JPH07229995A - Pressure controller at the cold hot condition of reactor pressure vessel - Google Patents
Pressure controller at the cold hot condition of reactor pressure vesselInfo
- Publication number
- JPH07229995A JPH07229995A JP6020249A JP2024994A JPH07229995A JP H07229995 A JPH07229995 A JP H07229995A JP 6020249 A JP6020249 A JP 6020249A JP 2024994 A JP2024994 A JP 2024994A JP H07229995 A JPH07229995 A JP H07229995A
- Authority
- JP
- Japan
- Prior art keywords
- pressure
- reactor
- water
- pressure vessel
- detector
- 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
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
-
- 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
【0001】[0001]
【産業上の利用分野】本発明は、原子力発電所における
定期検査時の原子炉圧力容器水圧試験に係り、特に原子
炉圧力容器の冷温状態時における水位及び圧力の任意目
標値に自動制御する原子炉圧力容器冷温時圧力制御装置
に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a water pressure test of a reactor pressure vessel at the time of periodic inspection in a nuclear power plant, and particularly to an atom for automatically controlling an arbitrary target value of water level and pressure in a cold state of the reactor pressure vessel. The present invention relates to a pressure control device for a cold state of a furnace pressure vessel.
【0002】[0002]
【従来の技術】原子力発電所については、法律により定
期的に発電所を停止して、その工作物を点検すること
(一般に定期検査と称している)が、また機器によって
は、監督官庁の立会検査を受けることが義務付けられて
いる。この定期検査期間中に実施する原子炉圧力容器内
部の構成要素(燃料、制御棒、炉内核計装、気水分離
器、蒸気乾燥器等)の交換を含む点検作業終了、及び原
子炉圧力容器の付随機器(制御棒駆動機構、再循環ポン
プ、配管弁類等)の交換を含む点検作業終了に伴い復旧
健全度合確認を実施する。2. Description of the Related Art For nuclear power plants, it is legally necessary to regularly shut down the power plant and inspect the work (generally called periodic inspection). It is obligatory to have an inspection. Completion of inspection work including replacement of components inside the reactor pressure vessel (fuel, control rods, nuclear instrumentation, steam separator, steam dryer, etc.) to be carried out during this periodic inspection period, and reactor pressure vessel Confirmation of the soundness of restoration will be carried out at the completion of inspection work including replacement of auxiliary equipment (control rod drive mechanism, recirculation pump, piping valves, etc.).
【0003】このためには、原子炉圧力容器の冷温状態
において原子炉圧力容器に水張りを行ないポンプにより
加圧し、例えば図2の工程図に示すような一次系点検
A、漏洩検査B、制御棒駆動系の機能検査C,E、ポン
プ試験D、使用前検査F等の作業を行なう。To this end, the reactor pressure vessel is filled with water in a cold state of the reactor pressure vessel and pressurized by a pump. For example, a primary system inspection A, a leakage inspection B, and a control rod as shown in the process diagram of FIG. Work such as drive system functional inspections C and E, pump test D, and pre-use inspection F are performed.
【0004】この時の原子炉圧力容器に対する水圧試験
のための加圧及び圧力制御は、制御棒駆動水系ポンプに
より、原子炉圧力容器内に制御棒駆動系の冷却水ライン
を通じて水を供給することと、原子炉圧力容器から原子
炉浄化系のブローラインを通じて水を系外に排出するこ
とにより行なわれる。なお、この圧力制御は、水の供給
量と排出量のバランスを運転員が原子炉圧力を監視しな
がら調整していた。Pressurization and pressure control for the water pressure test on the reactor pressure vessel at this time are performed by supplying water into the reactor pressure vessel through a cooling water line of the control rod drive system by a control rod drive water system pump. Then, the water is discharged from the reactor pressure vessel to the outside of the system through the blow line of the reactor cleaning system. In this pressure control, the operator adjusted the balance between the water supply amount and the water discharge amount while monitoring the reactor pressure.
【0005】また、作業工程の一次系点検Aと漏洩検査
Bに引き続いて、この原子炉圧力容器における原子炉圧
力(運転圧力)を利用して、制御棒駆動系の機能検査C
(全制御棒スクラム試験)も実施する。さらに近年にお
いては、原子炉圧力容器の周辺機器(例えば原子炉再循
環ポンプ部品、モータ)の改造や更新、及び同制御系の
取替え等に伴う早期健全性確認(不具合部の早期摘出と
是正を含む)の観点からの原子炉圧力容器の冷温加圧
(運転圧力)下における試運転Dの実施等がある。In addition, following the primary inspection A and the leakage inspection B of the work process, the functional inspection C of the control rod drive system is carried out using the reactor pressure (operating pressure) in this reactor pressure vessel.
(All control rod scrum test) is also conducted. Furthermore, in recent years, early soundness confirmation (removal and early correction of faulty parts is required due to remodeling and renewal of peripheral equipment of reactor pressure vessels (for example, reactor recirculation pump parts, motors) and replacement of the control system. From the viewpoint of (including), there is a trial operation D under cold pressurization (operating pressure) of the reactor pressure vessel.
【0006】なお、以上の確認及び試験の夫々は、定期
検査工事の工程上クリティカルとなるもので、官庁検査
対象の検査は、それに先立つ社内検査が実施されるた
め、原子炉圧力容器等を上記一連のプラント状態に整定
する機会は複数回発生する。Each of the above confirmations and tests is critical in the process of the periodic inspection work, and the inspection of the government inspection target is an in-house inspection prior to the inspection. The opportunity to settle into a series of plant conditions occurs multiple times.
【0007】[0007]
【発明が解決しようとする課題】原子炉が冷温状態にお
ける原子炉圧力容器の圧力を所定の圧力に整定する作業
については、原子炉圧力容器の大きさや作業内容から大
掛かりなものとなり、さらに、その進行には上記した試
験及び検査と関連する設備系統の運転管理も当然必要と
なる。The work of stabilizing the pressure of the reactor pressure vessel in a cold state of the reactor at a predetermined pressure is a major task depending on the size of the reactor pressure vessel and the work content. Of course, operation management of the equipment system related to the above-mentioned tests and inspections is also necessary for the progress.
【0008】さらに、この原子炉圧力容器の試験等の進
行中に不意に発生する警報に対処しつつ、大勢の人が待
機していることを気に掛けながら原子炉圧力容器の圧力
等、プラントの状態整定を計画工程通りに準備し、かつ
運営管理を行なう運転員にかかる負担は非常に大きくな
る支障があった。Furthermore, while coping with an alarm generated abruptly during the test of the reactor pressure vessel, etc., the plant pressure, etc. There was a problem that the burden on the operator who prepares the state settling according to the planned process and manages the operation becomes very large.
【0009】本発明の目的とするところは、冷温状態に
おける原子炉圧力容器の圧力と水位信号等から原子炉圧
力容器内の圧力制御を自動的に実施する原子炉圧力容器
冷温時圧力制御装置を提供することにある。An object of the present invention is to provide a cold pressure control device for a reactor pressure vessel, which automatically controls the pressure in the reactor pressure vessel from the pressure of the reactor pressure vessel and the water level signal in a cold state. To provide.
【0010】[0010]
【課題を解決するための手段】上記目的を達成するため
本発明に係る原子炉圧力容器冷温時圧力制御装置は、制
御棒駆動系に設けた給水を制御する駆動水ポンプと駆動
水調整弁及び駆動水流量検出器と炉水浄化系に設けた排
水を制御する排水弁及び排水流量検出器と原子炉圧力容
器に設けた水位検出器と排気弁及び圧力検出器を備えた
原子炉において、前記駆動水流量検出器及び排水流量検
出器と圧力検出器及び水位検出器からの夫々流量と圧力
及び水位の信号を入力すると共に予め備えたプログラム
に沿って前記駆動水調整弁及び排水弁と排気弁並びに駆
動水ポンプの夫々に制御信号を出力して原子炉圧力容器
の圧力制御をする圧力制御器を設けたことを特徴とす
る。In order to achieve the above object, a reactor pressure vessel cold temperature pressure control device according to the present invention comprises a drive water pump and a drive water regulating valve provided in a control rod drive system for controlling water supply. In a reactor equipped with a driving water flow rate detector and a drainage valve for controlling drainage provided in a reactor water purification system, a drainage flow rate detector, a water level detector provided in a reactor pressure vessel, an exhaust valve, and a pressure detector, Driving water flow rate detector, drainage flow rate detector, pressure detector, and water level signal from the water level detector are input respectively, and the driving water regulating valve, drainage valve, and exhaust valve are installed in accordance with a preset program. Further, a pressure controller for outputting a control signal to each of the driving water pumps to control the pressure of the reactor pressure vessel is provided.
【0011】[0011]
【作用】プラント冷温状態時で原子炉圧力容器への加圧
及び定圧力制御を運転員の指示により自動的に実施す
る。 (1) 昇圧準備として原子炉圧力容器へ水張を行う。圧力
制御器は水位検出器からの水位信号と、予め設定した目
標とを比較しながら、駆動水調整弁により給水量を制御
する。水位が目標に到達すると、それまで開放していた
排気弁を閉止させて原子炉圧力容器の昇圧を開始する。[Operation] Pressurization of the reactor pressure vessel and constant pressure control are automatically performed according to the operator's instruction in the cold state of the plant. (1) Water pressure is applied to the reactor pressure vessel in preparation for pressurization. The pressure controller controls the amount of water supplied by the drive water adjusting valve while comparing the water level signal from the water level detector with a preset target. When the water level reaches the target, the exhaust valve that had been open until then is closed and the pressure increase in the reactor pressure vessel is started.
【0012】(2) 圧力制御器は、昇圧開始と共に圧力検
出器らの圧力上昇率を監視評価し、原子炉圧力容器への
給、排水量を駆動水調整弁と排水弁を制御して、予め設
定したプログラムに沿った昇圧及び定圧力を保持する。 (3) 昇降圧中また定圧力制御中は、排水制御弁が予定外
に閉止した場合等で原子炉圧力容器の圧力が予め設定し
た圧力以上に上昇すると、圧力検出器の圧力信号により
圧力制御器は給水を自動停止させる。(2) The pressure controller monitors and evaluates the rate of pressure increase from the pressure detectors at the start of pressurization, and controls the drive water regulating valve and the drain valve to control the supply and drainage amount to the reactor pressure vessel in advance. Hold the boost and constant pressure according to the set program. (3) During boosting / boosting or constant pressure control, if the pressure in the reactor pressure vessel rises above a preset pressure, such as when the drainage control valve is closed unexpectedly, pressure control is performed with the pressure signal from the pressure detector. The water supply automatically stops the water supply.
【0013】[0013]
【実施例】本発明の一実施例について図面を参照して説
明する。図1の構成図に示すように、原子炉圧力容器1
の底部には、炉心2内に配置された炉心2の核反応度を
調節する制御棒3の位置を変化(挿入、引抜き)させる
ための制御棒駆動機構4が据付けられており、制御棒駆
動系28の駆動水ポンプ5により、制御棒駆動機構4の駆
動及び冷却の目的で復水貯蔵タンク6から水が駆動水調
整弁7を経由して供給される。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described with reference to the drawings. As shown in the configuration diagram of FIG. 1, a reactor pressure vessel 1
A control rod drive mechanism 4 for changing (inserting, withdrawing) the position of the control rod 3 for adjusting the nuclear reactivity of the core 2 arranged in the core 2 is installed at the bottom of the control rod drive. The drive water pump 5 of the system 28 supplies water from the condensate storage tank 6 via the drive water regulating valve 7 for the purpose of driving and cooling the control rod drive mechanism 4.
【0014】制御棒駆動機構4に供給された水は、制御
棒駆動機構4を通過した後に原子炉圧力容器1内に放出
される。なお、原子炉圧力容器1においては、この制御
棒駆動機構4から放出された水を原子炉圧力容器1の外
部へ排水しないと、原子炉圧力容器1内の水位は上昇す
る。また、仮に原子炉圧力容器1内の空気の排気がされ
ないと、前記の水位上昇は原子炉圧力容器1内の空間を
押し縮めて、原子炉圧力容器1内の圧力を上昇させるこ
とになる。The water supplied to the control rod drive mechanism 4 is discharged into the reactor pressure vessel 1 after passing through the control rod drive mechanism 4. In the reactor pressure vessel 1, unless the water discharged from the control rod drive mechanism 4 is discharged to the outside of the reactor pressure vessel 1, the water level in the reactor pressure vessel 1 rises. Further, if the air in the reactor pressure vessel 1 is not exhausted, the rise in the water level causes the space in the reactor pressure vessel 1 to be compressed and the pressure in the reactor pressure vessel 1 to rise.
【0015】原子炉圧力容器1に付属している再循環系
26から分岐し、他端を給水配管27に接続された炉水浄化
系23には、原子炉圧力容器1における余剰水を復水貯蔵
タンク6へ排出する排水系24が排水弁8を介して配設さ
れており、原子炉圧力容器1の頂部には圧力上昇を防止
するための排気系25が排気弁9を介して設けられてい
る。Recirculation system attached to the reactor pressure vessel 1
In the reactor water purification system 23, which is branched from 26 and the other end of which is connected to the water supply pipe 27, a drainage system 24 for discharging excess water in the reactor pressure vessel 1 to the condensate storage tank 6 is provided via a drain valve 8. An exhaust system 25 for preventing pressure rise is provided at the top of the reactor pressure vessel 1 via an exhaust valve 9.
【0016】さらに、制御棒駆動系28の前記駆動水調整
弁7を有する流路には駆動水流量検出器10が、炉水浄化
系23の排水弁8を有する流路には排水流量検出器11が、
また原子炉圧力容器1には圧力検出器12と水位検出器13
が設けられている。各検出器10,11,12,13 から出力され
る駆動水流量信号14と排水流量信号15、圧力信号16及び
水位信号17は、予め設定された昇圧、定圧、圧力降下等
をプログラムに沿って処理をするプログラム制御器で電
算機化されている圧力制御器18に入力される。Further, a drive water flow rate detector 10 is provided in the flow path of the control rod drive system 28 having the drive water adjusting valve 7, and a drain water flow rate detector is provided in the flow path of the reactor water purification system 23 having the drain valve 8. 11 is,
The reactor pressure vessel 1 has a pressure detector 12 and a water level detector 13
Is provided. The drive water flow rate signal 14, drainage flow rate signal 15, pressure signal 16 and water level signal 17 output from each of the detectors 10, 11, 12, 13 are preset pressure increase, constant pressure, pressure drop, etc. according to the program. It is input to the pressure controller 18 which is a computerized program controller for processing.
【0017】この圧力制御器18から前記駆動水ポンプ5
には停止信号19が、駆動水調整弁7には駆動水制御信号
20が、また排水弁8には排水制御信号21が、さらに排気
弁9には排気制御信号22が各々出力されるように構成さ
れている。From this pressure controller 18 to the drive water pump 5
Is a stop signal 19 and the drive water adjusting valve 7 is a drive water control signal.
20 and the drainage control signal 21 to the drainage valve 8 and the exhaustion control signal 22 to the exhaust valve 9 respectively.
【0018】次に上記構成による作用について説明す
る。 (1) 原子炉圧力容器1内の昇圧準備は、運転員の確認に
よってプラント全体としての昇圧準備が確認された後
に、圧力制御器18の「昇圧準備モード」を始動させる
と、圧力制御器18は予め設定されたプログラムに沿って
原子炉圧力容器1への給水流量と排水流量が等しくなる
ように駆動水調整弁7及び排水弁8を制御し始める。こ
の流量差が許容範囲内に安定すると、「昇圧準備完了」
として、次の「圧力上昇モード」に移行する。Next, the operation of the above configuration will be described. (1) To prepare for boosting the pressure in the reactor pressure vessel 1, after the operator confirms that boosting for the entire plant has been confirmed, when the “pressurizing preparation mode” of the pressure controller 18 is started, the pressure controller 18 Starts to control the drive water adjusting valve 7 and the drain valve 8 so that the flow rate of water supplied to the reactor pressure vessel 1 becomes equal to the flow rate of drainage in accordance with a preset program. When this flow rate difference stabilizes within the allowable range, "preparation for boosting"
Then, it shifts to the next "pressure increase mode".
【0019】(2) 圧力上昇制御については、圧力制御器
18が「昇圧準備完了」(給水流量=排水流量)、及び水
位信号17が予め定めた目標値で安定していることを条件
として排気弁9に閉止信号22を発する。また、計画昇圧
時間を考慮した経時的圧力変化目標値と、実圧から偏差
を算出して排水制御信号21により、排水弁8への制御を
開始する。(2) For the pressure rise control, the pressure controller
18 is a "pressurization ready" (supply water flow rate = drainage flow rate), and the closing signal 22 is issued to the exhaust valve 9 on condition that the water level signal 17 is stable at a predetermined target value. Further, a deviation is calculated from the target value of pressure change over time in consideration of the planned pressurization time and the actual pressure, and the drainage control signal 21 starts the control to the drainage valve 8.
【0020】排水弁8が開度を減じると排水量が低下
し、原子炉圧力容器1の保有水が増加することにより圧
力が上昇する。なお、経時的に増加するプログラム目標
値は、原子炉圧力容器1への定量注水と、制御される排
水量の差により実圧力として追従される。When the opening of the drain valve 8 is reduced, the amount of drainage decreases, and the water held in the reactor pressure vessel 1 increases, so that the pressure rises. The program target value that increases with time is tracked as an actual pressure due to the difference between the quantitative water injection into the reactor pressure vessel 1 and the controlled discharge amount.
【0021】(3) 圧力の定値制御は、圧力検出器12から
の圧力信号16が定値目標値に到達(定めた許容範囲内に
なる)すると、圧力制御器18は経時的目標値変化を停止
して、排水制御信号21の一定出力を出し続けるため、排
水弁8は制御棒駆動系28からの給水流量と排水流量が等
しくなるような弁開度状態で最終的に安定する。この状
態は、次の圧力目標値への昇圧または「圧力降下モー
ド」が発されるまで維持される。(3) In the constant pressure control of the pressure, when the pressure signal 16 from the pressure detector 12 reaches a constant target value (within a predetermined allowable range), the pressure controller 18 stops changing the target value with time. Then, since the drainage control signal 21 is continuously output at a constant level, the drainage valve 8 is finally stabilized in a valve opening state in which the water supply flow rate from the control rod drive system 28 and the drainage flow rate become equal. This state is maintained until the next pressure increase to the target pressure value or the "pressure decrease mode" is issued.
【0022】(4) 圧力降下制御について、圧力制御器18
における「圧力降下モード」は、計画降圧時間を考慮し
たプログラムで、経時的圧力変化目標値に対して排水弁
8を制御して(昇圧の場合と逆に、排水弁8は開度を増
して排水量を増加する)追従させる。(4) Regarding the pressure drop control, the pressure controller 18
The "pressure drop mode" is a program that considers the planned pressure reduction time, and controls the drainage valve 8 with respect to the target value of pressure change over time (in contrast to the case of boosting, the drainage valve 8 increases the opening degree). Increase the drainage) Follow it.
【0023】(5) 昇圧及び定値圧力制御時の安全確保に
ついては、何らかの原因で排水弁8が計画外で全閉した
場合には原子炉圧力容器1内の保有水が増加することに
より圧力が上昇して、原子炉圧力容器1及び付属設備機
器に過大圧力が加わることが想定される。(5) Regarding ensuring safety during boosting and constant pressure control, if the drain valve 8 is completely closed unplanned for some reason, the pressure in the reactor pressure vessel 1 will increase due to an increase in water retained. It is assumed that the pressure rises and excessive pressure is applied to the reactor pressure vessel 1 and attached equipment.
【0024】しかしながら、原子炉圧力容器1内の圧力
が予め設定した圧力以上となった場合には、圧力制御器
18は駆動水ポンプ5へ停止信号19を出力して、制御棒駆
動系28から原子炉圧力容器1内への給水を停止し、これ
により原子炉圧力容器1に過大圧力が加わることを防止
する。However, when the pressure in the reactor pressure vessel 1 exceeds the preset pressure, the pressure controller
18 outputs a stop signal 19 to the driving water pump 5 to stop the water supply from the control rod drive system 28 into the reactor pressure vessel 1 and thereby prevent an excessive pressure from being applied to the reactor pressure vessel 1. .
【0025】本発明においては、従来は運転員の経験と
勘、及び終始、原子炉圧力容器1の状態を監視すること
により実施していたプラント冷温時の原子炉圧力容器1
における内部圧力の昇降圧、及び定値制御が、自動的に
実施されるので運転員への負担が大幅に軽減される。さ
らに、原子炉圧力容器1への加減圧と定圧力制御が自動
化されて、運転員操作の個人差による影響を受けないの
で、作業の安定性と再現性が正確となり、高い信頼性を
得られる。In the present invention, conventionally, the reactor pressure vessel 1 at the time of the cold temperature of the plant was carried out by monitoring the experience and intuition of the operator and the state of the reactor pressure vessel 1 from beginning to end.
Since the step-up / step-down of the internal pressure and the constant value control are automatically performed, the burden on the operator is greatly reduced. Further, since the pressurization / depressurization and constant pressure control to the reactor pressure vessel 1 are automated and are not affected by individual differences in operator's operation, work stability and reproducibility are accurate, and high reliability is obtained. .
【0026】特に、定期検査時の圧力昇圧点検におい
て、機器手直しが必要となった場合には、原子炉圧力容
器1における「降圧→補修→昇圧→検査→降圧」の作業
が必要となり、冷温状態での圧力制御を実施する頻度が
増加するが、本発明によれば容易に実施できる。In particular, when it is necessary to repair the equipment in the pressure increase inspection during the periodic inspection, the work of "reduction step → repair → step up → inspection → step down" in the reactor pressure vessel 1 is required, and the cold state Although the frequency of performing the pressure control in step 1 increases, the present invention can easily perform the pressure control.
【0027】[0027]
【発明の効果】以上本発明によれば、定期検査時等で実
施する原子炉圧力容器の冷温状態における内部圧力の加
圧、減圧と定圧力制御が、自動的に行われると共に、そ
の圧力制御が正確で作業の信頼性が向上する。さらに、
作業員の負担を大幅に軽減する効果がある。As described above, according to the present invention, the pressurization, depressurization and constant pressure control of the internal pressure in the cold state of the reactor pressure vessel, which is carried out at the time of periodic inspection, etc., are automatically performed and the pressure control is performed. Is accurate and improves work reliability. further,
This has the effect of significantly reducing the burden on workers.
【図1】本発明に係る一実施例の原子炉圧力容器冷温時
圧力制御装置の構成図。FIG. 1 is a configuration diagram of a cold pressure control device for a reactor pressure vessel according to an embodiment of the present invention.
【図2】原子炉圧力容器における加圧試験の工程図。FIG. 2 is a process diagram of a pressure test in a reactor pressure vessel.
1…原子炉圧力容器、2…炉心、3…制御棒、4…制御
棒駆動機構、5…駆動水ポンプ、6…復水貯蔵タンク、
7…駆動水調整弁、8…排水弁、9…排気弁、10…駆動
水流量検出器、11…排水流量検出器、12…圧力検出器、
13…水位検出器、14…駆動水流量信号、15…排水流量信
号、16…圧力信号、17…水位信号、18…圧力制御器、19
…停止信号、20…駆動水制御信号、21…排水制御信号、
22…排気制御信号、23…炉水浄化系、24…排水系、25…
排気系、26…再循環系、27…給水配管、28…制御棒駆動
系。1 ... Reactor pressure vessel, 2 ... Reactor core, 3 ... Control rod, 4 ... Control rod drive mechanism, 5 ... Drive water pump, 6 ... Condensate storage tank,
7 ... Drive water adjusting valve, 8 ... Drain valve, 9 ... Exhaust valve, 10 ... Drive water flow rate detector, 11 ... Drainage flow rate detector, 12 ... Pressure detector,
13 ... water level detector, 14 ... driving water flow rate signal, 15 ... drainage flow rate signal, 16 ... pressure signal, 17 ... water level signal, 18 ... pressure controller, 19
… Stop signal, 20… Drive water control signal, 21… Drainage control signal,
22 ... Exhaust control signal, 23 ... Reactor water purification system, 24 ... Drainage system, 25 ...
Exhaust system, 26 ... Recirculation system, 27 ... Water supply piping, 28 ... Control rod drive system.
Claims (1)
動水ポンプと駆動水調整弁及び駆動水流量検出器と炉水
浄化系に設けた排水を制御する排水弁及び排水流量検出
器と原子炉圧力容器に設けた水位検出器と排気弁及び圧
力検出器を備えた原子炉において、前記駆動水流量検出
器及び排水流量検出器と圧力検出器及び水位検出器から
の夫々流量と圧力及び水位の信号を入力すると共に予め
備えたプログラムに沿って前記駆動水調整弁及び排水弁
と排気弁並びに駆動水ポンプの夫々に制御信号を出力し
て原子炉圧力容器の圧力制御をする圧力制御器を設けた
ことを特徴とする原子炉圧力容器冷温時圧力制御装置。1. A drive water pump, a drive water adjusting valve, a drive water flow rate detector, and a drainage valve and a drainage flow rate detector, which are provided in a control rod drive system, for controlling water supply, and a drainage flow rate detector, which is provided in a reactor water purification system. In a reactor equipped with a water level detector provided in a reactor pressure vessel, an exhaust valve, and a pressure detector, the flow rate and pressure from the driving water flow rate detector, the drainage flow rate detector, the pressure detector, and the water level detector, respectively. A pressure controller for inputting a water level signal and outputting a control signal to each of the drive water regulating valve, the drain valve, the exhaust valve, and the drive water pump according to a program prepared in advance to control the pressure of the reactor pressure vessel. A reactor pressure vessel cold temperature pressure control device characterized by being provided.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP6020249A JPH07229995A (en) | 1994-02-17 | 1994-02-17 | Pressure controller at the cold hot condition of reactor pressure vessel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP6020249A JPH07229995A (en) | 1994-02-17 | 1994-02-17 | Pressure controller at the cold hot condition of reactor pressure vessel |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH07229995A true JPH07229995A (en) | 1995-08-29 |
Family
ID=12021928
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP6020249A Pending JPH07229995A (en) | 1994-02-17 | 1994-02-17 | Pressure controller at the cold hot condition of reactor pressure vessel |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH07229995A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR100942194B1 (en) * | 2007-12-18 | 2010-02-11 | 한전케이피에스 주식회사 | Apparatus for draining of RCS and the method there for |
KR101698344B1 (en) * | 2016-03-11 | 2017-01-20 | 한국수력원자력 주식회사 | A pressurizer intergrated control system of a nuclear generating station |
-
1994
- 1994-02-17 JP JP6020249A patent/JPH07229995A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR100942194B1 (en) * | 2007-12-18 | 2010-02-11 | 한전케이피에스 주식회사 | Apparatus for draining of RCS and the method there for |
KR101698344B1 (en) * | 2016-03-11 | 2017-01-20 | 한국수력원자력 주식회사 | A pressurizer intergrated control system of a nuclear generating station |
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