JPS6140078B2 - - Google Patents

Info

Publication number
JPS6140078B2
JPS6140078B2 JP54134378A JP13437879A JPS6140078B2 JP S6140078 B2 JPS6140078 B2 JP S6140078B2 JP 54134378 A JP54134378 A JP 54134378A JP 13437879 A JP13437879 A JP 13437879A JP S6140078 B2 JPS6140078 B2 JP S6140078B2
Authority
JP
Japan
Prior art keywords
cooling pipe
valve
water supply
closing valve
closing
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
JP54134378A
Other languages
Japanese (ja)
Other versions
JPS5658693A (en
Inventor
Katsuo Niizawa
Kazuo Suzuki
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 Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
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 Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP13437879A priority Critical patent/JPS5658693A/en
Publication of JPS5658693A publication Critical patent/JPS5658693A/en
Publication of JPS6140078B2 publication Critical patent/JPS6140078B2/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】 本発明は沸騰水形原子炉等の軽水炉の残留熱除
去装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a residual heat removal device for a light water reactor such as a boiling water reactor.

一般にこの種の残留熱除去装置は炉の冷却水再
循環管路等から分岐して停止時冷却管路を設け、
この冷却管路の途中には冷却管路開閉弁、ポンプ
および熱交換器を設け、炉の停止時には上記ポン
プによつて熱交換器を通して冷却水を循環させ、
炉の残留熱を除去するように構成されている。ま
た、上記冷却管路開閉弁とポンプとの間から分岐
してサプレツシヨンチヤンバ内に連通する非常時
給水管路を設け、この非常時給水管路の途中には
非常時給水弁を設け、常時はこの非常時給水弁を
閉弁しておくとともに冷却材喪失事故等の非常時
にはこの非常時給水弁を開弁してサプレツシヨン
チヤンバ内の水を停止時冷却管路に供給しこの停
止時冷却管路を介して炉内に供給するように構成
し、非常用炉心冷却装置としても作動するように
構成されている。ところで、上記非常時給水弁は
非常時に確実に開弁することが必要であり、この
ため従来この非常時給水弁は弁開阻止インターロ
ツクなしのキーロツクスイツチによる手動操作で
開弁することができるように構成されている。し
かし、このようなものでは炉の停止時冷却モード
時に誤操作によつて上記の非常時給水弁が開弁さ
れる可能性があり、このような場合は炉内の冷却
水が冷却管路開閉弁および非常時給水弁を通つて
サプレツシヨンプール内に放出され、炉水喪失事
故につながる可能性があつた。
Generally, this type of residual heat removal device has a cooling pipe branched from the furnace cooling water recirculation pipe, etc. to provide a cooling pipe during shutdown.
A cooling pipe opening/closing valve, a pump, and a heat exchanger are installed in the middle of this cooling pipe, and when the furnace is stopped, the cooling water is circulated through the heat exchanger by the pump.
Configured to remove residual heat from the furnace. In addition, an emergency water supply pipe is provided that branches from between the cooling pipe opening/closing valve and the pump and communicates with the suppression chamber, and an emergency water supply valve is provided in the middle of this emergency water supply pipe, so that the The emergency water supply valve is kept closed, and in the event of an emergency such as a loss of coolant accident, the emergency water supply valve is opened to supply water in the suppression chamber to the cooling pipe during shutdown. It is configured to be supplied into the reactor via a cooling pipe line, and is configured to also operate as an emergency core cooling system. By the way, it is necessary for the above-mentioned emergency water supply valve to open reliably in an emergency, and for this reason, conventionally, this emergency water supply valve can be opened by manual operation using a key lock switch without an interlock to prevent the valve from opening. It is configured as follows. However, with such a system, there is a possibility that the above-mentioned emergency water supply valve may be opened due to an erroneous operation during the shutdown cooling mode of the reactor. and was released into the suppression pool through the emergency water supply valve, potentially leading to a reactor water loss accident.

本発明は以上の事情にもとづいてなされたもの
で、その目的とするところは誤操作による炉水喪
失事故の可能性がないとともに装置全体の信頼性
を損なうことのない原子炉の残留熱除去装置を得
ることにある。
The present invention has been made based on the above circumstances, and its purpose is to provide a residual heat removal device for a nuclear reactor that does not have the possibility of a loss of reactor water accident due to incorrect operation and does not impair the reliability of the entire device. It's about getting.

以下本発明を図面に示す一実施例にしたがつて
説明する。この一実施例は本発明を沸謄水形原子
炉の残留熱除去装置に適用したものであつて、ま
ず第1図にしたがつて全体の構成を説明する。図
中1は炉容器、2…は再循環管路、3…は再循環
ポンプ、4…はジエツトポンプである。そして、
上記再循環管路2…の再循環ポンプ3…の吸込側
から分岐し、かつこの再循環管路2…の再循環ポ
ンプ3…の吐出側に接続された一対の停止時冷却
管路5,5が設けられている。そして、これら停
止時冷却管路5,5の中間部にはそれぞれ熱交換
器6,6が設けられ、これら停止時冷却管路5,
5を流れる冷却水を冷却するように構成されてい
る。そして、これら停止時冷却管路5,5の上流
側部分は両方の停止時冷却管路5,5に共用され
た1本の共通管路7に構成され、この共通管路7
は格納容器8を貫通して格納容器8外に導出され
ている。また、この共通管路7は各停止時冷却管
路5,5毎に並列に配置されたそれぞれ一対の並
列管路9a,9b,9c,9dに分岐され、これ
らの並列管路9a,9b,9c・9dはそれぞれ
熱交換器6,6に接続されている。そして、上記
の共通管路7の途中には格納容器8の内側と外側
にそれぞれ位置して冷却管路開閉弁10,11が
設けられている。また、上記並列管路9a,9
b,9c・9dにはそれぞれ上流側から冷却管路
開閉弁12a,12b,12c,12dおよびポ
ンプ13a,13b,13c,113dが設けら
れている。また、上記熱交換器6,6の下流側の
停止時冷却管路5,5の途中にはそれぞれ開閉弁
14,14が設けられ、また両方の停止時冷却管
路5,5はタイバルブ15を介して互に連通して
いる。そして、これらの停止時冷却管路5,5の
並列管路9a,9b,9c,9dの冷却管路開閉
弁12a,12b,12c,12dとポンプ13
a,13b,13c,13dとの間からそれぞれ
分岐して非常時給水管路16,16が設けられ、
これら非常時給水管路16,16はサプレツシヨ
ンチヤンバ17内に挿通している。また、これら
給水管路16,16の途中には上記の並列管路9
a,9b,9c,9dにそれぞれ対応して非常時
給水弁18a,18b,18c,18dが設けら
れている。そして、上記並列管路9a,9b,9
c,9dの冷却管路開閉弁12a,12b,12
c,12dとこれらにそれぞれ対応した非常時給
水弁18a,18b,18c,18dとはそれぞ
れ制御機構19a,19b,19c,19dによ
つて所定の関係で開閉制御されるように構成され
ている。これらの制御機構19a,19b,19
c,19dはいずれも同様の構成であり、以下1
組の冷却管路開閉弁12aと非常時給水弁18a
の制御機構19aについて第2図を参照して説明
する。上記冷却管路開閉弁12aおよび非常時給
水弁18aはたとえばモータ駆動形の開閉弁であ
つて、電気信号により開閉作動されるように構成
されている。そして、上記冷却管路開閉弁12a
は冷却管路開閉弁制御回路20aからの信号によ
り開閉作動され、また非常時給水弁18aは非常
時給水弁制御回路21aからの信号により開閉作
動されるように構成されている。そして上記冷却
管路開閉弁制御回路20aはこの冷却管路開閉弁
12aの弁操作スイツチ(図示せず)からの開弁
信号22と、原子炉事故信号23が信号反転回路
24を介して入力されるAND回路25からの出
力信号によつて冷却管路開閉弁12aを開弁作動
させ、また上記の弁操作スイツチの閉弁信号26
と原子炉事故信号23とが入力されるOR回路2
7からの出力信号によつて冷却管路開閉弁12a
を閉弁作動させるように構成されている。なお、
上記の原子炉事故信号23は原子炉冷却水喪失と
格納容器8内の圧力上昇に対応して出力される信
号である。また、上記の冷却管路開閉弁12aに
はその開閉作動に連動するリミツトスイツチ28
が設けられ、この冷却管路開閉弁12aが完全に
閉弁した場合にその旨の信号が出力され、非常時
給水弁制御回路21aに送られるように構成され
ている。そして、上記の非常時給水弁制御回路2
1は非常時給水弁18aの弁操作スイツチ(図示
せず)の開弁信号29と上記リミツトスイツチ2
8からの信号が入力されるAND回路30を有
し、このAND回路30の出力信号はOR回路31
に入力され、またこのOR回路31には原子炉事
故信号23が入力され、このOR回路31の出力
信号によつて非常時給水弁18aが開弁されるよ
うに構成されている。また、上記の弁操作スイツ
チの閉弁信号32と、原子炉事故信号23が信号
反転回路33を介して入力されるAND回路34
からの出力信号によつて上記非常時給水弁18a
が閉弁されるように構成されている。
The present invention will be described below with reference to an embodiment shown in the drawings. In this embodiment, the present invention is applied to a residual heat removal device for a boiling water nuclear reactor, and the overall configuration will first be explained with reference to FIG. In the figure, 1 is a furnace vessel, 2... is a recirculation pipe, 3... is a recirculation pump, and 4... is a jet pump. and,
A pair of stop cooling pipes 5 branched from the suction side of the recirculation pump 3 of the recirculation pipe 2 and connected to the discharge side of the recirculation pump 3 of the recirculation pipe 2, 5 is provided. Heat exchangers 6, 6 are provided in the intermediate portions of these cooling pipe lines 5, 5 when stopped, respectively, and these cooling pipe lines 5, 5 when stopped,
It is configured to cool the cooling water flowing through 5. The upstream portion of these cooling pipes 5, 5 at the time of shutdown is configured as one common pipe 7 shared by both the cooling pipes 5, 5 at the time of shutdown, and this common pipe 7
penetrates the containment vessel 8 and is led out of the containment vessel 8. Further, this common pipe line 7 is branched into a pair of parallel pipe lines 9a, 9b, 9c, and 9d, which are arranged in parallel for each of the stop cooling pipe lines 5, 5, and these parallel pipe lines 9a, 9b, 9c and 9d are connected to heat exchangers 6 and 6, respectively. Cooling pipe opening/closing valves 10 and 11 are provided in the middle of the common pipe line 7, located on the inside and outside of the containment vessel 8, respectively. In addition, the parallel pipe lines 9a, 9
Cooling pipe opening/closing valves 12a, 12b, 12c, 12d and pumps 13a, 13b, 13c, 113d are provided in cooling pipes b, 9c, and 9d, respectively, from the upstream side. In addition, on-off valves 14, 14 are provided in the middle of the stop cooling pipes 5, 5 on the downstream side of the heat exchangers 6, 6, respectively, and both the stop cooling pipes 5, 5 have a tie valve 15. communicate with each other through. Then, the cooling pipe opening/closing valves 12a, 12b, 12c, 12d of the parallel pipes 9a, 9b, 9c, 9d of the cooling pipes 5, 5 at the time of stop and the pump 13
Emergency water supply pipes 16, 16 are provided branching off from between a, 13b, 13c, and 13d, respectively.
These emergency water supply pipes 16, 16 are inserted into the suppression chamber 17. Moreover, in the middle of these water supply pipes 16, 16, the above-mentioned parallel pipe 9 is provided.
Emergency water supply valves 18a, 18b, 18c, and 18d are provided corresponding to a, 9b, 9c, and 9d, respectively. And the parallel pipe lines 9a, 9b, 9
c, 9d cooling pipe opening/closing valves 12a, 12b, 12
c, 12d and the corresponding emergency water supply valves 18a, 18b, 18c, 18d are configured to be opened and closed in a predetermined relationship by control mechanisms 19a, 19b, 19c, 19d, respectively. These control mechanisms 19a, 19b, 19
Both c and 19d have the same configuration, and the following 1
Set of cooling pipe opening/closing valve 12a and emergency water supply valve 18a
The control mechanism 19a will be explained with reference to FIG. The cooling pipe opening/closing valve 12a and the emergency water supply valve 18a are, for example, motor-driven opening/closing valves, and are configured to be opened and closed by electric signals. The cooling pipe opening/closing valve 12a
are configured to be opened and closed by signals from the cooling pipe opening/closing valve control circuit 20a, and the emergency water supply valve 18a is configured to be opened and closed by signals from the emergency water supply valve control circuit 21a. The cooling pipe opening/closing valve control circuit 20a receives a valve opening signal 22 from a valve operation switch (not shown) of the cooling pipe opening/closing valve 12a and a reactor accident signal 23 through a signal inversion circuit 24. The cooling pipe opening/closing valve 12a is opened by the output signal from the AND circuit 25, and the valve closing signal 26 of the valve operation switch is activated.
OR circuit 2 into which the and reactor accident signal 23 are input.
The cooling pipe opening/closing valve 12a is activated by the output signal from 7.
The valve is configured to close the valve. In addition,
The above reactor accident signal 23 is a signal that is output in response to the loss of reactor cooling water and the rise in pressure within the containment vessel 8. Further, the cooling pipe opening/closing valve 12a has a limit switch 28 which is linked to its opening/closing operation.
is provided, and when the cooling pipe opening/closing valve 12a is completely closed, a signal to that effect is output and sent to the emergency water supply valve control circuit 21a. And the above emergency water supply valve control circuit 2
1 is a valve opening signal 29 of a valve operation switch (not shown) of the emergency water supply valve 18a and the limit switch 2
The output signal of this AND circuit 30 is input to an OR circuit 31.
The reactor accident signal 23 is also input to this OR circuit 31, and the emergency water supply valve 18a is opened by the output signal of this OR circuit 31. Further, an AND circuit 34 is provided with the valve closing signal 32 of the valve operation switch described above and the reactor accident signal 23 being inputted via a signal inverting circuit 33.
The emergency water supply valve 18a is activated by the output signal from the
is configured so that the valve is closed.

次に上記の一実施例の作用を説明する。まず炉
の正常運転時には停止時冷却管路5,5の各冷却
管路開閉弁10,11,12a,12b,12
c,12dはいずれも閉弁状態であり、炉水は再
循環管路2…を通つて循環される。次に炉を停止
して残留熱を除去する場合すなわち停止時冷却モ
ードの場合には、冷却管路開閉弁10,11,1
2a,12b,12c,12dおよび開閉弁1
4,14を開弁し、ポンプ13a,13b,13
c,13dを運転する。したがつて炉水はこの停
止時冷却管路5,5を介して熱交換器6,6を通
つて循環され、炉心の冷却をなす。この場合冷却
管路開閉弁12aが開弁しているときにはリミツ
トスイツチ28から信号が出力されていないので
非常時給水弁18aの弁操作スイツチを開弁操作
しても非常時給水弁制御回路21aのAND回路
30から信号は出力されず、よつて非常時給水弁
18aは開弁しない。したがつて冷却管路開閉弁
12aが開弁されている状態で誤つて非常時給水
弁18aの弁操作スイツチを開弁操作しても非常
時給水弁18aは開弁されず、よつて炉水がサプ
レツシヨンチヤンバ17に放出されてしまう可能
性はない。次に原子炉事故信号23が出力されて
いない状態で手動によりサプレツシヨンチヤンバ
17内の水を原子炉に注入する場合すなわち手動
で低圧注水モードとする場合には、まず冷却管路
開閉弁12aを閉弁する。したがつてこの冷却管
路開閉弁12aのリミツトスイツチ28から信号
が出力され、非常時給水弁制御回路21aの
AND回路30に送られる。よつてこの状態で非
常時給水弁18aの弁操作スイツチを操作するこ
とにより非常時給水弁18aを開弁し、低圧注水
モードとすることができる。また、冷却水喪失等
の原子炉事故が生じた場合には原子炉事故信号2
3が冷却管路開閉弁制御回路20aおよび非常時
給水弁制御回路21aに送られる。したがつて冷
却管路開閉弁制御回路20aのAND回路25か
らは冷却管路開閉弁12aの弁操作スイツチの操
作状態には関係なく常に信号は出力されず、また
OR回路27からは弁操作スイツチの操作状態に
は関係なく信号が出力され、よつてこの冷却管路
開閉弁12aは自動的に閉弁される。また、原子
炉事故信号23は非常時給水弁制御回路21aの
OR回路31に入力されるので、このOR回路31
からは非常時給水弁18aの弁操作スイツチの操
作状態とは関係なく常に信号が出力されて非常時
給水弁18aが自動的に開弁され、サプレツシヨ
ンチヤンバ17内の水はポンプ13aによつて原
子炉内に注入され、自動的に低圧注入モードとな
る。なお、この一実施例は非常時給水弁制御回路
21aに入力される冷却管路開閉弁12aの閉弁
信号はこの冷却管路開閉弁12aの開閉作動に連
動したリミツトスイツチ28によつて出力される
ものであるから、その信頼性が高いものである。
なお、上述の作用は冷却管路開閉弁12aと非常
時給水弁18aとについてのみ説明したが、他の
冷却管路開閉弁12b,12c,12dと非常時
給水弁18b,18c,18dについてもまつた
く同様である。
Next, the operation of the above embodiment will be explained. First, during normal operation of the furnace, the cooling pipe opening/closing valves 10, 11, 12a, 12b, 12 of the cooling pipes 5, 5 during shutdown.
Both valves c and 12d are closed, and reactor water is circulated through the recirculation pipes 2. Next, when the furnace is stopped and the residual heat is removed, that is, in the cooling mode during shutdown, the cooling pipe opening/closing valves 10, 11, 1
2a, 12b, 12c, 12d and on-off valve 1
4, 14 open, pumps 13a, 13b, 13
c, drive 13d. Therefore, the reactor water is circulated through the heat exchangers 6, 6 via the cooling pipes 5, 5 during shutdown to cool the reactor core. In this case, when the cooling pipe opening/closing valve 12a is open, no signal is output from the limit switch 28, so even if the valve operation switch of the emergency water supply valve 18a is opened, the AND of the emergency water supply valve control circuit 21a is No signal is output from the circuit 30, and therefore the emergency water supply valve 18a does not open. Therefore, even if the valve operation switch of the emergency water supply valve 18a is opened by mistake while the cooling pipe opening/closing valve 12a is open, the emergency water supply valve 18a will not be opened, and the reactor water will not be opened. There is no possibility that the liquid will be released into the suppression chamber 17. Next, when the water in the suppression chamber 17 is manually injected into the reactor without the reactor accident signal 23 being output, that is, when the low-pressure water injection mode is manually set, first the cooling pipe opening/closing valve is 12a is closed. Therefore, a signal is output from the limit switch 28 of the cooling pipe opening/closing valve 12a, and the emergency water supply valve control circuit 21a is activated.
It is sent to the AND circuit 30. Therefore, by operating the valve operation switch of the emergency water supply valve 18a in this state, the emergency water supply valve 18a can be opened and set to the low pressure water injection mode. In addition, in the event of a reactor accident such as loss of cooling water, the reactor accident signal 2
3 is sent to the cooling pipe opening/closing valve control circuit 20a and the emergency water supply valve control circuit 21a. Therefore, no signal is always output from the AND circuit 25 of the cooling pipe opening/closing valve control circuit 20a, regardless of the operating state of the valve operation switch of the cooling pipe opening/closing valve 12a.
A signal is output from the OR circuit 27 regardless of the operating state of the valve operating switch, and thus the cooling pipe opening/closing valve 12a is automatically closed. In addition, the reactor accident signal 23 is output from the emergency water supply valve control circuit 21a.
Since it is input to the OR circuit 31, this OR circuit 31
A signal is always output from the valve control switch of the emergency water supply valve 18a to automatically open the emergency water supply valve 18a, and the water in the suppression chamber 17 is supplied to the pump 13a. Therefore, it is injected into the reactor and automatically enters low pressure injection mode. In this embodiment, the closing signal for the cooling pipe opening/closing valve 12a input to the emergency water supply valve control circuit 21a is outputted by a limit switch 28 that is linked to the opening/closing operation of the cooling pipe opening/closing valve 12a. Because it is a product, its reliability is high.
In addition, although the above-mentioned operation was explained only for the cooling pipe opening/closing valve 12a and the emergency water supply valve 18a, it also applies to the other cooling pipeline opening/closing valves 12b, 12c, 12d and the emergency water supply valves 18b, 18c, 18d. It's very similar.

なお、本発明は上記の一実施例には限定されな
い。
Note that the present invention is not limited to the above embodiment.

たとえば冷却管路開閉弁制御回路および非常時
給水弁制御回路の具体的構成は必らずしも上記の
ものに限定されず、同様の作動をするものであれ
ばどのようなものでもよい。
For example, the specific configurations of the cooling pipe opening/closing valve control circuit and the emergency water supply valve control circuit are not necessarily limited to those described above, and may be of any type as long as they operate in the same way.

また非常時給水弁と関連して制御される冷却管
路開閉弁は必らずしも上記一実施例の冷却管路開
閉弁に限らず、要は非常時給水管路の分岐部より
上流側にある冷却管路開閉弁と非常時給水弁とを
前述の如き関係で制御すればよいものである。
Furthermore, the cooling pipe opening/closing valve that is controlled in conjunction with the emergency water supply valve is not necessarily limited to the cooling pipe opening/closing valve of the above-mentioned embodiment; It is sufficient to control a certain cooling pipe opening/closing valve and an emergency water supply valve in the relationship as described above.

上述の如く本発明は原子炉事故信号が入力され
ない場合にのみ冷却管路開閉弁を手動で開閉操作
可能とするとともに原子炉事故信号が入力された
場合には上記冷却管路開閉弁を閉弁する冷却管路
開閉弁制御回路と、上記冷却管路開閉弁の閉弁信
号が入力されかつ原子炉事故信号が入力されない
場合にのみ非常時給水弁を手動で開閉操作可能と
するとともに原子炉事故信号が入力された場合に
は上記非常時給水弁を開弁する非常時給水弁制御
回路とを設けたものである。したがつて手動によ
り停止時冷却モードおよび低圧注水モードの切換
ができ、また原子炉事故時には自動的に低圧注水
モードに切換えることができるとともに冷却管路
開閉弁が閉弁しない限り非常時給水弁は開弁でき
ないので、冷却管路開閉弁が開弁している状態で
誤操作により非常時給水弁を開弁してしまう可能
性はなく、よつてモード切換時の操作が容易であ
るとともに誤操作による炉水の喪失等を確実に防
止できる等その効果は大である。
As described above, the present invention enables manual opening and closing of the cooling pipe opening/closing valve only when a reactor accident signal is not input, and closes the cooling pipe opening/closing valve when a reactor accident signal is input. A cooling pipe opening/closing valve control circuit that enables manual opening/closing of the emergency water supply valve only when a closing signal for the cooling pipe opening/closing valve is input and a reactor accident signal is not input, and a reactor accident An emergency water supply valve control circuit is provided which opens the emergency water supply valve when a signal is input. Therefore, it is possible to manually switch between shutdown cooling mode and low-pressure water injection mode, and in the event of a reactor accident, it is possible to automatically switch to low-pressure water injection mode, and the emergency water supply valve is closed unless the cooling pipe opening/closing valve is closed. Since the valve cannot be opened, there is no possibility that the emergency water supply valve may be opened by mistake while the cooling pipe opening/closing valve is open. The effects are great, such as being able to reliably prevent water loss.

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

図面は本発明の一実施例を示し、第1図は全体
の系統図、第2図は制御回路のブロツク線図であ
る。 1……炉容器、2……再循環管路、5……停止
時冷却管路、6……熱交換器、12a,12b,
12c,12d……冷却管路開閉弁、13a,1
3b,13c,13d……ポンプ、18a,18
b,18c,18d……非常時給水弁、20a…
…冷却管路開閉弁制御回路、21a……非常時給
水弁制御回路、28……リミツトスイツチ。
The drawings show one embodiment of the present invention, with FIG. 1 being an overall system diagram and FIG. 2 being a block diagram of a control circuit. DESCRIPTION OF SYMBOLS 1... Furnace vessel, 2... Recirculation pipe line, 5... Cooling pipe line during shutdown, 6... Heat exchanger, 12a, 12b,
12c, 12d... Cooling pipe opening/closing valve, 13a, 1
3b, 13c, 13d...pump, 18a, 18
b, 18c, 18d...Emergency water supply valve, 20a...
...Cooling pipe opening/closing valve control circuit, 21a...Emergency water supply valve control circuit, 28...Limit switch.

Claims (1)

【特許請求の範囲】 1 原子炉の停止時に炉内の冷却水を循環させる
停止時冷却管路と、この停止時冷却管路の途中に
設けられた冷却管路開閉弁、ポンプおよび熱交換
器と、上記冷却管路開閉弁と上記ポンプとの間か
ら分岐してサプレツシヨンチヤンバ内に連通し非
常時に上記サプレツシヨンチヤンバ内の水を上記
停止時冷却管路に供給する非常時給水管路と、こ
の非常時給水管路の途中に設けられた非常時給水
弁とを備えたものにおいて、原子炉事故信号が入
力されない場合にのみ上記冷却管路開閉弁を手動
で開閉操作可能とするとともに原子炉事故信号が
入力された場合には上記冷却管路開閉弁を閉弁す
る冷却管路開閉弁制御回路と、上記冷却管路開閉
弁の閉信号が入力されかつ原子炉事故信号が入力
されない場合にのみ上記非常時給水弁を手動で開
閉操作可能とするとともに原子炉事故信号が入力
された場合には上記非常時給水弁を開弁する非常
時給水弁制御回路とを具備したことを特徴とする
原子炉の残留熱除去装置。 2 前記冷却管路開閉弁の閉弁信号はこの冷却管
路開閉弁の開閉作動に連動して作動するスイツチ
機構により出力されるものであることを特徴とす
る前記特許請求の範囲第1項記載の原子炉の残留
熱除去装置。
[Scope of Claims] 1. A shutdown cooling pipe that circulates cooling water in the reactor when the reactor is shut down, and a cooling pipe opening/closing valve, pump, and heat exchanger provided in the middle of this shutdown cooling pipe. and an emergency supply branched from between the cooling pipe opening/closing valve and the pump and communicating with the suppression chamber to supply water in the suppression chamber to the cooling pipe during shutdown in an emergency. In a system equipped with a water pipe and an emergency water supply valve installed in the middle of the emergency water supply pipe, the cooling pipe opening/closing valve can be manually opened and closed only when a reactor accident signal is not input. and a cooling pipe opening/closing valve control circuit that closes the cooling pipe opening/closing valve when a reactor accident signal is input, and a cooling pipe opening/closing valve control circuit that closes the cooling pipeline opening/closing valve when a reactor accident signal is input, and a reactor accident signal is input. The emergency water supply valve is equipped with an emergency water supply valve control circuit that enables the emergency water supply valve to be manually opened and closed only when the reactor accident signal is input. Characteristic residual heat removal equipment for nuclear reactors. 2. The valve closing signal of the cooling pipe opening/closing valve is output by a switch mechanism that operates in conjunction with the opening/closing operation of the cooling pipe opening/closing valve. residual heat removal equipment for nuclear reactors.
JP13437879A 1979-10-18 1979-10-18 Residual heat removal device for nuclear reactor Granted JPS5658693A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP13437879A JPS5658693A (en) 1979-10-18 1979-10-18 Residual heat removal device for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP13437879A JPS5658693A (en) 1979-10-18 1979-10-18 Residual heat removal device for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS5658693A JPS5658693A (en) 1981-05-21
JPS6140078B2 true JPS6140078B2 (en) 1986-09-06

Family

ID=15126985

Family Applications (1)

Application Number Title Priority Date Filing Date
JP13437879A Granted JPS5658693A (en) 1979-10-18 1979-10-18 Residual heat removal device for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS5658693A (en)

Also Published As

Publication number Publication date
JPS5658693A (en) 1981-05-21

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