during an earthquake, water will not be supplied to the reactor until the water level in the water storage tank falls below the set value. Not only will it not be possible to supply cooling water, but there is also a risk that the cooling water transfer pump will be damaged. Therefore, even if the water source is switched to the suppression pool, there is a risk that the cooling function of the reactor will stop. There was also the problem that the reactor's cooling function would stop until the switch was made. In view of this, an object of the present invention is to provide a nuclear reactor cooling system in which the cooling function of the reactor does not stop during normal times or during earthquakes.

以下、図面を参照して本発明の実施例について
説明する。
Embodiments of the present invention will be described below with reference to the drawings.

第1図乃至第3図において、原子炉建屋1内中
央には原子炉格納容器3が載置され、この原子炉
格納容器3内に原子炉圧力容器4が収納され、そ
の下部にはサプレツシヨンプール2が設けられて
いる。
1 to 3, a reactor containment vessel 3 is placed in the center of a reactor building 1, a reactor pressure vessel 4 is housed within this reactor containment vessel 3, and a suppressor is placed in the lower part of the reactor containment vessel 3. A swimming pool 2 is provided.

一方、原子炉建屋1外には、水貯蔵タンク5が
設けられ、この水貯蔵タンク5と前記原子炉圧力
容器4間を水管6で連結しており、この水管6に
は一端が前記サプレツシヨンプール2に接続され
た水管7の他端が接続され、その分岐点Pの下流
側に冷却水移送ポンプ8が取付けられている。
On the other hand, a water storage tank 5 is provided outside the reactor building 1, and a water pipe 6 connects the water storage tank 5 and the reactor pressure vessel 4, with one end of the water pipe 6 being connected to the reactor pressure vessel 4. The other end of the water pipe 7 is connected to the water pipe 2, and a cooling water transfer pump 8 is installed downstream of the branch point P thereof.

前記水管6の分岐点Pと水貯蔵タンク5間には
電動弁9および逆止弁10が取付けられ、前記水
管7には逆止弁11および電動弁12が取付けら
れ、さらに前記水管6の冷却水移送ポンプ8と原
子炉圧力容器4間には逆止弁13、仕切り弁14
および逆止弁15が冷却水移送ポンプ8側から順
に取付けられている。
An electric valve 9 and a check valve 10 are installed between the branch point P of the water pipe 6 and the water storage tank 5, and a check valve 11 and an electric valve 12 are installed on the water pipe 7, and furthermore, the water pipe 6 is cooled. A check valve 13 and a gate valve 14 are provided between the water transfer pump 8 and the reactor pressure vessel 4.
and check valves 15 are installed in order from the cooling water transfer pump 8 side.

一方、原子炉建屋1内の床面の適宜位置には、
4個の地震感知装置16,16………16が取り
付けられている。これら地震感知装置16は水源
変更設定装置19に接続され、水源変更設定装置
19は水管6に取付けられた電動弁9と信号回路
17によつて連結され、電動弁12とは信号回路
18によつて連結され、これら地震感知装置1
6、水源変更設定装置19および電動弁9,12
が耐震安全装置Mを形成している。
On the other hand, at appropriate locations on the floor within the reactor building 1,
Four earthquake sensing devices 16, 16...16 are attached. These earthquake sensing devices 16 are connected to a water source change setting device 19, and the water source change setting device 19 is connected to an electric valve 9 attached to the water pipe 6 by a signal circuit 17, and the electric valve 12 is connected to a signal circuit 18. These earthquake sensing devices 1
6. Water source change setting device 19 and electric valves 9, 12
forms the seismic safety device M.

次に、作用について説明する。 Next, the effect will be explained.

本発明の原子炉冷却装置は、手動起動又は原子
力発電所内の信号により自動起動し、通常は屋外
に設置された水貯蔵タンク5内の水を水源とし、
水管6に取付けられた冷却水移送ポンプ8によ
り、水貯蔵タンク内の水は水管6を経て、原子炉
圧力容器4に導びかれる。このときには、水管6
に取付けられた各弁は遠隔操作により開放され水
管7に取付けられた各弁は閉じられている。そし
て、前記水貯蔵タンク5内の水位が設定値より低
くなると、電動弁9は閉じられ、電動弁12、逆
止弁11が開放されるので、水貯蔵タンク内の水
の供給は停止され、サプレツシヨンプール2の水
が原子炉圧力容器に供給される。
The nuclear reactor cooling system of the present invention is started manually or automatically by a signal within the nuclear power plant, and uses water in a water storage tank 5 normally installed outdoors as a water source,
A cooling water transfer pump 8 attached to the water pipe 6 guides water in the water storage tank to the reactor pressure vessel 4 through the water pipe 6 . At this time, water pipe 6
Each valve attached to the water pipe 7 is opened by remote control, and each valve attached to the water pipe 7 is closed. Then, when the water level in the water storage tank 5 becomes lower than the set value, the electric valve 9 is closed, and the electric valve 12 and check valve 11 are opened, so that the supply of water in the water storage tank is stopped. Water from the suppression pool 2 is supplied to the reactor pressure vessel.

ところが、地震が発生すると、第4図に示すよ
うに地震感知装置16が地震動の大きさを感知
し、その信号は水源変更設定装置19に送られ
る。この水源変更設定装置19においては、予め
水源変更設定値Bが設定されており、ここで地震
感知装置による地震動の大きさAと水源変更設定
値Bが比較される。A<Bであれば、水貯蔵タン
ク5内の水位設定値による制御が優先され、たと
えば電動弁9は開、電動弁12は閉となつたまま
となる。そして通常の場合と同様に水貯蔵タンク
5からの水が原子炉圧力容器4に送られる。A≧
Bであれば水貯蔵タンク5内の水位設定値による
制御は殺される。そして電動弁9は閉、電動弁1
2は開と強制的に制御され、サプレツシヨンプー
ル2からの水が原子炉圧力容器4に送られる。
However, when an earthquake occurs, the earthquake sensing device 16 senses the magnitude of the seismic motion as shown in FIG. 4, and the signal is sent to the water source change setting device 19. In this water source change setting device 19, a water source change setting value B is set in advance, and here, the magnitude A of the seismic motion detected by the earthquake sensing device and the water source change setting value B are compared. If A<B, priority is given to control based on the set value of the water level in the water storage tank 5, and for example, the electric valve 9 remains open and the electric valve 12 remains closed. Water from the water storage tank 5 is then sent to the reactor pressure vessel 4 as in the normal case. A≧
If it is B, the control based on the set value of the water level in the water storage tank 5 is canceled. Then, electric valve 9 is closed and electric valve 1 is closed.
2 is forcibly controlled to be open, and water from the suppression pool 2 is sent to the reactor pressure vessel 4.

なお、前記電動弁9,12は空気作動弁とする
ことも勿論可能である。また水貯蔵タンク5及び
水管を通常の強度で設計することも可能である。
また水管6及び水貯蔵タンク5の健全性を確認し
た上で、手動で水貯蔵タンク5に水源を切り換え
ることもできる。
Note that the electric valves 9 and 12 can of course be air-operated valves. It is also possible to design the water storage tank 5 and the water pipes with normal strength.
Further, after confirming the soundness of the water pipe 6 and the water storage tank 5, the water source can be manually switched to the water storage tank 5.

本発明は以上のように構成したので、水管6の
水貯蔵タンク5と原子炉建屋1間の部分が破壊す
るような地震が発生した場合でも、正常に原子炉
圧力容器4が冷却され原子炉運転上の安全性が維
持される。しかも、原子炉建屋1外の水管および
水貯蔵タンク5の強度を必要以上に大きく設計す
る必要もなくなるし、それらの支持方法も簡単で
よく原子炉冷却装置全体の建設費用の低減および
建設工程の短縮を図ることができる。
Since the present invention is configured as described above, even if an earthquake occurs that destroys the portion of the water pipe 6 between the water storage tank 5 and the reactor building 1, the reactor pressure vessel 4 is normally cooled and the reactor Driving safety is maintained. Moreover, there is no need to design the water pipes outside the reactor building 1 and the water storage tank 5 to be unnecessarily strong, and the way to support them is simple, reducing the construction cost of the entire reactor cooling system and speeding up the construction process. It is possible to shorten the time.

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

第1図は本発明に係る原子炉冷却装置の概略構
成図、第2図は原子炉建屋の縦断面図、第3図は
〓〓〓〓〓
原子炉建屋の横断面図および第4図は本発明の作
用を説明するための流れ系統図である。 1……原子炉建屋、2……サプレツシヨンプー
ル、4……原子炉圧力容器、5……水貯蔵タン
ク、6……水管、7……水管、8……冷却水移送
ポンプ、9,12……電動弁、16……地震感知
装置、19……水源変更設定装置。 〓〓〓〓〓
Figure 1 is a schematic configuration diagram of a nuclear reactor cooling system according to the present invention, Figure 2 is a vertical cross-sectional view of a reactor building, and Figure 3 is
A cross-sectional view of the reactor building and FIG. 4 are flow diagrams for explaining the operation of the present invention. 1...Reactor building, 2...Suppression pool, 4...Reactor pressure vessel, 5...Water storage tank, 6...Water pipe, 7...Water pipe, 8...Cooling water transfer pump, 9, 12...Electric valve, 16...Earthquake sensing device, 19...Water source change setting device. 〓〓〓〓〓

Claims (1)

【特許請求の範囲】[Claims] 1 原子炉建屋と、この原子炉建屋内に設置され
た原子炉格納容器と、この原子炉格納容器内に収
納されてなる原子炉圧力容器と、上記原子炉格納
容器の下部に設けられてなるサプレツシヨンプー
ルと、上記原子炉建屋外に設けられた水貯蔵タン
クと、この水貯蔵タンクから導出され原子炉建屋
を貫通し第1の弁の上流側に至る第1の水管と、
前記第1の弁の下流側から導出され冷却水移送ポ
ンプの吸込側に接続される第2の水管と、前記冷
却水移送ポンプの吐出側から導出され上記原子炉
格納容器を貫通し上記原子炉圧力容器内に開口す
る第3の水管と、上記サプレツシヨンプールに一
端を開口し第2の弁を介して上記第2の水管に接
続されてなる第4の水管と、上記原子炉圧力容器
に冷却水を供給する場合第1の弁を開第2の弁を
閉として上記水貯蔵タンクから冷却水を供給し、
水貯蔵タンクの水位が設定値より低下したときは
第1の弁を閉第2の弁を開として上記サプレツシ
ヨンプールから冷却水を供給する制御装置とを具
備した原子炉冷却装置において、原子炉建屋内に
設置された複数の地震感知装置と、この地震感知
装置からの信号が入力され、この信号の大きさが
あらかじめ設定された水源変更設定値より大きい
場合上記第1の弁に閉信号を、上記第2の弁に開
信号を出力する水源変更設定装置とを有し、これ
ら閉信号と開信号は上記水貯蔵タンク水位による
制御に対し優先されてなることを特徴とする原子
炉冷却装置。
1. A reactor building, a reactor containment vessel installed within the reactor building, a reactor pressure vessel housed within the reactor containment vessel, and a reactor pressure vessel provided below the reactor containment vessel. a suppression pool, a water storage tank provided outside the reactor building, a first water pipe led out from the water storage tank, penetrating the reactor building and reaching the upstream side of the first valve;
a second water pipe led out from the downstream side of the first valve and connected to the suction side of the cooling water transfer pump; and a second water pipe led out from the discharge side of the cooling water transfer pump and penetrating the reactor containment vessel and connected to the reactor a third water pipe that opens into the pressure vessel; a fourth water pipe that has one end open to the suppression pool and is connected to the second water pipe via a second valve; and the reactor pressure vessel. When supplying cooling water to the water storage tank, the first valve is opened and the second valve is closed, and cooling water is supplied from the water storage tank.
A nuclear reactor cooling system comprising a control device that closes a first valve and opens a second valve to supply cooling water from the suppression pool when the water level in the water storage tank drops below a set value. A plurality of earthquake sensing devices installed in the reactor building and a signal from this earthquake sensing device are input, and if the magnitude of this signal is larger than a preset water source change setting value, a close signal is sent to the first valve. and a water source change setting device that outputs an open signal to the second valve, wherein the close signal and the open signal are prioritized over the control based on the water level of the water storage tank. Device.
JP15335479A 1979-11-27 1979-11-27 Nuclear reactor cooling device Granted JPS5676096A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP15335479A JPS5676096A (en) 1979-11-27 1979-11-27 Nuclear reactor cooling device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP15335479A JPS5676096A (en) 1979-11-27 1979-11-27 Nuclear reactor cooling device

Publications (2)

Publication Number Publication Date
JPS5676096A JPS5676096A (en) 1981-06-23
JPS6117319B2 true JPS6117319B2 (en) 1986-05-07

Family

ID=15560621

Family Applications (1)

Application Number Title Priority Date Filing Date
JP15335479A Granted JPS5676096A (en) 1979-11-27 1979-11-27 Nuclear reactor cooling device

Country Status (1)

Country Link
JP (1) JPS5676096A (en)

Also Published As

Publication number Publication date
JPS5676096A (en) 1981-06-23

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