JPS61167894A - Overhauling inspection system of hydraulic pressure control unit in nuclear reactor control rod driving hydraulic pressure system - Google Patents
Overhauling inspection system of hydraulic pressure control unit in nuclear reactor control rod driving hydraulic pressure systemInfo
- Publication number
- JPS61167894A JPS61167894A JP60007698A JP769885A JPS61167894A JP S61167894 A JPS61167894 A JP S61167894A JP 60007698 A JP60007698 A JP 60007698A JP 769885 A JP769885 A JP 769885A JP S61167894 A JPS61167894 A JP S61167894A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- control unit
- rod drive
- reactor
- hydraulic pressure
- 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.)
- Granted
Links
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
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、原子炉制御棒駆動水圧系における水圧制御ユ
ニットの分解点検システム、さらに詳細には、沸騰水型
原子炉におけるこの種システムの改良に関するものであ
る。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to an overhaul system for a hydraulic control unit in a nuclear reactor control rod drive hydraulic system, and more particularly to an improvement of this type of system in a boiling water nuclear reactor. It is something.
本発明の説明に先立ち、従来型（沸騰水型）原子炉制御
棒駆動水圧系の全体的な配管系統を第４図にもとづいて
説明する。Prior to explaining the present invention, the overall piping system of a conventional (boiling water type) nuclear reactor control rod drive hydraulic system will be explained based on FIG.
第４図において、１は復水貯蔵タンク、２は制御棒駆動
系主配管、３はスクラム供給水系配管、４は駆動水系配
管、５は冷却水系配管、６は排出水配管、７は制御棒駆
動水ポンプ、８は駆動水フィルタ、９は流量ｉｌｌ整弁
、ｌＯおよび１１は圧力調整弁、１２は制御棒駆動機構
（ＣＲＤ）を示し、ＣＲＤ１２には、第４図に符号１３
で示す水圧制御ユニツ） （ＨＣＵ）を介して高圧水が
供給され、制御棒の挿入・引抜がおこなわれる。In Figure 4, 1 is a condensate storage tank, 2 is a control rod drive system main pipe, 3 is a scram supply water system pipe, 4 is a drive water system pipe, 5 is a cooling water system pipe, 6 is a discharge water pipe, and 7 is a control rod 8 is a driving water pump, 8 is a driving water filter, 9 is a flow rate adjustment valve, 10 and 11 are pressure adjustment valves, 12 is a control rod drive mechanism (CRD), and the CRD 12 has a reference numeral 13 in FIG.
High-pressure water is supplied through the water pressure control unit (HCU) shown in Figure 2, and the control rods are inserted and withdrawn.
第５図は第４図に示すＨＣＵ１３の外観図、第６図は第
５図に示すＨＣＵ１３の配管系統説明図で、第５図およ
び第６図において、１４はスクラムアキュムレータ、１
５は窒素容器、１６ないし１８は計装ユニット、１９は
入口スクラム弁、２０は出口スクラム弁、２１および２
２はスクラムパイロット弁、２３および２４は切換弁、
２５および２６は流量調兼付切換弁、２７ないし２９は
隔離弁、３０はドレン弁を示している。5 is an external view of the HCU 13 shown in FIG. 4, and FIG. 6 is an explanatory diagram of the piping system of the HCU 13 shown in FIG.
5 is a nitrogen container, 16 to 18 are instrumentation units, 19 is an inlet scram valve, 20 is an outlet scram valve, 21 and 2
2 is a scram pilot valve, 23 and 24 are switching valves,
Reference numerals 25 and 26 indicate flow control and switching valves, 27 to 29 isolation valves, and 30 a drain valve.
上記したＨＣＵ１３は、原子炉内におけるＣＲＤ１２の
位置決めをおこなう、いわゆる制御棒駆動系の一部を構
成し、ＨＣＵ１３の機能は、通常運転時における制御棒
（ＣＲ）の挿入・引抜と、原子炉緊急停止（スクラム）
時におけるＣＲの急速挿入とに大別することができる。The HCU 13 described above constitutes a part of the so-called control rod drive system that positions the CRD 12 in the reactor, and the functions of the HCU 13 are the insertion and withdrawal of control rods (CR) during normal operation and the Stop (scrum)
It can be broadly divided into rapid insertion of CR at times.
原子炉通常運転時にあっては、制御棒手動操作系からの
電気信号にもとづき、制御棒駆動系内で制御された高圧
水をＣＢＤ１２に導き、ＣＢの挿入・引抜をおこなって
炉内を安定させるとともに、ＣＲＤ１２の冷却をも同時
におこなう。During normal reactor operation, high-pressure water controlled within the control rod drive system is guided to the CBD 12 based on electrical signals from the control rod manual operation system, and the CB is inserted and withdrawn to stabilize the inside of the reactor. At the same time, the CRD 12 is also cooled at the same time.
一方、スクラム時にあっては、原子炉保護系からの電気
信号にもとづき、入口・出ロ両スクラム弁１９および２
０を急速に開弁させることにより、アキュムレータ１４
に貯えられている高圧水をＣＲＤ１２の下部室に導き、
ＣＲを急速挿入して原子炉の運転を停止させる。On the other hand, during scram, both the inlet and outlet scram valves 19 and 2 are activated based on electrical signals from the reactor protection system.
By rapidly opening the valve 0, the accumulator 14
The high pressure water stored in is led to the lower chamber of CRD12,
Rapidly insert CR to stop reactor operation.
従来型（沸騰水盤）原子炉制御棒駆動水圧系の働きは以
上のごときであるが、現在稼動しているＢＷＲ１１００
ＭＷｅプラントには、１８５基のＣ几Ｄ１２およびＨＣ
Ｕ１３が設置されておシ、そのうち、２０％にあたる約
４０基のＨＣＵ１３が一定期間内に分解点検されるもの
であって、この分解点検作業は、成る一定の間隔を存し
て順次交替的におこなわれる。The function of the conventional (boiling water basin) reactor control rod drive hydraulic system is as described above, and the BWR1100 currently in operation
The MWe plant has 185 C tanks D12 and HC
Approximately 40 HCU13s, or 20% of the U13s, are to be overhauled and inspected within a certain period of time. It is carried out.
しかして、上記したＨＣＵ１３の分解点検作業は、原子
炉の安全をつかさどる制御棒駆動系の性質上、短期間の
うちに完了することが望ましいが、従来にあっては、Ｈ
ＣＵ１３を１基ずつ順に分解点検するようにしているた
め、作業完了までに比較的長期間を必要としていた。However, due to the nature of the control rod drive system that controls reactor safety, it is desirable to complete the above-mentioned overhaul of the HCU 13 within a short period of time.
Since each CU13 was disassembled and inspected one by one, it took a relatively long time to complete the work.
本発明は、以上の点を考慮してなされたものであって、
その目的とするところは、沸騰水型原子炉の安全をつか
さどる制御棒駆動系、すなわち複数基からなるＩＣＵの
分解点検作業を短期間のうちに完了することのできる、
改良された原子炉制御棒駆動水圧系におけるＨＣＵの分
解点検システムを提供しようとするものである。The present invention has been made in consideration of the above points, and includes:
The purpose of this is to enable the overhaul of the control rod drive system, which is responsible for the safety of boiling water reactors, or the ICU, which is made up of multiple units, to be completed in a short period of time.
The present invention aims to provide an improved HCU overhaul system in a nuclear reactor control rod drive hydraulic system.
上記目的を達成するため、本発明は、炉心に配設されて
いる複数本の原子炉制御棒を、各制御棒に対応して配設
された制御棒駆動機構により＃！抜操作する原子炉制御
棒の駆動水圧系において、上記各制御棒駆動機構に高圧
水を供給する主水圧制御ユニットから独立して、複数個
の制御棒駆動水分岐通路を有する測水圧制御ユニットを
設け、かつ上記各制御棒駆動機構に接続されている主水
圧制御ユニットの交替的分解点検に際し、複数基の主水
圧制御ユニットを一括同時的に遮断して副木圧制御ユニ
ットに切り換えることにより、分解点検に付されている
複数基の主水圧制御ユニットに対応して、それぞれの系
の原子炉制御棒を常駆動操作のために待機せしめること
を特徴とするものである。In order to achieve the above object, the present invention drives a plurality of reactor control rods disposed in a reactor core by a control rod drive mechanism disposed corresponding to each control rod. In the drive water pressure system for the reactor control rods to be removed, a water pressure control unit having a plurality of control rod drive water branch passages is installed independently of the main water pressure control unit that supplies high pressure water to each of the control rod drive mechanisms. When the main water pressure control units installed and connected to each of the control rod drive mechanisms are periodically overhauled, multiple main water pressure control units are simultaneously shut off and switched to the splint pressure control unit. This system is characterized in that the reactor control rods of each system are kept on standby for constant operation in correspondence with a plurality of main hydraulic control units that are being inspected for overhaul.
以下、本発明を、第１図ないし第３図の一実施例にもと
づいて説明すると、第１図は本発明システムを採用した
原子炉制御棒駆動水圧系の全体的な配管系統説明図、第
２図は本発明において要部となる水圧制御ユニットの配
管系統説明図で、第１図において、第４図に示す従来型
原子炉制御棒駆動水圧系の配管系統と同一符号は同一部
分、すなわち１は復水貯蔵タンク、２Ｆｉ制御棒駆動系
主配管、３はスクラム供給水系配管、４は駆動水系配管
、５は冷却水系配管、６は排出水配管、７は制御棒駆動
水ポンプ、８は駆動水フィルタ、９は流量＠整弁、１０
および１１は圧力調整弁、１２はＣＲＤ、１３はＨＣＵ
を示し、ＣＲＤ１２には、従来と同様、ＨＣＵ１３を介
して高圧水が供給され、ＣＲの挿入・引抜がおこなわれ
る。３１は第２図に示すように、既述したＨＣＵ （主
ＨＣＵ）１３と同様に構成された副ＨＣＵを示し、この
副ＨＣＵ３１は、第１図からも明らかなように、主ＨＣ
Ｕ１３から独立して設けられているものであって、後述
する主ＨＣＵ１３の分解点検に際し、複数基の主ＨＣＵ
１３を一括同時的に遮断して副ＨＣＵ３ｘｉＣ切り換え
る。しかして、副ＨＣＵ３１の制御棒挿入側配管３２に
は、制御棒駆動水供給ヘッダ３３が接続されており、こ
のヘッダ３３には、制御棒挿入側配管３２から複数基（
たとえば２０基）のＣＲＤ１２，１２・・・の下部室に
高圧水を分配供給する制御棒挿入側分配配管３４゜３４
・・・が接続されている。また、副ＨＣＵ３１の制御棒
引抜側配管３５には、制御棒駆動水排出へラダ３６が接
続されており、このヘッダ３６には、複数基のＣＲＤ１
２，１２・・・の上部室から排出された高圧水を合流さ
せて制御棒引抜側配管３５に流す制御棒挿入側分配配管
３４．３４・・パと同数の制御棒引抜側集合配管３７．
３７・・・が接続されている。３８は各制御棒挿入側分
配配管３４．３４・・・の途中に接続したセレクタ電磁
弁、３９は各制御棒引抜側集合配管３７．３７・・・の
途中に接続したセレクタ電磁弁を示し、上記したセレク
タ電磁弁３８．３８・・・および３９．３９・・・は、
それぞれ中央制御室４０からの電気信号４工および４２
により遠隔的に開閉操作される。第１図中、４３はＣ几
Ｄ１２，１２・・・の制御棒挿入側ハイベント弁、４４
はＣＲＤ１２，１２・・・の制御棒引抜側ハイベント弁
、４５は制御棒挿入側分配配管３４．３４・・・に取シ
付けたワンタッチカップリング、４６は制御棒引抜側集
合配管３７．３７・・・に取シ付けたワンタッチカップ
リング、４７は制御棒挿入側ハイベント弁４３．４３・
・・を接続した配管に取り付けたワンタッチカップリン
グ、４８は制御棒引抜側ハイベント弁４４．４４・・・
を接続した配管に取り付けたワンタッチカップリングで
、各ワンタッチカップリング４５．４５・・・と４７，
４７・・・とは、フレキシブルチューブ４９によって接
続されている。また、他のワンタッチカップリング４６
゜４６・・・、！：４８．４８・・・とは、フレキシブ
ルチューブ５０によって接続されている。Hereinafter, the present invention will be explained based on one embodiment of FIGS. 1 to 3. FIG. FIG. 2 is an explanatory diagram of the piping system of the hydraulic control unit, which is the main part of the present invention. In FIG. 1, the same reference numerals as the piping system of the conventional reactor control rod drive hydraulic system shown in FIG. 1 is a condensate storage tank, 2 is a control rod drive system main pipe, 3 is a scram supply water system pipe, 4 is a drive water system pipe, 5 is a cooling water system pipe, 6 is a discharge water pipe, 7 is a control rod drive water pump, 8 is a Driving water filter, 9 is flow rate @ valve control, 10
and 11 is a pressure regulating valve, 12 is CRD, and 13 is HCU
As in the conventional case, high-pressure water is supplied to the CRD 12 via the HCU 13, and the CR is inserted and withdrawn. As shown in FIG. 2, reference numeral 31 indicates a sub-HCU configured similarly to the previously described HCU (main HCU) 13, and as is clear from FIG.
It is provided independently from U13, and when disassembling and inspecting the main HCU 13 described later, multiple main HCUs
13 all at once and switch to the secondary HCU3xiC. A control rod drive water supply header 33 is connected to the control rod insertion side piping 32 of the sub-HCU 31, and a plurality of water supply headers (
For example, control rod insertion side distribution piping 34°34 that distributes and supplies high-pressure water to the lower chambers of CRD12, 12... (for example, 20 units)
...is connected. In addition, a ladder 36 is connected to the control rod extraction side piping 35 of the sub-HCU 31 to discharge control rod driving water, and this header 36 has a plurality of CRD 1
The control rod insertion side distribution piping 34.2, 12... which merges the high pressure water discharged from the upper chambers and flows into the control rod withdrawal side piping 35. The control rod extraction side collective piping 37.34 has the same number as 34.
37... are connected. 38 indicates a selector solenoid valve connected in the middle of each control rod insertion side distribution pipe 34, 34..., 39 indicates a selector solenoid valve connected in the middle of each control rod withdrawal side collection pipe 37, 37..., The selector solenoid valves 38, 38... and 39, 39... mentioned above are
Electrical signals 4 and 42 from the central control room 40, respectively
It is opened and closed remotely. In Fig. 1, 43 is a high vent valve on the control rod insertion side of C box D12, 12, 44
is the high vent valve on the control rod withdrawal side of CRD12, 12..., 45 is the one-touch coupling attached to the control rod insertion side distribution piping 34, 34..., 46 is the control rod withdrawal side collective piping 37, 37 The one-touch coupling attached to ..., 47 is the control rod insertion side high vent valve 43.43.
One-touch coupling attached to the pipe connected to..., 48 is the high vent valve on the control rod withdrawal side 44.44...
Each one-touch coupling 45.45... and 47,
47... are connected by a flexible tube 49. Also, other one-touch couplings 46
゜46...! :48, 48... are connected by a flexible tube 50.
第３図は本発明システムの動作系を詳細に説明する配管
系統説明図を示し、ここで、原子炉運転を停止して原子
炉施設の定期検査をおこなうにあたシ、上記検査と並行
して主ＨＣＵの分解点検作業をおこなう場合の手順につ
き、第３図にもとづいて説明する。Figure 3 shows an explanatory diagram of the piping system to explain in detail the operating system of the system of the present invention. The procedure for disassembling and inspecting the main HCU will be explained based on FIG.
なお、現在稼動している沸騰水型原子炉にあっては、常
設のＨＣＵが炉心を中心に２つのエリアに分れて設置さ
れているため、本発明システムを上記したと同タイプの
沸騰水型原子炉に採用する場合は、第１図ないし第３図
に符号１３で示す主ＨＣＵと符号３１で示す副ＨＣＵと
は、それぞれ各エリアに１基ずつ設置される。In addition, in currently operating boiling water reactors, the permanently installed HCU is divided into two areas around the reactor core. When the system is adopted in a type nuclear reactor, one main HCU indicated by reference numeral 13 and one sub-HCU indicated by reference numeral 31 in FIGS. 1 to 3 are installed in each area.
第３図において、原子炉運転を停止して主ＨＣＵ１３．
１３・・・の分解点検をおこなうに際しては、分解点検
を目的とする複数基（たとえば２０基）の主ＨＣＵ１３
，１３・・・に対応するＣＲＤ１２゜１２・・・の制御
棒挿入側ハイベント弁４３．４３・・・と、副ＨＣＵ３
１の制御棒挿入側分配配管３４゜３４・・・とをそれぞ
れワンタッチカップリング４５゜４７およびフレキシブ
ルチューブ４９を介して接続する。また、上記複数基の
主ＨＣＵ１３，１３・・・に対応するＣＲＤ１２，１２
・・・の制御棒引抜側ハイベント弁４４，４４・・・と
、副ＨＣＵ３１の制御棒引抜側集合配管３７．３７・・
・とをそれぞれワンタッチカップリング４６．４８およ
びフレキシブルチューブ５０を介して接続する。そして
、その後、分解点検を目的とする上記複数基の主ＨＣＵ
１３．１３・・・の各隔離弁２７．２７・・・と２８゜
２８・・・とを閉じ、副ＨＣＵ３１，３１・・・の隔離
弁２７と２８とを開けば、上記分解点検を目的とする複
数基の主ＨＣＵ１３．１３・・・に対応して、それぞれ
の系ＣＲを常駆動操作のために待機させることができる
ものであって、分解点検に付されている複数基の主ＨＣ
Ｕ１３，１３・・・中、成る特定の主ＨＣＵ１３に対応
するＣＲＤの駆動操作を必要とする場合は、中央制御室
４０からの電気信号４１および４２により、特定の制御
棒挿入側分配配管３４と制御棒引抜側集合配管３７とに
接続されているセレクタ電磁弁３８と３９とが開き、ア
キュムレータ１４に貯えられている高圧水を目的とする
ＣＲＤ１２の下部室に導くことができるものであって、
なおアキュムレータ１４からＣＲＤ１２の下部室に注入
される高圧水の流速は約１５ｔ／ｍｉｎ、その水圧は約
１８Ｋｆ／ｃＷ＆” ｇｌｉ度でよい。In FIG. 3, the reactor operation is stopped and the main HCU 13.
13..., the main HCU 13 of multiple units (for example, 20 units) for the purpose of overhaul and inspection.
, 13..., the control rod insertion side high vent valves 43, 43... of the CRD12゜12..., and the sub HCU3
1 control rod insertion side distribution pipes 34, 34, . . . are connected via one-touch couplings 45, 47 and flexible tubes 49, respectively. In addition, the CRDs 12, 12 corresponding to the plurality of main HCUs 13, 13...
... control rod withdrawal side high vent valves 44, 44... and control rod withdrawal side collective piping 37, 37 of the sub HCU 31...
and are connected via one-touch couplings 46 and 48 and flexible tubes 50, respectively. After that, the main HCUs of the plurality of units for the purpose of overhaul and inspection are
13. If the isolation valves 27, 27... and 28° 28... of 13.13... are closed and the isolation valves 27 and 28 of the sub-HCU 31, 31... are opened, the above-mentioned disassembly and inspection will be carried out. It is possible to keep each system CR on standby for constant operation corresponding to multiple main HCUs 13, 13...
When it is necessary to drive the CRD corresponding to a specific main HCU 13 consisting of U13, 13..., the electrical signals 41 and 42 from the central control room 40 are used to drive the specific control rod insertion side distribution piping 34. The selector solenoid valves 38 and 39 connected to the control rod withdrawal side collection pipe 37 are opened, and the high-pressure water stored in the accumulator 14 can be guided to the lower chamber of the CRD 12 for which it is intended.
Note that the flow rate of the high-pressure water injected from the accumulator 14 into the lower chamber of the CRD 12 may be about 15 t/min, and the water pressure may be about 18 Kf/cW&'' gli degree.
本発明は以上のごときであり、本発明によれば、沸騰水
型原子炉制御棒駆動水圧系における多数基の主ＨＣＵ１
３，１３・・・を交替的に分解点検するに際し、複数基
（たとえば２０基）の主ＨＣＵ１３．１３・・・を−揺
回時的に遮断して副ＨＣＵ３１に切り換えることにより
、分解点検に付されている上記複数基の主ＨＣ！Ｕ１３
，１３・・・に対応して、それぞれの系のＣＲを常駆動
操作のために待機せしめ、上記複数基の主ＨＣＵ１３，
１３・・・を同時に分解点検することができるものであ
って、この種作業に必要とする期間を従来よりも大幅に
短縮することができる。The present invention is as described above, and according to the present invention, a large number of main HCUs 1 in a boiling water reactor control rod drive hydraulic system
3, 13, etc., by periodically shutting off the main HCUs 13, 13, etc. during rotation and switching to the sub HCU 31. The main HC of the above multiple groups attached! U13
, 13..., the CR of each system is put on standby for constant operation, and the plurality of main HCUs 13,
13... can be disassembled and inspected at the same time, and the period required for this type of work can be significantly shortened compared to the conventional method.
また、図示実施例に示すように、副ＨＣＵ３１の制御棒
駆動水供給へラダ３３に接続されている複数本の制御棒
挿入側分配配管３４．３４・・・の途中にセレクタ電磁
弁３８．３８・・・を接続し、かつ制御棒駆動水排出ヘ
ッダ３６に接続されている複数本の制御棒引抜側集合配
管３７．３７・・・の途中にセレクタ電磁弁３９．３９
・・・を接続し、上記セレクタ電磁弁３８．３８・・・
と３９，３９・・・との開閉動作を、それぞれ中央制御
室４０からの電気信号４１および４２によって集中的に
遠隔操作するようにすれば、分解点検に付されている複
数基の主ＨＣＵ１３，１３・・・に対応する全てのＣＲ
Ｄ１２．１２・・・を一括的に監視することができ至便
である。In addition, as shown in the illustrated embodiment, selector solenoid valves 38, 38 are installed in the middle of a plurality of control rod insertion side distribution pipes 34, 34, which are connected to the ladder 33 to supply control rod drive water to the sub-HCU 31. A selector solenoid valve 39, 39 is installed in the middle of a plurality of control rod withdrawal side collection pipes 37, 37, which are connected to the control rod drive water discharge header 36.
Connect the above selector solenoid valve 38, 38...
If the opening/closing operations of the main HCUs 13, 39, 39, . . . All CRs corresponding to 13...
D12.12... can be monitored all at once, which is very convenient.
本発明は以上のごときでめ９、図示実施例の説明からも
明らかなように、本発明によれば、沸騰水型原子炉の安
全をつかさどる制御棒駆動系、すなわち複数基からなる
ＨＣＵの分解点検作業を短期間のうちに完了することの
できる、改良された原子炉制御棒駆動水圧系におけるＨ
ＣＵの分解点検システムを提供することができる。According to the present invention, as is clear from the explanation of the illustrated embodiments, the control rod drive system, which is in charge of the safety of boiling water reactors, that is, the HCU consisting of multiple units, can be disassembled. H in an improved reactor control rod drive hydraulic system that allows inspection work to be completed in a short period of time.
A CU overhaul/inspection system can be provided.
第１図ないし第３図は本発明の一実施例を示し、第１図
は本発明システムを採用した原子炉制御棒駆動水圧系の
全体的な配管系統説明図、第２図は本発明システムにお
いて要部となる水圧制御ユニットの配管系統説明図、第
３図は本発明システムの動作系を詳細に説明する配管系
統説明図、第４図は従来型原子炉制御棒駆動水圧系の全
体的な配管系統説明図、第５図は第４図に示す制御棒駆
動水圧系に組込まれている水圧制御ユニットの外観図、
第６図は第５図に示す水圧制御ユニットの配管系統説明
図である。Figures 1 to 3 show one embodiment of the present invention, Figure 1 is an explanatory diagram of the overall piping system of the reactor control rod drive hydraulic system employing the system of the present invention, and Figure 2 is the system of the present invention. Figure 3 is an explanatory diagram of the piping system of the hydraulic control unit, which is the main part of the system, Figure 3 is an explanatory diagram of the piping system explaining in detail the operating system of the system of the present invention, and Figure 4 is an overall diagram of the conventional reactor control rod drive hydraulic system. Fig. 5 is an external view of the hydraulic control unit incorporated in the control rod drive hydraulic system shown in Fig. 4;
FIG. 6 is an explanatory diagram of the piping system of the water pressure control unit shown in FIG. 5.
Claims (1)
制御棒に対応して配設された制御棒駆動機構により挿抜
操作する原子炉制御棒の駆動水圧系において、上記各制
御棒駆動機構に高圧水を供給する主水圧制御ユニツトか
ら独立して、複数個の制御棒駆動水分岐通路を有する副
水圧制御ユニツトを設け、かつ上記各制御棒駆動機構に
接続されている主水圧制御ユニツトの交替的分解点検に
際し、複数基の主水圧制御ユニツトを一括同時的に遮断
して副水圧制御ユニツトに切り換えることにより、分解
点検に付されている複数基の主水圧制御ユニツトに対応
して、それぞれの系の原子炉制御棒を常駆動操作のため
に待機せしめることを特徴とする原子炉制御棒駆動水圧
系における水圧制御ユニツトの分解点検システム。1. In the reactor control rod drive hydraulic system in which multiple reactor control rods arranged in the reactor core are inserted and removed by control rod drive mechanisms arranged corresponding to each control rod, each of the above-mentioned controls An auxiliary water pressure control unit having a plurality of control rod drive water branch passages is provided independently of the main water pressure control unit that supplies high pressure water to the rod drive mechanism, and the main water pressure control unit is connected to each of the control rod drive mechanisms. When overhauling and inspecting control units, multiple main water pressure control units can be simultaneously shut off and switched to the auxiliary water pressure control unit to accommodate multiple main water pressure control units undergoing overhaul. 1. An overhaul and inspection system for a hydraulic control unit in a reactor control rod drive hydraulic system, characterized in that the reactor control rods of each system are kept on standby for constant operation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60007698A JPH0631772B2 (en) | 1985-01-19 | 1985-01-19 | Reactor control rod drive hydraulic system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60007698A JPH0631772B2 (en) | 1985-01-19 | 1985-01-19 | Reactor control rod drive hydraulic system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61167894A true JPS61167894A (en) | 1986-07-29 |
| JPH0631772B2 JPH0631772B2 (en) | 1994-04-27 |
Family
ID=11672986
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60007698A Expired - Lifetime JPH0631772B2 (en) | 1985-01-19 | 1985-01-19 | Reactor control rod drive hydraulic system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0631772B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007033384A (en) * | 2005-07-29 | 2007-02-08 | Toshiba Corp | Cooling water supply method and cooling water supply system for control rod driving mechanism |
| JP2018205221A (en) * | 2017-06-08 | 2018-12-27 | 日立Ｇｅニュークリア・エナジー株式会社 | Control rod drive system and inspection method for control rod drive system |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60228994A (en) * | 1984-04-27 | 1985-11-14 | 株式会社東芝 | Drive in case of routine inspection of control rod driving mechanism and driving method thereof |
-
1985
- 1985-01-19 JP JP60007698A patent/JPH0631772B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60228994A (en) * | 1984-04-27 | 1985-11-14 | 株式会社東芝 | Drive in case of routine inspection of control rod driving mechanism and driving method thereof |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007033384A (en) * | 2005-07-29 | 2007-02-08 | Toshiba Corp | Cooling water supply method and cooling water supply system for control rod driving mechanism |
| JP2018205221A (en) * | 2017-06-08 | 2018-12-27 | 日立Ｇｅニュークリア・エナジー株式会社 | Control rod drive system and inspection method for control rod drive system |
| GB2564748A (en) * | 2017-06-08 | 2019-01-23 | Hitachi Ge Nuclear Energy Ltd | Control rod drive system and inspection method of control rod drive system |
| US10957458B2 (en) | 2017-06-08 | 2021-03-23 | Hitachi-Ge Nuclear Energy, Ltd. | Movable standby hydraulic control unit that is usable during a control rod drive system inspection to temporarily replace any one of several hydraulic control units |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0631772B2 (en) | 1994-04-27 |
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