JPH06337295A - Hydraulic system for driving control rod - Google Patents

Hydraulic system for driving control rod

Info

Publication number
JPH06337295A
JPH06337295A JP5126877A JP12687793A JPH06337295A JP H06337295 A JPH06337295 A JP H06337295A JP 5126877 A JP5126877 A JP 5126877A JP 12687793 A JP12687793 A JP 12687793A JP H06337295 A JPH06337295 A JP H06337295A
Authority
JP
Japan
Prior art keywords
cooling water
valve
line
stop valve
control rod
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
JP5126877A
Other languages
Japanese (ja)
Inventor
Kazuo Kushima
和夫 久島
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 JP5126877A priority Critical patent/JPH06337295A/en
Publication of JPH06337295A publication Critical patent/JPH06337295A/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To prevent the erroneous function of a control rod driving mechanism during periodic inspection by providing a remote control valve for closing a cooling water stop valve when the pressure difference between a nuclear reactor and the inlet of a cooling water line, line measured by a differential manometer, exceeds a set value. CONSTITUTION:A cooling water stop valve 25 disposed in a cooling water line 4 is a remote control valve and when the pressure difference between a nuclear reactor 14 and the inlet of the cooling water line 4 exceeds a set value, a pressure difference signal 31 is delivered from a differential manometer 18 disposed in an instrumentation line 40. The cooling water stop valve 25 is closed automatically by the pressure difference signal 31. Consequently, even if an operator conducts the remote control of a hydraulic pressure control unit 7 while missing the closing operation of a return line stop valve 20, the differential manometer 18 detects the increase of cooling water supply pressure and interrupt the circuit between a control rod driving water pump 3 and the hydraulic control unit 7 thus preventing erroneous function of the control rod driving mechanism 8. The pump 3 is protected by providing a minimum flow line 16.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は沸騰水型原子炉の制御棒
駆動機構の誤動作を防止する制御棒駆動水圧系設備に関
する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a control rod drive hydraulic system facility for preventing malfunction of a control rod drive mechanism of a boiling water reactor.

【0002】[0002]

【従来の技術】一般に、沸騰水型原子炉においては、原
子炉内に収容され核分裂反応によって熱を発生している
炉心の下方より制御棒を挿入し、あるいは引き抜いて、
核分裂反応に利用される中性子の吸収量を調整すること
によって、原子炉の出力を調整している。制御棒の装荷
体数は原子炉の大小により異なるが、数十乃至百数十体
程度である。
2. Description of the Related Art Generally, in a boiling water reactor, a control rod is inserted or pulled out from below the core which is contained in the reactor and generates heat by a fission reaction.
The output of the nuclear reactor is adjusted by adjusting the absorption amount of neutrons used for fission reaction. The number of control rods to be loaded varies depending on the size of the reactor, but is about several tens to one hundred and several tens.

【0003】制御棒はその下端に結合する制御棒駆動機
構により挿入・引抜される。制御棒駆動機構は水圧によ
って駆動し、そのための駆動水は水圧制御ユニットを介
して制御棒駆動水圧系設備から供給される。また、制御
棒駆動機構内部の摺動部に使用しているシールリングや
位置指示のためのリードスイッチを高温の原子炉から保
護するための冷却水も水圧制御ユニットを介して制御棒
駆動水圧系設備から供給される。なお、制御棒駆動機構
及び水圧制御ユニットの台数は制御棒と同一である。
The control rod is inserted / pulled out by a control rod drive mechanism connected to the lower end of the control rod. The control rod drive mechanism is driven by water pressure, and the drive water therefor is supplied from the control rod drive water pressure system equipment via the water pressure control unit. In addition, the cooling water to protect the seal ring used for the sliding part inside the control rod drive mechanism and the reed switch for position indication from the high temperature reactor is also controlled by the control rod drive hydraulic system via the hydraulic control unit. Supplied from equipment. The number of control rod drive mechanisms and water pressure control units is the same as that of the control rods.

【0004】以下、図7を参照して制御棒駆動水圧系設
備の従来例について説明する。この制御棒駆動水圧系設
備は、原子炉14運転中においてはスピルオーバライン
1を経由してタービン設備(図示せず)から供給される
復水を、原子炉14が停止している定期検査中は復水貯
蔵槽2の復水をそれぞれ水源としている。そしてこの水
源から導かれる復水は制御棒駆動水ポンプ3で昇圧され
る。なお、この水源としてはプラントによって復水貯蔵
槽2の代わりに復水貯蔵タンクの復水が用いられる場合
もある。
A conventional example of control rod drive hydraulic system equipment will be described below with reference to FIG. This control rod drive water pressure system equipment is used during the periodic inspection in which the reactor 14 stops condensate supplied from the turbine equipment (not shown) via the spillover line 1 during the operation of the reactor 14. Condensed water in the condensate storage tank 2 is used as a water source. Condensed water introduced from this water source is boosted by the control rod drive water pump 3. As the water source, the condensate of the condensate storage tank may be used instead of the condensate storage tank 2 depending on the plant.

【0005】昇圧された復水は系統ライン30から分岐
する冷却水ライン4,駆動水ライン5,充填水ライン6
の3通りの経路で水圧制御ユニット7へ導かれる(以下
冷却水ライン,駆動水ライン,充填水ラインによって供
給される復水をそれぞれ冷却水,駆動水,充填水とい
う)。
The condensate whose pressure has been increased branches from the system line 30 into a cooling water line 4, a driving water line 5, and a filling water line 6.
Are guided to the water pressure control unit 7 through the following three routes (hereinafter, condensate supplied by the cooling water line, the driving water line, and the filling water line are referred to as cooling water, driving water, and filling water, respectively).

【0006】この内、冷却水としては制御棒駆動機構8
の1台当たり、毎分0.7〜1.3リットルが供給さ
れ、この流量は系統ライン30に配設された流量計9の
流量信号29をこの流量計9の下流側に配設された流量
調整弁10に伝達し、その開度を制御することによって
常時一定に維持されている。この流量調整弁10の上流
側及び下流側には、その保守・点検作業を容易にするた
めにそれぞれ流量調整弁前弁11及び流量調整弁後弁1
2が設けられている。また、冷却水ライン4には冷却水
止め弁13が設けられており、流量調整弁前弁11及び
流量調整弁後弁12と同様に手動弁である。
Of these, the control rod drive mechanism 8 is used as cooling water.
0.7 to 1.3 liters per minute are supplied to each unit of the flow rate signal 29 of the flow meter 9 provided in the system line 30 and the flow rate signal 29 is provided downstream of the flow meter 9. It is constantly maintained by being transmitted to the flow rate adjusting valve 10 and controlling its opening. On the upstream side and the downstream side of the flow rate adjusting valve 10, a flow rate adjusting valve front valve 11 and a flow rate adjusting valve rear valve 1 are provided to facilitate maintenance and inspection work.
Two are provided. A cooling water stop valve 13 is provided in the cooling water line 4 and is a manual valve like the flow rate adjusting valve front valve 11 and the flow rate adjusting valve rear valve 12.

【0007】また、駆動水は制御棒駆動機構8を挿入ま
たは引抜操作する時にのみ通水される。制御棒駆動機構
8を正常に駆動させるためには、駆動水の供給圧力を原
子炉14の圧力に対し所定の値ほど高く設定する必要が
あるため、系統ライン30の駆動水ライン5の分岐部よ
り下流側に配設された圧力調整弁15によって調整して
いる。
Further, the drive water is passed only when the control rod drive mechanism 8 is inserted or withdrawn. In order to drive the control rod drive mechanism 8 normally, it is necessary to set the supply pressure of the drive water higher than the pressure of the nuclear reactor 14 by a predetermined value. Therefore, the branch portion of the drive water line 5 of the system line 30. The pressure is adjusted by the pressure adjusting valve 15 arranged on the further downstream side.

【0008】さらに、充填水は原子炉14内の核分裂反
応を緊急に停止させるため制御棒駆動機構8を急速挿入
させる場合に備えて、水圧制御ユニット7内のアキュム
レータ(図示せず)に高圧水を充填するために通水す
る。従って、一旦充填が完了すれば再度充填が必要とな
るまで流れはない。
Further, the filling water is supplied to a high pressure water in an accumulator (not shown) in the water pressure control unit 7 in case the control rod drive mechanism 8 is rapidly inserted in order to urgently stop the nuclear fission reaction in the nuclear reactor 14. Water to fill. Therefore, once the filling is completed, there is no flow until the filling becomes necessary again.

【0009】制御棒駆動水ポンプ3の上流側と下流側は
ミニマムフローライン16によってバイパスされ、この
制御棒駆動水ポンプ3の締切運転防止及びその制御棒駆
動水ポンプ3下流側の配管表面で結露が発生しない程度
に復水の温度を上昇させている。また、制御棒駆動水ポ
ンプ3は水圧制御ユニット7への冷却水,駆動水,充填
水の供給以外に、パージライン17を介して原子炉再循
環ポンプ(図示せず)及び原子炉冷却材浄化系ポンプ
(図示せず)へパージ水を供給する機能も有している。
The upstream side and the downstream side of the control rod driving water pump 3 are bypassed by the minimum flow line 16, and the deadline operation of the control rod driving water pump 3 is prevented and dew condensation is formed on the pipe surface on the downstream side of the control rod driving water pump 3. The condensate temperature is raised to such an extent that no Further, the control rod driving water pump 3 supplies the cooling water, the driving water, and the filling water to the water pressure control unit 7 as well as the reactor recirculation pump (not shown) and the reactor coolant purification via the purge line 17. It also has a function of supplying purge water to a system pump (not shown).

【0010】原子炉14の圧力に対し、冷却水の供給圧
力が低過ぎると所定の冷却水流量が得られず、高過ぎる
と制御棒駆動機構8に不適切な水圧が加わって誤動作す
る可能性がある。このため、これらの圧力の差が適切な
値に保たれていることを監視できるように原子炉14と
冷却水ライン4入口の圧力を導く計装ライン40に差圧
計18が設けられている。特に、定期検査中に水圧制御
ユニット7もしくは制御棒駆動機構8の保守点検作業を
行うに当たっては、水圧制御ユニット7を1台ずつ隔離
していく作業が必要であり、この時には隔離していない
水圧制御ユニット7に集中する。よって、対応する制御
棒駆動機構8のみ冷却水供給圧力が上昇して誤動作する
可能性があった。
If the supply pressure of the cooling water is too low with respect to the pressure of the nuclear reactor 14, a predetermined cooling water flow rate cannot be obtained, and if it is too high, an inappropriate water pressure may be applied to the control rod drive mechanism 8 to cause a malfunction. There is. Therefore, the differential pressure gauge 18 is provided in the instrumentation line 40 that guides the pressures at the inlet of the reactor 14 and the cooling water line 4 so that it can be monitored that the difference between these pressures is maintained at an appropriate value. In particular, when performing maintenance work on the water pressure control unit 7 or the control rod drive mechanism 8 during the periodic inspection, it is necessary to isolate the water pressure control units 7 one by one. Focus on the control unit 7. Therefore, there is a possibility that only the corresponding control rod drive mechanism 8 may malfunction due to an increase in cooling water supply pressure.

【0011】この現象を防止するために、冷却水ライン
4から分岐して原子炉冷却材浄化系の原子炉戻りライン
(図示せず)へ接続するリターンライン19を設け、水
圧制御ユニット7の隔離作業を行う場合には、リターン
ライン19から原子炉冷却材浄化系及び原子炉給水系
(図示せず)を経由して原子炉14へ冷却水をバイパス
させることにより、冷却水供給圧力の上昇を防止する運
用としている。なお、リターンライン19には通常時に
冷却水がバイパスされないように手動のリターンライン
止め弁20が設けられている。
In order to prevent this phenomenon, a return line 19 is provided which branches from the cooling water line 4 and is connected to the reactor return line (not shown) of the reactor coolant purification system to isolate the water pressure control unit 7. When performing work, the cooling water supply pressure is increased by bypassing the cooling water from the return line 19 to the reactor 14 via the reactor coolant purification system and the reactor water supply system (not shown). The operation is to prevent. The return line 19 is provided with a manual return line stop valve 20 so that the cooling water is not bypassed during normal operation.

【0012】[0012]

【発明が解決しようとする課題】上述の従来の制御棒駆
動水圧系設備においては、水圧制御ユニットの隔離作業
と、原子炉冷却材浄化系または原子炉給水系の保守点検
作業が重なった場合には、リターンラインの通水不能、
あるいは通水可能な状況での作業員によるリターンライ
ン止め弁の不操作によって冷却水供給圧力の上昇による
制御棒駆動機構の誤動作が起こる可能性があった。ま
た、加圧源である制御棒駆動水ポンプを停止すれば上述
した制御棒駆動機構が誤動作する可能性はなくなるが、
一部の水圧制御ユニットのみを隔離する場合や、原子炉
再循環ポンプまたは原子炉冷却材浄化系ポンプが運転中
でこれらのポンプにパージ水を供給する必要がある場合
には、制御棒駆動水ポンプを停止させることはできな
い。
In the conventional control rod drive hydraulic system equipment described above, when the isolation work of the water pressure control unit and the maintenance inspection work of the reactor coolant purification system or the reactor water supply system overlap with each other. Is impenetrable to the return line,
Alternatively, there is a possibility that the control rod drive mechanism malfunctions due to an increase in the cooling water supply pressure due to the operator not operating the return line stop valve in a situation where water can pass. Further, if the control rod drive water pump that is the pressurizing source is stopped, the above-mentioned control rod drive mechanism may not malfunction,
If only some of the water pressure control units are isolated, or if the reactor recirculation pump or reactor coolant purification system pump is operating and it is necessary to supply purge water to these pumps, control rod drive water The pump cannot be stopped.

【0013】本発明は係る従来の事情に対処してなされ
たものであり、その目的は、定期検査中の制御棒駆動機
構の誤動作防止を図る制御棒駆動水圧系設備を提供する
ことにある。
The present invention has been made in view of the above conventional circumstances, and an object thereof is to provide a control rod drive hydraulic system facility for preventing malfunction of the control rod drive mechanism during a periodic inspection.

【0014】[0014]

【課題を解決するための手段】上記目的を達成するた
め、本発明の制御棒駆動水圧系設備は、請求項1記載の
発明では沸騰水型原子炉の出力を制御する制御棒駆動機
構に駆動水及び冷却水を供給する系統ラインと、この系
統ラインから分岐し駆動水を制御棒駆動機構に導く駆動
水ラインと、冷却水を制御棒駆動機構に導き冷却水止め
弁を有する冷却水ラインと、系統ラインに設けられ駆動
水と冷却水の流量を調整し上流側及び下流側にそれぞれ
前弁及び後弁を配設して成る流量調整弁と、原子炉と前
記冷却水ラインの入口の差圧を計測する差圧計と、系統
ラインから分岐し原子炉冷却材浄化系に前記冷却材を導
き前記差圧の上昇を防止しリターンライン止め弁を有す
るリターンラインとを備えて成る制御棒駆動水圧系設備
において、前記冷却水止め弁は前記差圧計の差圧が設定
値以上となった場合に閉動作する遠隔操作弁であること
を特徴とする制御棒駆動水圧系設備を提供するものであ
る。
In order to achieve the above object, the control rod drive hydraulic system equipment of the present invention is a control rod drive mechanism for controlling the output of a boiling water reactor according to the invention of claim 1. A system line for supplying water and cooling water, a drive water line branched from this system line for guiding drive water to the control rod drive mechanism, and a cooling water line for guiding cooling water to the control rod drive mechanism and having a cooling water stop valve , A flow rate adjusting valve that is installed in the system line and that adjusts the flow rates of the driving water and the cooling water and has front and rear valves on the upstream and downstream sides, respectively, and the difference between the reactor and the inlet of the cooling water line. Control rod drive water pressure provided with a differential pressure gauge for measuring pressure and a return line branched from a system line to guide the coolant to a reactor coolant purification system and prevent the differential pressure from rising and having a return line stop valve Cooling in system equipment Valve is intended to provide a control rod drive hydraulic system facility, which is a remotely operated valve for closing operation when the differential pressure of the differential pressure gauge is equal to or larger than a set value.

【0015】請求項2記載の発明では、前記冷却水止め
弁が遠隔操作弁であることに代えて、前記冷却水止め弁
をバイパスする冷却水止め弁バイパスラインと、この冷
却水止め弁バイパスラインに配設される冷却水止め弁バ
イパス弁とを有し、この冷却水止め弁バイパス弁は前記
差圧計の差圧が設定値以上となった場合に閉動作する遠
隔操作弁であることを特徴とする請求項1記載の制御棒
駆動水圧系設備を提供するものである。
According to a second aspect of the present invention, instead of the cooling water stop valve being a remote control valve, a cooling water stop valve bypass line that bypasses the cooling water stop valve and the cooling water stop valve bypass line. And a cooling water stop valve bypass valve, wherein the cooling water stop valve bypass valve is a remote operated valve that closes when the differential pressure of the differential pressure gauge exceeds a set value. The control rod drive hydraulic system facility according to claim 1 is provided.

【0016】請求項3記載の発明では、前記冷却水止め
弁が遠隔操作弁であることに代えて、前記流量調整弁を
差圧計の差圧が設定値以上となった場合に閉動作する遠
隔操作弁としたことを特徴とする請求項1記載の制御棒
駆動水圧系設備を提供するものである。
According to a third aspect of the invention, instead of the cooling water stop valve being a remote control valve, a remote control for closing the flow rate adjusting valve when the differential pressure of the differential pressure gauge exceeds a set value. The control rod drive hydraulic system facility according to claim 1, characterized in that it is an operation valve.

【0017】請求項4記載の発明では、前記冷却水止め
弁が遠隔操作弁であることに代えて、前記前弁または後
弁を差圧計の差圧が設定値以上となった場合に閉動作す
る遠隔操作弁としたことを特徴とする請求項1記載の制
御棒駆動水圧系設備を提供するものである。
According to a fourth aspect of the present invention, instead of the cooling water stop valve being a remote control valve, the front valve or the rear valve is closed when the differential pressure of the differential pressure gauge exceeds a set value. The control rod drive hydraulic system facility according to claim 1, wherein the remote control valve is used.

【0018】請求項5記載の発明では、前記冷却水止め
弁が遠隔操作弁であることに代えて、前記リターンライ
ン止め弁を差圧計の差圧が設定値以上となった場合に開
動作する遠隔操作弁としたことを特徴とする請求項1記
載の制御棒駆動水圧系設備を提供するものである。
According to the fifth aspect of the invention, instead of the cooling water stop valve being a remote control valve, the return line stop valve is opened when the differential pressure of the differential pressure gauge exceeds a set value. A control rod drive hydraulic system facility according to claim 1, characterized in that it is a remote control valve.

【0019】請求項6記載の発明では、前記冷却水止め
弁が遠隔操作弁であることに代えて、冷却水を復水貯蔵
槽に導き連絡ライン止め弁を有する連絡ラインを有し、
この連絡ライン止め弁は前記差圧計の差圧が設定値以上
となった場合に開動作する遠隔操作弁であることを特徴
とする請求項1記載の制御棒駆動水圧系設備を提供する
ものである。
According to a sixth aspect of the invention, instead of the cooling water stop valve being a remote control valve, there is a connecting line for guiding the cooling water to the condensate storage tank and having a connecting line stop valve,
2. The control rod drive hydraulic system facility according to claim 1, wherein the connecting line stop valve is a remote operated valve that opens when the differential pressure of the differential pressure gauge exceeds a set value. is there.

【0020】[0020]

【作用】上記構成の制御棒駆動水圧系設備においては、
原子炉と冷却水ライン入口との差圧が設定値以上となっ
た時に、差圧計の発する差圧信号により制御棒駆動水ポ
ンプと水圧制御ユニットの間の弁が自動的に閉じる。こ
の弁の閉止によって、供給圧力を遮断して冷却水供給圧
力の上昇による制御棒駆動機構の誤動作を防止する。あ
るいは水圧制御ユニット以外へのライン上の弁を有する
ものにおいては、原子炉と冷却水ライン入口との差圧が
設定値以上となった時に、差圧計の発する差圧信号によ
り同様に自動的に開動作する。この弁の開動作によって
過大な圧力を逃がして冷却水供給圧力の上昇による制御
棒駆動機構の誤動作を防止する。
[Operation] In the control rod drive hydraulic system equipment having the above configuration,
When the differential pressure between the reactor and the inlet of the cooling water line exceeds the set value, the valve between the control rod drive water pump and the hydraulic pressure control unit is automatically closed by the differential pressure signal generated by the differential pressure gauge. By closing this valve, the supply pressure is shut off to prevent the control rod drive mechanism from malfunctioning due to an increase in the cooling water supply pressure. Or, in the case where the valve on the line other than the water pressure control unit is provided, when the pressure difference between the reactor and the cooling water line inlet exceeds the set value, the pressure difference signal generated by the differential pressure gauge automatically Open operation. By opening the valve, an excessive pressure is released to prevent the control rod drive mechanism from malfunctioning due to an increase in the cooling water supply pressure.

【0021】[0021]

【実施例】以下に本発明に係る制御棒駆動水圧系設備の
第1の実施例を図1に基づき説明する。なお、以下の図
1乃至図6において図7と同一部分については同一符号
を付し、その構成の説明は省略する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of control rod drive hydraulic system equipment according to the present invention will be described below with reference to FIG. In the following FIGS. 1 to 6, the same parts as those in FIG.

【0022】本実施例では、冷却水ライン4に配設され
た冷却水止め弁25を遠隔操作弁とし、原子炉14と冷
却水ライン4入口との差圧が設定値以上となったときに
計装ライン40に配設された差圧計18から差圧信号3
1が発信され、この差圧信号31により冷却水止め弁2
5が自動的に閉動作する。
In this embodiment, the cooling water stop valve 25 arranged in the cooling water line 4 is used as a remote control valve, and when the differential pressure between the reactor 14 and the inlet of the cooling water line 4 exceeds a set value. The differential pressure signal 3 from the differential pressure gauge 18 arranged on the instrumentation line 40.
1 is transmitted, and the cooling water stop valve 2 is generated by this differential pressure signal 31.
5 automatically closes.

【0023】これにより、定期検査中に作業員がリター
ンライン止め弁20の開操作を忘れたまま水圧制御ユニ
ット7の隔離作業を行ってしまった場合でも、冷却水供
給圧力の上昇を差圧計18が検出して制御棒駆動水ポン
プ3と水圧制御ユニット7の間を遮断するので制御棒駆
動機構8の誤動作を防止することができる。なお、制御
棒駆動水ポンプ3の吐出側が遮断されてもミニマムフロ
ーライン16には通水されているので制御棒駆動水ポン
プが締切運転により、損傷に至ることはない。
As a result, even if the worker forgets to open the return line stop valve 20 during the periodic inspection and performs the isolation work of the water pressure control unit 7, the differential pressure gauge 18 increases the cooling water supply pressure. Is detected and the control rod drive water pump 3 and the water pressure control unit 7 are shut off from each other, so that the control rod drive mechanism 8 can be prevented from malfunctioning. Even if the discharge side of the control rod drive water pump 3 is shut off, water is passed through the minimum flow line 16 so that the control rod drive water pump will not be damaged by the shutoff operation.

【0024】次に本発明に係る制御棒駆動水圧系設備の
第2の実施例について図2を用いて説明する。本実施例
では、冷却水止め弁13をバイパスする冷却水止め弁バ
イパスライン23を冷却水ライン4に設け、その冷却水
止め弁バイパスライン23上に冷却水止め弁バイパス弁
21を設けている。
Next, a second embodiment of the control rod drive hydraulic system equipment according to the present invention will be described with reference to FIG. In this embodiment, a cooling water stop valve bypass line 23 that bypasses the cooling water stop valve 13 is provided in the cooling water line 4, and the cooling water stop valve bypass valve 21 is provided on the cooling water stop valve bypass line 23.

【0025】このように構成された第2の実施例におい
ては、原子炉14と冷却水ライン4入口との差圧が設定
値以上となった時に差圧計18が発する差圧信号32に
より、冷却水止め弁バイパス弁21が閉動作する。冷却
水止め弁13は定期検査中は閉運用し、原子炉14の通
常運転中は開運用する。
In the second embodiment thus constructed, the cooling is performed by the differential pressure signal 32 generated by the differential pressure gauge 18 when the differential pressure between the reactor 14 and the inlet of the cooling water line 4 exceeds the set value. The water stop valve bypass valve 21 is closed. The cooling water stop valve 13 is closed during the regular inspection and opened during the normal operation of the reactor 14.

【0026】これにより、前記第1の実施例と同等の効
果が得られることに加え、原子炉14の通常運転中に差
圧計18の誤信号によって冷却水止め弁バイパス弁21
が閉じたとしても、冷却水止め弁13が開状態であるこ
とから、水圧制御ユニット7への冷却水供給上は何ら支
障を生ずることがないという効果も有している。
As a result, in addition to the effect equivalent to that of the first embodiment, the cooling water stop valve bypass valve 21 due to an erroneous signal from the differential pressure gauge 18 during the normal operation of the reactor 14.
Even if is closed, since the cooling water stop valve 13 is in the open state, there is also an effect that there is no problem in supplying cooling water to the water pressure control unit 7.

【0027】次に、本発明に係る制御棒駆動水圧系設備
の第3の実施例について図3を用いて説明する。本実施
例では原子炉14と冷却水ライン4入口との差圧が設定
値以上となった時に、差圧計18が発する差圧信号33
により、系統ライン30に配設された流量調整弁26が
自動的に閉動作する。
Next, a third embodiment of the control rod drive hydraulic system equipment according to the present invention will be described with reference to FIG. In this embodiment, when the differential pressure between the reactor 14 and the inlet of the cooling water line 4 becomes equal to or higher than the set value, the differential pressure signal 33 generated by the differential pressure gauge 18 is generated.
As a result, the flow rate adjusting valve 26 arranged in the system line 30 automatically closes.

【0028】これにより、前記第1の実施例と同等の効
果を得ることができる。さらに、本発明に係る制御棒駆
動水圧系設備の第4の実施例について図4に基づいて説
明する。
As a result, the same effect as that of the first embodiment can be obtained. Further, a fourth embodiment of the control rod drive hydraulic system facility according to the present invention will be described with reference to FIG.

【0029】本実施例では系統ライン30に配設された
流量調整弁10の上流側に設置されている流量調整弁前
弁27を遠隔操作弁とし、原子炉14と冷却水ライン4
入口との差圧が設定値となった時に、差圧計18の発す
る差圧信号34を流量調整弁前弁27に送信し、流量調
整弁前弁27が閉動作するようにしたものである。
In this embodiment, the flow control valve front valve 27 installed upstream of the flow control valve 10 arranged in the system line 30 is used as a remote control valve, and the reactor 14 and the cooling water line 4 are connected.
When the differential pressure with the inlet reaches a set value, the differential pressure signal 34 generated by the differential pressure gauge 18 is transmitted to the flow rate regulating valve front valve 27 so that the flow rate regulating valve front valve 27 is closed.

【0030】これにより、前記第1の実施例と同等の効
果を得ることができる。なお、流量調整弁前弁27に代
えて系統ライン30の下流側に設置されている流量調整
弁後弁12を遠隔操作弁として用いても同等の効果が得
られるのは言うまでもない。
As a result, the same effect as that of the first embodiment can be obtained. Needless to say, the same effect can be obtained even if the flow control valve rear valve 12 installed on the downstream side of the system line 30 is used as the remote control valve instead of the flow control valve front valve 27.

【0031】次に、本発明の第5の実施例について図5
に基づいて説明する。本実施例においては、系統ライン
30の下流側に接続されたリターンライン19に配設さ
れているリターンライン止め弁28を遠隔操作弁とし
て、原子炉14と冷却水ライン4入口との差圧が設定値
以上になった時に、差圧計18が発する差圧信号35に
よってリターンライン止め弁28が開動作するものであ
る。
Next, a fifth embodiment of the present invention will be described with reference to FIG.
It will be described based on. In the present embodiment, the return line stop valve 28 provided in the return line 19 connected to the downstream side of the system line 30 is used as a remote control valve, and the differential pressure between the reactor 14 and the cooling water line 4 inlet is set. The return line stop valve 28 is opened by the differential pressure signal 35 generated by the differential pressure gauge 18 when the value exceeds the set value.

【0032】これにより、定期検査中に作業員がリター
ンライン止め弁28の開操作を忘れたまま、水圧制御ユ
ニット7の隔離作業を行ってしまう場合においても、冷
却水供給圧力の上昇を差圧計18が検出してリターンラ
イン19に通水させることが可能である。また、それと
同時に冷却水供給圧力を低下させるので制御棒駆動機構
8の誤操作を防止することができる。
As a result, even when the worker forgets to open the return line stop valve 28 during the periodic inspection and performs the isolation work of the water pressure control unit 7, the increase in the cooling water supply pressure is measured by the differential pressure gauge. It is possible for 18 to detect and pass water to the return line 19. At the same time, the cooling water supply pressure is reduced, so that the control rod drive mechanism 8 can be prevented from being erroneously operated.

【0033】最後に、本発明に係る制御棒駆動水圧系設
備の第6の実施例について図6を用いて説明する。本実
施例では、冷却水ライン4入口下流部の系統ライン30
から分岐し復水貯蔵槽2へ導く連絡ライン22を設け、
同ライン上には遠隔操作可能な連絡ライン止め弁24を
設けている。そして原子炉14と冷却水ライン4入口と
の差圧が設定値以上になった時、差圧計18の発する差
圧信号36により連絡ライン止め弁24が開動作する。
Finally, a sixth embodiment of the control rod drive hydraulic system equipment according to the present invention will be described with reference to FIG. In the present embodiment, the system line 30 downstream of the inlet of the cooling water line 4
A communication line 22 is provided that branches from this to the condensate storage tank 2.
A communication line stop valve 24 that can be remotely operated is provided on the same line. When the pressure difference between the reactor 14 and the inlet of the cooling water line 4 exceeds the set value, the communication line stop valve 24 is opened by the pressure difference signal 36 generated by the pressure difference gauge 18.

【0034】これにより、定期検査中に作業員がリター
ンライン止め弁20の開操作を忘れたまま、水圧制御ユ
ニット7の隔離作業を行ってしまう場合においても、冷
却水供給圧力の上昇を差圧計18が検出して連絡ライン
止め弁24が開動作するので冷却水供給圧力を低下させ
ることが可能である。
As a result, even if the worker forgets to open the return line stop valve 20 during the regular inspection and performs the isolation work of the water pressure control unit 7, the increase in the cooling water supply pressure is measured by the differential pressure gauge. 18 detects and the connecting line stop valve 24 opens, so that the cooling water supply pressure can be reduced.

【0035】[0035]

【発明の効果】以上説明したように本発明の制御棒駆動
水圧系設備においては、定期検査中の制御棒駆動機構の
誤動作を防止することが可能であり、もって制御棒駆動
水圧系設備の健全性の向上を図ることができる。
As described above, in the control rod drive hydraulic system facility of the present invention, it is possible to prevent malfunction of the control rod drive mechanism during the periodic inspection, and thus the soundness of the control rod drive hydraulic system facility is improved. It is possible to improve the sex.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明に係る制御棒駆動水圧系設備の第1の実
施例を示す系統構成図。
FIG. 1 is a system configuration diagram showing a first embodiment of a control rod drive hydraulic system facility according to the present invention.

【図2】本発明に係る制御棒駆動水圧系設備の第2の実
施例を示す系統構成図。
FIG. 2 is a system configuration diagram showing a second embodiment of control rod drive hydraulic system equipment according to the present invention.

【図3】本発明に係る制御棒駆動水圧系設備の第3の実
施例を示す系統構成図。
FIG. 3 is a system configuration diagram showing a third embodiment of a control rod drive hydraulic system facility according to the present invention.

【図4】本発明に係る制御棒駆動水圧系設備の第4の実
施例を示す系統構成図。
FIG. 4 is a system configuration diagram showing a fourth embodiment of control rod drive hydraulic system equipment according to the present invention.

【図5】本発明に係る制御棒駆動水圧系設備の第5の実
施例を示す系統構成図。
FIG. 5 is a system configuration diagram showing a fifth embodiment of a control rod drive hydraulic system facility according to the present invention.

【図6】本発明に係る制御棒駆動水圧系設備の第6の実
施例を示す系統構成図。
FIG. 6 is a system configuration diagram showing a sixth embodiment of control rod drive hydraulic system equipment according to the present invention.

【図7】制御棒駆動水圧系設備の従来例を示す系統構成
図。
FIG. 7 is a system configuration diagram showing a conventional example of control rod drive hydraulic system equipment.

【符号の説明】[Explanation of symbols]

4…冷却水ライン 5…駆動水ライン 10…流量調整弁 11…流量調整弁前弁 12…流量調整弁後弁 13…冷却水止め弁 14…原子炉 18…差圧計 19…リターンライン 20…リターンライン
止め弁 21…冷却水止め弁バイパス弁 22…連絡ライン 23…冷却水止め弁バイパスライン24…連絡ライン止
め弁 25…冷却水止め弁 26…流量調整弁 27…流量調整弁前弁 28…リターンライン
止め弁 30…系統ライン 31…差圧信号 32…差圧信号 33…差圧信
号 34…差圧信号 35…差圧信号 36…差圧信号
4 ... Cooling water line 5 ... Driving water line 10 ... Flow rate adjusting valve 11 ... Flow rate adjusting valve front valve 12 ... Flow rate adjusting valve rear valve 13 ... Cooling water stop valve 14 ... Reactor 18 ... Differential pressure gauge 19 ... Return line 20 ... Return Line stop valve 21 ... Cooling water stop valve bypass valve 22 ... Communication line 23 ... Cooling water stop valve bypass line 24 ... Communication line stop valve 25 ... Cooling water stop valve 26 ... Flow rate adjusting valve 27 ... Flow rate adjusting valve front valve 28 ... Return Line stop valve 30 ... System line 31 ... Differential pressure signal 32 ... Differential pressure signal 33 ... Differential pressure signal 34 ... Differential pressure signal 35 ... Differential pressure signal 36 ... Differential pressure signal

Claims (6)

【特許請求の範囲】[Claims] 【請求項1】 沸騰水型原子炉の出力を制御する制御棒
駆動機構に駆動水及び冷却水を供給する系統ラインと、
この系統ラインから分岐し駆動水を制御棒駆動機構に導
く駆動水ラインと、冷却水を制御棒駆動機構に導き冷却
水止め弁を有する冷却水ラインと、系統ラインに設けら
れ駆動水と冷却水の流量を調整し上流側及び下流側にそ
れぞれ前弁及び後弁を配設して成る流量調整弁と、原子
炉と前記冷却水ラインの入口の差圧を計測する差圧計
と、系統ラインから分岐し原子炉冷却材浄化系に前記冷
却材を導き前記差圧の上昇を防止しリターンライン止め
弁を有するリターンラインとを備えて成る制御棒駆動水
圧系設備において、前記冷却水止め弁は前記差圧計の差
圧が設定値以上となった場合に閉動作する遠隔操作弁で
あることを特徴とする制御棒駆動水圧系設備。
1. A system line for supplying drive water and cooling water to a control rod drive mechanism for controlling the output of a boiling water reactor,
A drive water line that branches from this system line to guide the drive water to the control rod drive mechanism, a cooling water line that guides cooling water to the control rod drive mechanism and has a cooling water stop valve, and drive water and cooling water provided in the system line From the system line, a flow rate adjustment valve that adjusts the flow rate of the In a control rod drive hydraulic system facility comprising a branch line for guiding the coolant to a reactor coolant purification system and preventing the rise of the differential pressure, and a return line having a return line stop valve, the cooling water stop valve is A control rod drive hydraulic system facility characterized in that it is a remote operated valve that closes when the differential pressure of the differential pressure gauge exceeds a set value.
【請求項2】 前記冷却水止め弁が遠隔操作弁であるこ
とに代えて、前記冷却水止め弁をバイパスする冷却水止
め弁バイパスラインと、この冷却水止め弁バイパスライ
ンに配設される冷却水止め弁バイパス弁とを有し、この
冷却水止め弁バイパス弁は前記差圧計の差圧が設定値以
上となった場合に閉動作する遠隔操作弁であることを特
徴とする請求項1記載の制御棒駆動水圧系設備。
2. A cooling water stop valve bypass line that bypasses the cooling water stop valve, and a cooling provided in the cooling water stop valve bypass line, instead of the cooling water stop valve being a remote control valve. 2. A water stop valve bypass valve, wherein the cooling water stop valve bypass valve is a remote control valve that closes when the differential pressure of the differential pressure gauge exceeds a set value. Control rod drive hydraulic system equipment.
【請求項3】 前記冷却水止め弁が遠隔操作弁であるこ
とに代えて、前記流量調整弁を差圧計の差圧が設定値以
上となった場合に閉動作する遠隔操作弁としたことを特
徴とする請求項1記載の制御棒駆動水圧系設備。
3. The cooling water stop valve is a remote control valve instead of a remote control valve, and the flow rate adjusting valve is a remote control valve that closes when the differential pressure of a differential pressure gauge exceeds a set value. The control rod drive hydraulic system facility according to claim 1.
【請求項4】 前記冷却水止め弁が遠隔操作弁であるこ
とに代えて、前記前弁または後弁を差圧計の差圧が設定
値以上となった場合に閉動作する遠隔操作弁としたこと
を特徴とする請求項1記載の制御棒駆動水圧系設備。
4. Instead of the cooling water stop valve being a remote control valve, the front valve or the rear valve is a remote control valve that closes when the differential pressure of a differential pressure gauge exceeds a set value. The control rod drive hydraulic system facility according to claim 1, wherein
【請求項5】 前記冷却水止め弁が遠隔操作弁であるこ
とに代えて、前記リターンライン止め弁を差圧計の差圧
が設定値以上となった場合に開動作する遠隔操作弁とし
たことを特徴とする請求項1記載の制御棒駆動水圧系設
備。
5. Instead of the cooling water stop valve being a remote control valve, the return line stop valve is a remote control valve that opens when the differential pressure of a differential pressure gauge exceeds a set value. The control rod drive hydraulic system facility according to claim 1.
【請求項6】 前記冷却水止め弁が遠隔操作弁であるこ
とに代えて、冷却水を復水貯蔵槽に導き連絡ライン止め
弁を有する連絡ラインを有し、この連絡ライン止め弁は
前記差圧計の差圧が設定値以上となった場合に開動作す
る遠隔操作弁であることを特徴とする請求項1記載の制
御棒駆動水圧系設備。
6. Instead of the cooling water stop valve being a remotely operated valve, the cooling water stop valve has a communication line for guiding the cooling water to the condensate storage tank, the communication line having a communication line stop valve, the communication line stop valve having the connection line stop valve. The control rod drive hydraulic system facility according to claim 1, wherein the remote control valve is opened when the differential pressure of the pressure gauge exceeds a set value.
JP5126877A 1993-05-28 1993-05-28 Hydraulic system for driving control rod Pending JPH06337295A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP5126877A JPH06337295A (en) 1993-05-28 1993-05-28 Hydraulic system for driving control rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP5126877A JPH06337295A (en) 1993-05-28 1993-05-28 Hydraulic system for driving control rod

Publications (1)

Publication Number Publication Date
JPH06337295A true JPH06337295A (en) 1994-12-06

Family

ID=14946063

Family Applications (1)

Application Number Title Priority Date Filing Date
JP5126877A Pending JPH06337295A (en) 1993-05-28 1993-05-28 Hydraulic system for driving control rod

Country Status (1)

Country Link
JP (1) JPH06337295A (en)

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