JPH023479B2 - - Google Patents
Info
- Publication number
- JPH023479B2 JPH023479B2 JP57030151A JP3015182A JPH023479B2 JP H023479 B2 JPH023479 B2 JP H023479B2 JP 57030151 A JP57030151 A JP 57030151A JP 3015182 A JP3015182 A JP 3015182A JP H023479 B2 JPH023479 B2 JP H023479B2
- Authority
- JP
- Japan
- Prior art keywords
- cooling system
- cooling
- cooling water
- reactor
- power supply
- 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 - Lifetime
Links
- 238000001816 cooling Methods 0.000 claims description 52
- 239000000498 cooling water Substances 0.000 claims description 22
- 238000001514 detection method Methods 0.000 claims description 11
- 239000000446 fuel Substances 0.000 claims description 8
- 238000010248 power generation Methods 0.000 claims description 7
- 238000010586 diagram Methods 0.000 description 4
- 230000002542 deteriorative effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000005611 electricity Effects 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Motor Or Generator Cooling System (AREA)
Description
【発明の詳細な説明】
本発明は原子炉冷却系統の制御装置に係り、特
に原子炉冷却系統のうち常に原子炉格納容器冷却
系と燃料プール冷却系の冷却機能を維持するのに
好適な原子炉冷却系統の制御装置に関するもので
ある。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control device for a nuclear reactor cooling system, and in particular to a nuclear reactor cooling system that is suitable for always maintaining the cooling functions of a reactor containment vessel cooling system and a fuel pool cooling system. This relates to a control device for a reactor cooling system.
一般に原子力発電設備の原子炉冷却系統は、第
１図に示すように、原子炉格納容器冷却系１と燃
料プール冷却系２とその他の補機冷却系３とより
なり、これらの冷却系１〜３の冷却機能を維持す
る冷却水供給のために３台のポンプ４ａ〜４ｃが
設けてある。ただし、ポンプ４ｃは予備としてあ
る。そして、これらのポンプ４ａ〜４ｃを駆動す
る電動機（図示せず）は、それぞれ通常電源（商
用電源または所内電源）５で運転されているが、
通常電源喪失事故時（停電など）でも運転を確保
できるようにするために、図示のように、非常用
デイーゼル発電設備からなる非常電源６ａ，６ｂ
が設けてあり、非常電源６ａではポンプ４ａ，４
ｃを、非常電源６ｂではポンプ４ｂを駆動できる
ようにバツクアツプしている。なお、各非常用デ
イーゼル発電設備は、通常電源５が喪失したら起
動するようにしてある。 Generally, the reactor cooling system of a nuclear power generation facility consists of a reactor containment vessel cooling system 1, a fuel pool cooling system 2, and other auxiliary equipment cooling systems 3, as shown in Fig. 1. Three pumps 4a to 4c are provided to supply cooling water to maintain the cooling function of 3. However, the pump 4c is kept as a spare. The electric motors (not shown) that drive these pumps 4a to 4c are each operated by a normal power source (commercial power source or in-house power source) 5,
In order to ensure operation even in the event of loss of normal power (power outage, etc.), emergency power sources 6a and 6b consisting of emergency diesel power generation equipment are provided as shown in the diagram.
is provided, and the emergency power source 6a is equipped with pumps 4a, 4.
c is backed up by the emergency power source 6b so that it can drive the pump 4b. It should be noted that each emergency diesel power generation facility is configured to start up when the normal power source 5 is lost.
しかしながら、第１図の構成では、通常電源５
が喪失し、非常電源６ａ，６ｂに切り替えたとき
に、非常電源６ａの非常用デイーゼル発電設備の
起動失敗をすると、非常電源６ｂのみとなるから
ポンプ４ｂしか運転されず、そのため、通常時の
ポンプ２台運転からポンプ１台運転となり、系統
流量が減少し、各冷却系１〜３の冷却機能が低下
するという問題を生ずる。また、ポンプ４ａ（あ
るいは４ｃ）または４ｂがトリツプした場合も同
様である。 However, in the configuration shown in Fig. 1, the normal power supply 5
If the emergency power source 6a fails to start when the emergency power source 6a and 6b switch to the emergency power source 6a and 6b, only the emergency power source 6b will be used, so only the pump 4b will be operated, and therefore the pump will not operate normally. The system changes from operating two pumps to operating one pump, resulting in a decrease in system flow rate and a problem in that the cooling function of each cooling system 1 to 3 is degraded. The same applies when the pump 4a (or 4c) or 4b trips.
本発明は上記に鑑みなされたもので、その目的
とするところは、原子炉冷却系統に供給する冷却
水量が生じても原子炉格納容器冷却系と燃料プー
ル冷却系との冷却機能が低下しないようにできる
原子炉冷却系統の制御装置を提供することにあ
る。 The present invention was made in view of the above, and its purpose is to prevent the cooling functions of the reactor containment vessel cooling system and the fuel pool cooling system from deteriorating even if the amount of cooling water supplied to the reactor cooling system increases. The object of the present invention is to provide a control device for a nuclear reactor cooling system that can perform
本発明の特徴は、補機冷却系の冷却水ラインに
冷却水供給量不足時に冷却水の供給を遮断する自
動弁を設け、原子炉冷却系統の各冷却系の機能を
維持するのに十分な冷却水を供給することが困難
になつたことを検出したら、その検出信号によつ
て制御手段を介して上記自動弁を閉とするように
制御する構成とした点にある。 A feature of the present invention is that the cooling water line of the auxiliary equipment cooling system is equipped with an automatic valve that shuts off the supply of cooling water when the supply of cooling water is insufficient. When it is detected that it has become difficult to supply cooling water, the automatic valve is controlled to close via the control means based on the detection signal.
以下本発明を第２図に示した実施例を用いて詳
細に説明する。 The present invention will be explained in detail below using the embodiment shown in FIG.
第２図は本発明の制御装置の一実施例を示す制
御系統図で、第１図と同一部分は同じ符号で示
し、ここでは説明を省略する。第２図において、
７は補器冷却系３の冷却水供給側に設けた冷却水
供給量不足時に冷却水供給を遮断する電磁弁など
の自動弁、８は通常電源５が喪失（停電など）し
て非常電源６ａ，６ｂに切り替えたときに、非常
電源６ａ用の非常用デイーゼル発電設備の起動失
敗などにより非常電源６ａの電圧が零かあるいは
非常に低いとそれを検出して動作し、常開接点８
ａを閉路とする不足電圧検出継電器、９は接点８a
が閉路すると自動弁７の電磁コイルに必要電流を
流して自動弁７を閉とする自動弁制御回路で、本
発明に係る制御装置は、自動弁７、不足電圧検出
継電器および自動弁制御回路９より構成してあ
る。 FIG. 2 is a control system diagram showing an embodiment of the control device of the present invention. The same parts as in FIG. In Figure 2,
7 is an automatic valve such as a solenoid valve installed on the cooling water supply side of the auxiliary cooling system 3 to cut off the cooling water supply in the event of insufficient supply of cooling water; 8 is an emergency power supply 6a when the normal power supply 5 is lost (power outage, etc.); , 6b, if the voltage of the emergency power source 6a is zero or very low due to failure to start the emergency diesel power generation equipment for the emergency power source 6a, the normally open contact 8 is activated.
Undervoltage detection relay with a closed circuit, 9 is contact 8 a
is an automatic valve control circuit that closes the automatic valve 7 by passing a necessary current through the electromagnetic coil of the automatic valve 7 when the circuit is closed. It is more structured.
長期にわたり系統の電源が喪失した場合は、原
子力発電設備は発電を停止しており、原子炉は隔
離される。このとき、原子炉冷却系統において、
冷却機能が必要となるものは、原子炉格納容器冷
却系１と燃料プール冷却系２である。 If the grid loses power for an extended period of time, nuclear power generation facilities will stop producing electricity and the reactor will be isolated. At this time, in the reactor cooling system,
The reactor containment cooling system 1 and the fuel pool cooling system 2 require a cooling function.
ところで、上記した本発明の実施例によれば、
通常電源５が喪失し、冷却水を原子炉冷却系統に
供給するポンプ４ａ〜４ｃをそれぞれ駆動する電
圧機の電源を非常電源６ａ，６ｂに切り替えた場
合、もし、非常電源６ａのための非常用デイーゼ
ル発電設備の起動失敗などのために、非常電源６
ａが喪失して、ポンプ４ｂのみの運転となつて、
原子炉冷却系統に供給する冷却水量が不足する
と、非常電源６ａの喪失が不足電圧検出継電器８
で検出されて、不足電圧検出継電器８が動作し
て、それの接点８aが閉路する。接点８aが閉路す
ると自動弁制御回路９が動作して、自動弁７の電
磁コイルに必要電流を流して、自動弁７を閉とす
る。したがつて、ポンプ４ｂからの冷却水は、原
子炉格納容器冷却系１と燃料プール冷却系２のみ
に供給されるようになり、これらの必要な冷却機
能を維持させることができる。 By the way, according to the embodiment of the present invention described above,
If the normal power source 5 is lost and the power supplies of the voltage generators that drive the pumps 4a to 4c that supply cooling water to the reactor cooling system are switched to the emergency power sources 6a and 6b, if the emergency power source 6a Emergency power supply 6
a is lost and only pump 4b is in operation,
When the amount of cooling water supplied to the reactor cooling system is insufficient, the loss of the emergency power supply 6a causes the undervoltage detection relay 8
is detected, the undervoltage detection relay 8 is activated, and its contact 8a is closed. When the contact point 8a is closed, the automatic valve control circuit 9 is activated, causing the necessary current to flow through the electromagnetic coil of the automatic valve 7, thereby closing the automatic valve 7. Therefore, the cooling water from the pump 4b is supplied only to the reactor containment vessel cooling system 1 and the fuel pool cooling system 2, making it possible to maintain their necessary cooling functions.
なお、一般に非常用デイーゼル発電設備は、通
常電源喪失後、約10秒で起動するようにしてある
ので、不足電圧検出継電器８がその後に不足電圧
の検出を開始するようにする限時手段を設けるこ
とが望しいことはいうまでもない。これにより自
動弁７の無駄な閉動作をなくすことができる。一
方、非常電源６ｂの喪失の場合は、非常電源６ａ
でポンプ４ａと４ｃとを駆動することができるか
ら、自動弁７を閉としなくとも、各冷却系１〜３
の冷却水機能を確保することができる。また、補
機冷却系３が複数である場合は、それぞれに自動
弁を設けて、同時にそれらの自動弁を閉とすれば
よい。 In addition, since emergency diesel power generation equipment is generally designed to start up in about 10 seconds after a power loss, a time limit means is provided so that the undervoltage detection relay 8 starts detecting undervoltage after that. Needless to say, this is desirable. This eliminates unnecessary closing operations of the automatic valve 7. On the other hand, in the case of loss of emergency power supply 6b, emergency power supply 6a
Since the pumps 4a and 4c can be driven by the
cooling water function can be ensured. Furthermore, when there are a plurality of auxiliary cooling systems 3, automatic valves may be provided for each of them, and the automatic valves may be closed at the same time.
また、第２図に示す実施例においては、原子炉
冷却系統に供給する冷却水量の不足を非常電源６
ａの喪失によつて検出するようにしているが、ポ
ンプ４ａか４ｃまたは４ｂのトリツプを検出した
ら、このトリツプ検出信号によつて自動弁制御回
路９を動作させて、自動弁７を閉とするようにし
てもよく、同一の効果を得ることができる。 In addition, in the embodiment shown in FIG. 2, the emergency power supply 6
When a trip of pump 4a, 4c, or 4b is detected, this trip detection signal operates automatic valve control circuit 9 to close automatic valve 7. The same effect can be obtained.
以上説明したように、本発明によれば、原子炉
冷却系統に供給する冷却水量に不足を生じたとき
に原子炉冷却系統の補機冷却系への冷却水供給を
遮断することができるので、原子炉冷却系統の原
子炉格納容器冷却系と燃料プール冷却系とは供給
する冷却水量に不足が生じても冷却機能が低下し
ないようにすることができ、系統の信頼性を向上
することができるという効果がある。 As explained above, according to the present invention, when there is a shortage in the amount of cooling water supplied to the reactor cooling system, the supply of cooling water to the auxiliary equipment cooling system of the reactor cooling system can be cut off. The reactor containment vessel cooling system and fuel pool cooling system in the reactor cooling system can prevent the cooling function from deteriorating even if there is a shortage in the amount of cooling water supplied, improving the reliability of the system. There is an effect.
第１図は従来の原子炉冷却系統の構成説明図、
第２図は本発明の原子炉冷却系統の制御装置の一
実施例を示す制御系統図である。
１……原子炉格納容器冷却系、２……燃料プー
ル冷却系、３……その他の補機冷却系、４ａ〜４
ｂ……ポンプ、５……通常電源、６ａ，６ｂ……
非常電源、７……自動弁、８……不足電圧検出継
電器、８a……継電器８の常開接点、９……自動
弁制御回路。
Figure 1 is an explanatory diagram of the configuration of a conventional reactor cooling system.
FIG. 2 is a control system diagram showing an embodiment of the reactor cooling system control device of the present invention. 1...Reactor containment vessel cooling system, 2...Fuel pool cooling system, 3...Other auxiliary equipment cooling systems, 4a-4
b...Pump, 5...Normal power supply, 6a, 6b...
Emergency power supply, 7... automatic valve, 8... undervoltage detection relay, 8 a ... normally open contact of relay 8, 9... automatic valve control circuit.
Claims (1)
その他の補機冷却系とよりなる原子炉冷却系統を
備え、前記各冷却系の機能を維持するための冷却
水流量を確保する複数台のポンプを設けてある原
子力発電設備の制御装置において、前記補機冷却
系の冷却水ラインに設けた供給冷却水量不足時に
冷却水の供給を遮断する自動弁と、前記各冷却系
の機能を維持するのに十分な冷却水を供給するこ
とが困難になつたことを検出する検出手段と、該
検出手段の出力により前記自動弁を閉とする制御
手段とよりなることを特徴とする原子炉冷却系統
の制御装置。 ２ 前記複数台のポンプの電源は、通常電源と該
通常電源喪失時のバツクアツプとしての複数の非
常電源とよりなり、前記検出手段は、前記通常電
源喪失のため前記非常電源で前記複数台のポンプ
を運転しているときに前記複数台のポンプのうち
前記各冷却系の機能維持が困難となるポンプの非
常電源喪失を検出すると動作する不足電圧検出手
段よりなる特許請求の範囲第１項記載の原子炉冷
却系統の制御装置。[Scope of Claims] 1. A reactor cooling system consisting of a reactor containment vessel cooling system, a fuel pool cooling system, and other auxiliary equipment cooling systems, and a cooling water flow rate to maintain the functions of each of the cooling systems. In a control device for a nuclear power generation facility that is provided with a plurality of pumps to secure the cooling water, an automatic valve that shuts off the supply of cooling water when the amount of supplied cooling water is insufficient is provided in the cooling water line of the auxiliary equipment cooling system, and each of the cooling systems A detection means for detecting that it has become difficult to supply sufficient cooling water to maintain the function of the automatic valve, and a control means for closing the automatic valve based on the output of the detection means. A control device for the reactor cooling system. 2. The power supply for the plurality of pumps is composed of a normal power supply and a plurality of emergency power supplies as a backup when the normal power supply is lost, and the detection means is configured to power the plurality of pumps with the emergency power supply due to the loss of the normal power supply. Claim 1, further comprising undervoltage detection means that operates when an emergency power loss is detected for a pump that makes it difficult to maintain the function of each of the cooling systems among the plurality of pumps when the pump is in operation. Control device for reactor cooling system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57030151A JPS58146895A (en) | 1982-02-25 | 1982-02-25 | Control device for reactor cooling circuit |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57030151A JPS58146895A (en) | 1982-02-25 | 1982-02-25 | Control device for reactor cooling circuit |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58146895A JPS58146895A (en) | 1983-09-01 |
| JPH023479B2 true JPH023479B2 (en) | 1990-01-23 |
Family
ID=12295753
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57030151A Granted JPS58146895A (en) | 1982-02-25 | 1982-02-25 | Control device for reactor cooling circuit |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58146895A (en) |
-
1982
- 1982-02-25 JP JP57030151A patent/JPS58146895A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS58146895A (en) | 1983-09-01 |
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