JPS63313094A - Device for supplying purging water to control rod driving mechanism - Google Patents
Device for supplying purging water to control rod driving mechanismInfo
- Publication number
- JPS63313094A JPS63313094A JP62147917A JP14791787A JPS63313094A JP S63313094 A JPS63313094 A JP S63313094A JP 62147917 A JP62147917 A JP 62147917A JP 14791787 A JP14791787 A JP 14791787A JP S63313094 A JPS63313094 A JP S63313094A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- water
- flow rate
- rod drive
- drive mechanism
- 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
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 117
- 238000010926 purge Methods 0.000 title claims abstract description 73
- 230000007246 mechanism Effects 0.000 title claims abstract description 45
- 230000037431 insertion Effects 0.000 claims abstract description 11
- 238000003780 insertion Methods 0.000 claims abstract description 11
- 238000000746 purification Methods 0.000 claims description 2
- 238000010586 diagram Methods 0.000 description 4
- 239000008400 supply water Substances 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 238000010612 desalination reaction Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 241000238558 Eucarida Species 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 1
- 230000001151 other effect 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
(gi業上の利用分野)
本発明は沸騰水型原子炉の原子炉圧力容器下部に多数本
設けられた制御棒駆動機構へパージ水を供給する制御棒
駆動機構パージ水供給装置に関する。[Detailed description of the invention] [Object of the invention] (Field of application in GI industry) The present invention supplies purge water to a control rod drive mechanism provided in large numbers at the bottom of a reactor pressure vessel of a boiling water reactor. The present invention relates to a control rod drive mechanism purge water supply device.
(従来の技術)
一般に、沸騰水型原子炉の原子炉圧力容器の下部には炉
心へ制御棒を挿入・引抜操作づ゛る制御棒駆動機構(以
下CRDという)が多数本設けられる。このCRDは通
常運転時には制御棒駆動機構電動機(以下CRD−電動
機という)により駆動され、緊急停止(以下スクラムと
いう)時には制御捧駆動水圧装置(以下CRD水圧装置
という)により駆動されるようになっている。(Prior Art) Generally, a large number of control rod drive mechanisms (hereinafter referred to as CRDs) are provided in the lower part of the reactor pressure vessel of a boiling water reactor for inserting and withdrawing control rods into the reactor core. During normal operation, this CRD is driven by a control rod drive mechanism electric motor (hereinafter referred to as CRD-motor), and during an emergency stop (hereinafter referred to as scram), it is driven by a control rod drive hydraulic device (hereinafter referred to as CRD hydraulic device). There is.
第3図はCRD水圧装置を示す構成図である。FIG. 3 is a configuration diagram showing the CRD hydraulic device.
原子炉格納′f1器1内に備えられた原子炉圧力容器2
の下部に多数本のCRD3が設けられ、そのCRD3に
接続してCRD水圧装v14が設けられる。Reactor pressure vessel 2 provided in reactor containment unit 1
A large number of CRDs 3 are provided at the bottom of the CRD 3, and a CRD hydraulic system v14 is provided connected to the CRD 3.
このCRD水圧装置4にはCRD3へ供給する供給水の
圧力を制御する水圧制御ユニット(以下トICUという
)5と、CRD3へ供給する供給水を昇圧するa、II
制御棒動水ポンプ(以下駆動水ポンプという)6とが備
えられる。This CRD water pressure device 4 includes a water pressure control unit (hereinafter referred to as ICU) 5 that controls the pressure of the water supplied to the CRD 3, and a and II water pressure units that increase the pressure of the water supplied to the CRD 3.
A control rod hydraulic pump (hereinafter referred to as a driving water pump) 6 is provided.
HCU 5は複数備え、られ、通常は2体のCRD3に
対して)−I CU 5が1基の割合で設けられる。A plurality of HCUs 5 are provided, and usually one ICU 5 is provided for each two CRDs 3.
1−I CU 5内には前記駆動水ポンプ6から充填水
ヘッダ7を通って送られる供給水を貯留するアキュムレ
ータ8と、このアキュムレータ8に貯留した供給水をス
クラム時にCRr)3へ供給するスクラム弁9とが備え
られる。1-I CU 5 includes an accumulator 8 that stores the supply water sent from the driving water pump 6 through the filling water header 7, and a scram that supplies the supply water stored in the accumulator 8 to the CRr) 3 at the time of scram. A valve 9 is provided.
前記駆動水ポンプ6は復水脱塩装置出口および復水貯蔵
プール(C8P)10に接続され、ポンプ叶出側から上
記復水貯蔵プール10ヘポンプ保護のためにミニマムフ
ローライン11が接続される。また、駆動水ポンプ6の
吐出側からCRD3ヘバージ水配′Q12が接続され、
このパージ水配管12に流量制御弁13が介装される。The driving water pump 6 is connected to the condensate desalination device outlet and the condensate storage pool (C8P) 10, and a minimum flow line 11 is connected from the pump outlet side to the condensate storage pool 10 for pump protection. In addition, a barge water distribution 'Q12 to the CRD3 is connected from the discharge side of the driving water pump 6,
A flow control valve 13 is interposed in this purge water pipe 12 .
この流量制御弁13は駆動水ポンプ6の吐出側圧力と原
子炉圧力容器2内の圧力との差圧から自動的に弁開度を
調節して、CRD3へ所定流量のパージ水を供給するよ
うになっている。The flow rate control valve 13 automatically adjusts the valve opening based on the differential pressure between the discharge side pressure of the driving water pump 6 and the pressure inside the reactor pressure vessel 2, and supplies a predetermined flow rate of purge water to the CRD 3. It has become.
このように構成されるCRD水圧装置4において、復水
貯蔵プール10J3よび復水脱塩装置から駆動水ポンプ
6により吸い込まれた供給水は、駆動水ポンプ6により
昇圧された後、HCLJ 5内のアキュムレータ8に貯
留される。そして、スクラム時にはスクラム弁9が閉動
作されることにより、アキュムレータ8に貯留された高
圧水がCRD3へ供給され、この高圧水により制御棒が
一斉に炉心へ挿入される。In the CRD hydraulic device 4 configured as described above, the supply water sucked in by the drive water pump 6 from the condensate storage pool 10J3 and the condensate desalination device is pressurized by the drive water pump 6 and then pumped into the HCLJ 5. It is stored in the accumulator 8. During scram, the scram valve 9 is closed, so that the high pressure water stored in the accumulator 8 is supplied to the CRD 3, and the control rods are inserted into the reactor core all at once by this high pressure water.
また、通常運転時には駆動水ポンプ6の吐出側からパー
ジ水配管12を通ってCRD3ヘパージ水が供給され、
このパージ水により原子炉圧力容器2内の異物の沈降が
防止される。In addition, during normal operation, purge water is supplied to the CRD 3 from the discharge side of the drive water pump 6 through the purge water pipe 12,
This purge water prevents foreign matter from settling inside the reactor pressure vessel 2.
(発明が解決しようとする問題点)
このように、パージ水配管12からCRD3へ常時パー
ジ水が供給されるが、CRD電動機によるC RD 3
駆動速麿とバージ水量の関係によってはCRDa内に炉
水が流入することがある。(Problems to be Solved by the Invention) In this way, purge water is constantly supplied from the purge water pipe 12 to the CRD 3, but the CRD 3 by the CRD motor
Depending on the relationship between drive speed and barge water volume, reactor water may flow into the CRDa.
つまり、制御棒に連結されたCRDa内の中空ピストン
を駆動することによって挿入・引抜を行ない、挿入の場
合にはCRDa内にあった中空ピストンが制御棒の挿入
に従って原子炉圧力容器2内に挿入されることから、そ
の中空ピストンが移動した容量に相当する水量をCRD
a内に供給する必要がある。In other words, insertion and withdrawal are performed by driving the hollow piston in CRDa connected to the control rod, and in the case of insertion, the hollow piston in CRDa is inserted into the reactor pressure vessel 2 as the control rod is inserted. Therefore, the amount of water corresponding to the volume moved by the hollow piston is calculated as CRD.
It is necessary to supply within a.
この場合、CRD3駆動速麿が比較的ゆるやかであれば
パージ水がCRD3内へ供給されることにより、炉水の
CRD3内への流入が防止されるが、CRD3駆動速酊
が比較的速い場合にはパージ水の供給が間に合わず炉水
がCRDa内に流入する。In this case, if the CRD3 drive speed is relatively slow, purge water is supplied into the CRD3, thereby preventing reactor water from flowing into the CRD3, but if the CRD3 drive speed is relatively fast, In this case, purge water was not supplied in time and reactor water flowed into CRDa.
CRDa内に炉水が流入した場合、CRD3の性能には
影響がないが、原子炉の定期検査時に作業員が原子炉圧
力容器下部ペデスタル内で作業を行なうに際し、CRD
3からの放射線ωが増大し、作業員の被曝防止上好まし
くない。If reactor water flows into the CRDa, it will not affect the performance of CRD3, but when workers work inside the lower pedestal of the reactor pressure vessel during regular reactor inspections, the CRD
The radiation ω from 3 increases, which is unfavorable in terms of preventing workers from being exposed to radiation.
CRD3内への炉水の流入を防止するには、CRD3の
操作状態に関係なく多量のパージ水をCRD3に供給す
ることが考えられるが、低温のパージ水を多量に原子炉
圧力容器2内に流入させることは炉出力の低下を招くこ
とから好ましくない。In order to prevent reactor water from flowing into the CRD 3, it is possible to supply a large amount of purge water to the CRD 3 regardless of the operating state of the CRD 3. It is not preferable to let it flow in because it causes a decrease in the furnace output.
本発明は上記の事情を考慮してなされたもので、原子炉
圧力容器内に多Rのパージ水を流入させることなく、制
御棒駆動機構が挿入操作される場合にもi、lJ御棒駆
動機橘内に炉水が流入することを防止することができる
とともに、作業員を被曝から守ることができる制御棒駆
動機構パージ水供給装置を提供することを目的とする。The present invention has been made in consideration of the above circumstances, and can be used to drive the i and lJ control rods even when the control rod drive mechanism is inserted without flowing multi-R purge water into the reactor pressure vessel. An object of the present invention is to provide a control rod drive mechanism purge water supply device that can prevent reactor water from flowing into a reactor and protect workers from radiation exposure.
(問題点を解決するための手段)
本発明は、原子炉圧力容器下部に多数本設けられた制御
棒駆動機構と、その制御棒駆動機構へ供給するパージ水
を背圧する昇圧ポンプと、この背圧ポンプから上記制御
棒駆動i構へ供給されるパージ水の流量を調節する流量
制御弁とが備えられた制御棒駆動機構パージ水供給装置
において、上記流量制御弁の下流側のパージ水のうち通
常のパージ水流量を越えるパージ水をバイパスさせるバ
イパス配管が設けられ、このバイパス配管に制御棒駆動
機構挿入操作信号を入力したときに閉動作を行なうバイ
パス弁が介装されたものである。(Means for Solving the Problems) The present invention provides a control rod drive mechanism provided in large numbers at the bottom of a reactor pressure vessel, a booster pump that backpressures purge water supplied to the control rod drive mechanism, and a booster pump that backpressures purge water supplied to the control rod drive mechanism. In a control rod drive mechanism purge water supply device equipped with a flow control valve that adjusts the flow rate of purge water supplied from a pressure pump to the control rod drive i structure, the purge water on the downstream side of the flow control valve is A bypass pipe is provided to bypass purge water exceeding the normal purge water flow rate, and a bypass valve is interposed in the bypass pipe to perform a closing operation when a control rod drive mechanism insertion operation signal is input.
(作用)
llJ御棒側棒駆動機構作されない場合および引抜操作
される場合には流m制御弁の下流側のパージ水のうち通
常のパージ水流量を越えるパージ水がバイパス配管から
バイパスされ、残りのパージ水が通常のパージ水として
制御棒駆動機構へ供給される。そして、制御棒駆動機構
が挿入操作される場合には、バイパス弁が制御棒駆動機
構挿入操作信号を入力して閉動作を行なう。(Function) When the llJ control rod side rod drive mechanism is not operated or when it is pulled out, the purge water that exceeds the normal purge water flow rate among the purge water on the downstream side of the flow m control valve is bypassed from the bypass piping, and the remaining purge water is supplied to the control rod drive mechanism as normal purge water. When the control rod drive mechanism is inserted, the bypass valve receives a control rod drive mechanism insertion operation signal and performs a closing operation.
こうして、バイパス弁が閉動作を行なうことにより、バ
イパスされていたパージ水が制御棒駆動機構へ供給され
る。したがって、制御棒駆動機構へ炉水が流入すること
が防止される。In this manner, the bypass valve closes, and the purge water that has been bypassed is supplied to the control rod drive mechanism. Therefore, reactor water is prevented from flowing into the control rod drive mechanism.
(実施例) ・
本発明に係る制御棒駆動機構パージ水供給装置の一実施
例を図面を参照して説明する。(Embodiment) - An embodiment of the control rod drive mechanism purge water supply device according to the present invention will be described with reference to the drawings.
パージ水供給装2は第1図に示ケように原子炉圧力容器
2下部に多数本設けられた制御棒駆f、IJ機構(以下
CHDという)3と、そのCRD3へ供給するパージ水
を昇圧する昇圧ポンプとしての制御棒駆動水ポンプ(以
下駆動水ポンプという)6と、この駆動水ポンプ6から
上記CRD3へ供給されるパージ水のvtRを調節する
流m制御弁13とが備えられるとともに、上記流m制御
弁13の下流側のパージ水のうち通常のパージ水流量を
越えるパージ水をバイパスさせるバイパス配管15が設
けられ、このバイパス配管15に制御棒駆動機構挿入操
作信号16を入力したときに閉動作を行なうバイパス弁
17が介装される。第1図の°うち第3図と同一部分に
ついては同一符号を付して説明を省略する。As shown in FIG. 1, the purge water supply system 2 boosts the pressure of purge water supplied to the control rod drive f, IJ mechanism (hereinafter referred to as CHD) 3 and its CRD 3, which are provided in large numbers at the bottom of the reactor pressure vessel 2. A control rod driven water pump (hereinafter referred to as a driven water pump) 6 as a pressure boosting pump, and a flow m control valve 13 for adjusting the vtR of purge water supplied from the driven water pump 6 to the CRD 3 are provided. A bypass piping 15 is provided to bypass the purge water exceeding the normal purge water flow rate among the purge water on the downstream side of the flow m control valve 13, and when the control rod drive mechanism insertion operation signal 16 is input to the bypass piping 15. A bypass valve 17 is interposed which performs a closing operation. Portions in FIG. 1 that are the same as those in FIG. 3 are designated by the same reference numerals and their explanations will be omitted.
上記流ffi f、IJ all弁13は通常のパージ
水流量を越える流量のパージ水を流すように調節される
。また、バイパス配管15は流量制御弁13の下流側の
パージ水配管12と復水貯蔵プール10とを接続して設
けられる。このバイパス配管15はミニマムフローライ
ン11の一部を着用して設けてもよい。バイパス弁17
は通常は開状態となっており、図示しない制御棒操作盤
からの制御棒挿入操作信号16を入力したときに閉動作
するようになっている。バイパス弁17としては計装用
空気系(IA系)からの空気により開閉動作を行なう空
気作動弁あるいは電力により開閉動作を行なう電磁弁等
が用いられる。このバイパス弁17の近傍には流量調整
用のオリフィス18あるいは絞り弁を設けてもよい。The flow ffi f, IJ all valve 13 is adjusted to flow purge water at a flow rate that exceeds the normal purge water flow rate. Further, the bypass pipe 15 is provided to connect the purge water pipe 12 on the downstream side of the flow control valve 13 and the condensate storage pool 10 . This bypass piping 15 may be provided by attaching a part of the minimum flow line 11. Bypass valve 17
is normally in an open state, and closes when a control rod insertion operation signal 16 is input from a control rod operation panel (not shown). As the bypass valve 17, an air-operated valve that opens and closes using air from an instrument air system (IA system) or a solenoid valve that opens and closes using electric power is used. An orifice 18 or a throttle valve for adjusting the flow rate may be provided near the bypass valve 17.
次に、上記実施例の作用について説明する。Next, the operation of the above embodiment will be explained.
CRD3が操作されない場合および引抜操作される場合
には、流量制御弁13の下流側のパージ水のうら通常の
パージ水流量を越えるパージ水がバイパス配管15から
バイパスされ、開状態のバイパス弁17を通って復水貯
蔵プール10へ流入する。そして、通常流量のパージ水
がパージ水配管12を通ってCRD3へ供給され、その
パージ水により原子炉圧力容置2内の異物の沈降が防止
される。When the CRD 3 is not operated or when the CRD 3 is withdrawn, the purge water on the downstream side of the flow rate control valve 13 that exceeds the normal purge water flow rate is bypassed from the bypass pipe 15 and the bypass valve 17 in the open state is bypassed. and flows into the condensate storage pool 10. Then, purge water at a normal flow rate is supplied to the CRD 3 through the purge water pipe 12, and the purge water prevents foreign matter from settling in the reactor pressure vessel 2.
一方、CRD3が挿入操作される場合には、制御棒操作
盤からの制御棒挿入操作信号16をバイパス弁17が入
力して閉動作を行なう。そして、バイパス弁17が閉動
作を行なうことによりバイパスされていたパージ水がパ
ージ水配管12を通ってCRD3へ供給される。したが
って、CRD3が挿入操作されて、CRDa内の中空ピ
ストンが移動する場合でも、その中空ピストンが移動し
た容量に相当するパージ水量を供給することができ、C
RDa内への炉水の流入を防止することができる。On the other hand, when the CRD 3 is inserted, the bypass valve 17 inputs the control rod insertion operation signal 16 from the control rod operation panel and performs the closing operation. When the bypass valve 17 closes, the purge water that has been bypassed is supplied to the CRD 3 through the purge water pipe 12. Therefore, even when the hollow piston inside CRDa moves when the CRD3 is inserted, it is possible to supply the amount of purge water corresponding to the volume moved by the hollow piston, and the CRD3 is inserted into the CRDa.
It is possible to prevent reactor water from flowing into the RDa.
次に、第2図を用いて本発明の他の実施例を説明する。Next, another embodiment of the present invention will be described using FIG. 2.
この実施例はバイパス配S!15が流ffiシリ御弁1
3の下流側のパージ水配管12と原子炉圧力容器2に接
続された配管(復水給水管20あるいは復水給水管20
に接続される原子炉水浄化系戻り配管21)とを接続し
て設けられるとともに、このバイパス配管15にバイパ
ス弁17および流填制御弁22が直列に設けられる。This example is bypass distribution S! 15 flows ffi siri control valve 1
The purge water pipe 12 on the downstream side of 3 and the pipe connected to the reactor pressure vessel 2 (condensate water supply pipe 20 or condensate water supply pipe 20
A bypass valve 17 and a flow control valve 22 are provided in series to this bypass pipe 15.
この実施例においては、流準制御弁22が駆動水ポンプ
6吐出圧力と原子炉圧力容器2内の圧力との差圧から自
動的にその弁開度を調節するようになっており、バイパ
ス弁17が開状態の場合でもバイパス流量を所定流量に
調節して原子炉圧力容器2内へ不要な低温のパージ水が
流入することを防止でき、プラント出力への影響をより
小さくすることができる。その他前記実施例と同様の効
果がある。In this embodiment, the flow level control valve 22 automatically adjusts its opening degree based on the differential pressure between the discharge pressure of the drive water pump 6 and the pressure inside the reactor pressure vessel 2, and the bypass valve Even when 17 is open, the bypass flow rate can be adjusted to a predetermined flow rate to prevent unnecessary low-temperature purge water from flowing into the reactor pressure vessel 2, thereby making it possible to further reduce the influence on the plant output. Other effects similar to those of the embodiment described above are obtained.
本発明に係るvlull棒駆動機横駆動機構パージ水供
給装置御弁の下流側のパージ水のうち通常のパージ水流
量を越えるパージ水をバイパスさせるバイパス配管が設
けられ、このバイパス配管に制御棒駆動機構挿入操作信
号を入力したときに閉動作を行なうバイパス弁が介装さ
れたから、原子炉圧力容器内に多用のパージ水を流入さ
せることなく、制御棒駆動機構が挿入操作される場合に
も制御棒駆flJ機構内に炉水が流入することを防止す
ることができるとともに、作業員を被曝から守ることが
できるという効果がある。Vlull rod drive machine lateral drive mechanism according to the present invention Purge water supply device A bypass piping is provided to bypass the purge water that exceeds the normal purge water flow rate among the purge water downstream of the control valve, and this bypass piping is provided with a control rod drive mechanism. Since a bypass valve is installed that closes when a mechanism insertion operation signal is input, control can be performed even when the control rod drive mechanism is inserted without injecting a large amount of purge water into the reactor pressure vessel. This has the effect of preventing reactor water from flowing into the rod drive flJ mechanism and protecting workers from radiation exposure.
【図面の簡単な説明】
第1図は本発明に係る制御棒駆動機構パージ水供給装置
の一実施例を示す構成図、第2図は本発明の他の実施例
を示す構成図、第3図は制御棒駆動水圧装置を示す構成
図である。
1・・・原子炉格納容器、2・・・原子炉圧力容器、3
・・・I、IJ n枠駆動機構、4・・・制御棒駆動水
圧装置、5・・・水圧制御ユニット、6・・・制御棒駆
動水ポンプ、7・・・充填水ヘッダ、8・・・アキュム
レータ、9・・・スクラム弁、10・・・復水貯蔵プー
ル、11・・・ミニマムフローライン、12・・・パー
ジ水配管、13・・・流量制御弁、15・・・バイパス
配管、16・・・制御棒駆動機構挿入操作信号、17・
・・バイパス弁、18・・・オリフィス、20・・・復
水給水管、21・・・原子炉水浄化系戻り配管、22・
・・流R制御弁。[BRIEF DESCRIPTION OF THE DRAWINGS] FIG. 1 is a configuration diagram showing one embodiment of the control rod drive mechanism purge water supply device according to the present invention, FIG. 2 is a configuration diagram showing another embodiment of the present invention, and FIG. The figure is a configuration diagram showing a control rod drive hydraulic system. 1... Reactor containment vessel, 2... Reactor pressure vessel, 3
... I, IJ n-frame drive mechanism, 4... Control rod drive water pressure device, 5... Water pressure control unit, 6... Control rod drive water pump, 7... Filling water header, 8... - Accumulator, 9... Scram valve, 10... Condensate storage pool, 11... Minimum flow line, 12... Purge water piping, 13... Flow rate control valve, 15... Bypass piping, 16... Control rod drive mechanism insertion operation signal, 17.
... Bypass valve, 18 ... Orifice, 20 ... Condensate water supply pipe, 21 ... Reactor water purification system return pipe, 22 ...
...Flow R control valve.
Claims (1)
機構と、その制御棒駆動機構へ供給するパージ水を昇圧
する昇圧ポンプと、この昇圧ポンプから上記制御棒駆動
機構へ供給されるパージ水の流量を調節する流量制御弁
とが備えられた制御棒駆動機構パージ水供給装置におい
て、上記流量制御弁の下流側のパージ水のうち通常のパ
ージ水流間を越えるパージ水をバイパスさせるバイパス
配管が設けられ、このバイパス配管に制御棒駆動機構挿
入操作信号を入力したときに閉動作を行なうバイパス弁
が介装されたことを特徴とする制御棒駆動機構パージ水
供給装置。 2、前記バイパス配管は流量制御弁下流と復水貯蔵プー
ルとを接続して設けられた特許請求の範囲第1項記載の
制御棒駆動機構パージ水供給装置。 3、前記バイパス配管は流量制御弁下流と原子炉水浄化
系戻り配管とを接続して設けられた特許請求の範囲第1
項記載の制御棒駆動機構パージ水供給装置。[Claims] 1. A control rod drive mechanism provided in large numbers at the bottom of the reactor pressure vessel, a boost pump that boosts the pressure of purge water supplied to the control rod drive mechanism, and a booster pump that drives the control rods. In a control rod drive mechanism purge water supply device that is equipped with a flow rate control valve that adjusts the flow rate of purge water supplied to the mechanism, a purge that exceeds the normal purge water flow rate of the purge water downstream of the flow rate control valve. A control rod drive mechanism purge water supply device comprising a bypass pipe for bypassing water, and a bypass valve that performs a closing operation when a control rod drive mechanism insertion operation signal is input to the bypass pipe. . 2. The control rod drive mechanism purge water supply device according to claim 1, wherein the bypass pipe is provided to connect the downstream side of the flow control valve and the condensate storage pool. 3. The bypass pipe is provided to connect the downstream of the flow control valve and the reactor water purification system return pipe.
Control rod drive mechanism purge water supply device as described in .
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP62147917A JPS63313094A (en) | 1987-06-16 | 1987-06-16 | Device for supplying purging water to control rod driving mechanism |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP62147917A JPS63313094A (en) | 1987-06-16 | 1987-06-16 | Device for supplying purging water to control rod driving mechanism |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS63313094A true JPS63313094A (en) | 1988-12-21 |
Family
ID=15441018
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP62147917A Pending JPS63313094A (en) | 1987-06-16 | 1987-06-16 | Device for supplying purging water to control rod driving mechanism |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS63313094A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007187518A (en) * | 2006-01-12 | 2007-07-26 | Hitachi Ltd | System for supplying control rod water pressure in nuclear power plant |
-
1987
- 1987-06-16 JP JP62147917A patent/JPS63313094A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007187518A (en) * | 2006-01-12 | 2007-07-26 | Hitachi Ltd | System for supplying control rod water pressure in nuclear power plant |
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