JP2534546Y2 - Operation control device for pressurized water reactor - Google Patents
Operation control device for pressurized water reactorInfo
- Publication number
- JP2534546Y2 JP2534546Y2 JP1991026377U JP2637791U JP2534546Y2 JP 2534546 Y2 JP2534546 Y2 JP 2534546Y2 JP 1991026377 U JP1991026377 U JP 1991026377U JP 2637791 U JP2637791 U JP 2637791U JP 2534546 Y2 JP2534546 Y2 JP 2534546Y2
- Authority
- JP
- Japan
- Prior art keywords
- pressurizer
- pressure
- coolant
- filling
- spray
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【０００１】[0001]
【産業上の利用分野】本考案は、加圧水型原子炉の運転
制御装置の改良に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an improved operation control device for a pressurized water reactor.
【０００２】[0002]
【従来の技術】図２は、加圧水型原子炉（ＰＷＲ）の基
本概念図を示す。2. Description of the Related Art FIG. 2 shows a basic concept of a pressurized water reactor (PWR).
【０００３】図中の１は、原子炉容器（Ｒ／Ｖ）であ
る。この原子炉容器１には、この原子炉容器１内に所定
圧力に加圧された冷却材（Ｈ2 Ｏを用いる）を送り込む
冷却材循環ポンプ２が接続されている。前記原子炉容器
１内に送り込まれたＨ2 Ｏは、核反応により加熱され
る。前記原子炉容器１には、配管３を介して蒸気発生器
４が接続されている。前記Ｈ2 Ｏは、蒸気発生器４の伝
熱管内流体として胴側流体である給水（２次冷却材とも
いう）と熱交換し、これを沸騰せしめる。前記蒸気発生
器４からの蒸気はタ−ビンの駆動に用いられる。また、
低温になったＨ2 Ｏは、冷却材循環ポンプ２へ戻り、こ
のサイクルを繰り返す。[0003] Reference numeral 1 in the figure denotes a reactor vessel (R / V). The reactor vessel 1 is connected to a coolant circulating pump 2 for feeding a coolant (using H 2 O) pressurized to a predetermined pressure into the reactor vessel 1. The H 2 O sent into the reactor vessel 1 is heated by a nuclear reaction. A steam generator 4 is connected to the reactor vessel 1 via a pipe 3. The H 2 O exchanges heat with feed water (also referred to as a secondary coolant), which is a body-side fluid, as a fluid in the heat transfer tube of the steam generator 4, and causes it to boil. The steam from the steam generator 4 is used for driving a turbine. Also,
The cooled H 2 O returns to the coolant circulation pump 2 and repeats this cycle.
【０００４】前記配管３には冷却材の圧力を所定の範囲
に保つ加圧器５が設けられており、この加圧器５の内部
下方にはヒ−タ（図示せず）を有し、上方には低温冷却
材のスプレイノズル（図示せず）を有している。ここ
で、圧力を上げるときは、ヒ−タに通電し、加圧器５内
の水を蒸発させ、これにより蒸気相の圧力を増大させて
全体の圧力を上げることにより行う。逆に、圧力を下げ
るときは、上部のノズルから低温冷却材（Ｈ2 Ｏ）をス
プレイして蒸気相の温度を下げ、これにより蒸気相の圧
力を下げて全体の圧力を下げることにより行う。なお、
図中の６は加圧器スプレイラインである。The pipe 3 is provided with a pressurizer 5 for keeping the pressure of the coolant within a predetermined range. The pressurizer 5 has a heater (not shown) below the inside thereof and a heater above the pressurizer 5. Has a low temperature coolant spray nozzle (not shown). Here, when increasing the pressure, the heater is energized to evaporate water in the pressurizer 5, thereby increasing the pressure of the vapor phase to increase the overall pressure. Conversely, when lowering the pressure, a low-temperature coolant (H 2 O) is sprayed from the upper nozzle to lower the temperature of the vapor phase, thereby lowering the pressure of the vapor phase to lower the overall pressure. In addition,
6 in the figure is a pressurizer spray line.
【０００５】[0005]
【考案が解決しようとする課題】ところで、加圧器５の
満水走査は、従来、運転者による手動操作であった。従
って、満水時に加圧器５の圧力が急上昇したり、その後
加圧器５の圧力が急降下する恐れがあり、充填，抽出に
よる加圧器の圧力制御が円滑にできないという問題点が
あった。By the way, the water filling scan of the pressurizer 5 has conventionally been a manual operation by a driver. Therefore, there is a possibility that the pressure of the pressurizer 5 may rise suddenly when the water is full, and then the pressure of the pressurizer 5 may drop sharply, and there is a problem that the pressure control of the pressurizer by filling and extracting cannot be performed smoothly.
【０００６】本考案は上記事情を考慮してなされたもの
で、加圧器の満水操作を自動化することにより、満水時
に加圧器の圧力が急上昇したり、加圧器の圧力が急降下
するのを回避し、充填，抽出による加圧器の圧力制御を
円滑になし得る加圧水型原子炉の運転制御装置を提供す
ることを目的とする。The present invention has been made in view of the above circumstances, and by automating the operation of filling the pressurizer with water, it is possible to prevent the pressure of the pressurizer from rapidly rising or dropping when the water is full. Another object of the present invention is to provide a pressurized water reactor operation control device capable of smoothly controlling the pressure of a pressurizer by filling and extracting.
【０００７】[0007]
【課題を解決するための手段】本考案は、冷却材循環ポ
ンプ，原子炉容器及び蒸気発生器を配管を用いてル−プ
状に連絡させ、前記原子炉容器と蒸気発生器とを連絡す
る配管に加圧器を設け、更に前記冷却材循環ポンプ，原
子炉容器間を連絡する配管と前記加圧器間に加圧器スプ
レイラインを設けた加圧水型原子炉の運転を制御する装
置において、前記加圧器内の上方に設けられ低温冷却材
を供給するスプレイノズルと、このスプレイノズルに供
給する低温冷却材の供給流量を調節するためのスプレイ
弁と、前記加圧器内の下方に設けられたヒ−タと、前記
加圧器の圧力を測定するための圧力測定手段と、前記配
管に設けられ充填ポンプを有する冷却材充填ラインと、
前記配管に設けられ冷却材を取り出す抽出ラインとを備
え、充填量を増し抽出量を一定または減少することによ
り加圧器内の水位を上昇させて水位上昇に伴う圧力上昇
を前記ヒータおよび前記スプレイ弁により圧力制御を行
い、また水位が上昇して前記スプレイノズルに近くな
り、スプレイ効果がなくなって前記圧力測定手段での圧
力上昇を検知した時は前記冷却材充填ラインおよび抽出
ラインの制御に切替えて充填量から抽出量を引いた冷却
材量を制御することにより圧力制御を行うことを特徴と
する加圧水型原子炉の運転制御装置である。According to the present invention, a coolant circulation pump, a reactor vessel and a steam generator are connected in a loop using piping, and the reactor vessel and the steam generator are connected. An apparatus for controlling the operation of a pressurized water reactor in which a pressurizer is provided in a pipe, and a pressurizer spray line is provided between the coolant circulation pump and a pipe communicating between a reactor vessel and the pressurizer, wherein the pressurizer is provided. a spray nozzle for supplying a low-temperature coolant is provided above the inner, subjected to the spray nozzle
Spray for adjusting the supply flow rate of the low-temperature coolant to be supplied
Valves and the provided below the pressurizer heat - data and said
Pressure measuring means for measuring the pressure of the pressurizer , a coolant filling line having a filling pump provided in the pipe,
An extraction line provided in the pipe to take out a coolant; increasing the filling level and increasing or decreasing the extraction level to raise the water level in the pressurizer and increase the pressure with the water level rise
The pressure is controlled by the heater and the spray valve , and the water level rises and closes to the spray nozzle.
The spray effect disappears and the pressure
When a power increase is detected, the coolant filling line and extraction
An operation control apparatus for a pressurized water reactor, wherein pressure control is performed by controlling a coolant amount obtained by subtracting an extraction amount from a filling amount by switching to line control .
【０００８】[0008]
【作用】本考案において、加圧器水位上昇による圧力制
御を、前記加圧器内の下方に配置したヒータおよび前記
加圧器内の上方に配置されたスプレイノズルに供給する
低温冷却材を調節するためのスプレイ弁により行う。ま
た、気相消滅中、ヒ−タをＯＮとし加圧器を飽和状態に
維持し、不如意な外乱に対し、加圧器の圧力を急降下を
防止する。更に、加圧器のスプレイ効果がなくなること
による圧力上昇を前記圧力測定手段で検知した時は圧力
制御を前記ヒータおよびスプレイ弁から充填・抽出によ
る圧力制御に切替える。但し、この時点では、まだ加圧
器内に熱気が残っており、加圧壁の残留蒸気により過熱
されるのを防ぐため、スプレイ弁は微開のまま開として
おく。更に、ＲＣＳ（Ｒｅａｃｔｏｒ Ｃｏｏｌｉｎｇ
Ｓｙｓｔｅｍ）の圧力安定後、スプレイ弁開度を徐々
に加圧器圧力の突変を防止する。According to the present invention , the pressure control based on the rise in the water level of the pressurizer is performed by the heater disposed below the pressurizer and the pressure control.
Supply to the spray nozzle located above in the pressurizer
This is done with a spray valve to regulate the low temperature coolant. Further, during the gas phase disappearance, the heater is turned on to keep the pressurizer in a saturated state, thereby preventing the pressure of the pressurizer from suddenly dropping against an unexpected disturbance. Furthermore, the spray effect of the pressurizer is lost
When the pressure increase due to the pressure is detected by the pressure measuring means, the pressure control is switched from the heater and the spray valve to the pressure control by filling and extracting. However, at this time, there remains a thermal gas still in the pressurizer, superheated by the residual steam in the pressurizing pressure wall
The spray valve should be left open slightly to prevent this from happening. Furthermore, RCS (Reactor Cooling)
After the pressure of the system is stabilized, the spray valve opening is gradually prevented to prevent sudden change of the pressure of the pressurizer.
【０００９】[0009]
【実施例】図１は、本考案の一実施例に係る加圧水型原
子炉の運転制御装置の全体構成図である。なお、図２と
同部材は同符号を付して説明を省略する。FIG. 1 is an overall configuration diagram of an operation control device of a pressurized water reactor according to an embodiment of the present invention. The same members as those in FIG. 2 are denoted by the same reference numerals, and description thereof will be omitted.
【００１０】図中の11は、加圧器５の内部下方に設けら
れたヒ−タである。また、前記加圧器５の上方には、低
温冷却材のスプレイノズル12が設けられている。更に、
前記加圧器５には、水位計13が設けられている。Reference numeral 11 in the figure denotes a heater provided below the inside of the pressurizer 5. A spray nozzle 12 for a low-temperature coolant is provided above the pressurizer 5. Furthermore,
The pressurizer 5 is provided with a water level gauge 13.
【００１１】前記加圧器５に至る前記配管３には、充填
ポンプ（図示せず）や充填流量制御弁14を介在させた冷
却材充填ライン15が接続されている。また、前記配管３
には、抽出水圧力制御弁16等を介在させた冷却材を取り
出す抽出ライン17が接続されている。なお、図中の18
ａ，18ｂは流量計、19は充填流量制御器である。A coolant filling line 15 having a filling pump (not shown) and a filling flow rate control valve 14 interposed is connected to the pipe 3 leading to the pressurizer 5. In addition, the pipe 3
Is connected to an extraction line 17 for extracting a coolant through an extraction water pressure control valve 16 and the like. Note that 18 in the figure
a and 18b are flow meters, and 19 is a filling flow rate controller.
【００１２】前記加圧器５の上部には、加圧器内の圧力
を測定する圧力計20が設けられている。また、前記スプ
レイノズル12には、加圧器スプレイ弁21，リミッタ22，
圧力制御器23などが接続されている。こうした構成の運
転制御装置の動作は、次のように行う。A pressure gauge 20 for measuring the pressure in the pressurizer is provided above the pressurizer 5. Further, the spray nozzle 12 has a pressurizer spray valve 21, a limiter 22,
A pressure controller 23 and the like are connected. The operation of the operation control device having such a configuration is performed as follows.
【００１３】まず、加圧器内の水位を上昇させるため充
填流量制御弁14の開度を上昇し、充填流量を増加すると
ともに、抽出量を一定または減にする。これにより、差
引き系内量が増えて水位が上昇する。この際、加圧器５
のヒ−タ11をＯＮとして加圧器５内を飽和状態に保つ。
水位が上昇すると、蒸気相の容積が減り（圧縮され）て
圧力が上昇するので、圧力制御器23が動作し、圧力を抑
制する様にスプレイノズル12が開いて低温冷却材をスプ
レイする。First, in order to raise the water level in the pressurizer, the opening of the filling flow rate control valve 14 is raised to increase the filling flow rate and to make the extraction amount constant or to decrease. As a result, the amount in the subtraction system increases and the water level rises. At this time, the pressurizer 5
The heater 11 is turned ON to keep the inside of the pressurizer 5 in a saturated state.
When the water level rises, the volume of the vapor phase is reduced (compressed) and the pressure rises, so that the pressure controller 23 operates, and the spray nozzle 12 opens to spray the low-temperature coolant so as to suppress the pressure.
【００１４】また、水位が上昇していき、加圧器水位が
スプレイノズル12近くなると、スプレイされた低温冷却
材と蒸気との接触が十分でなくなるので、スプレイして
もなかなか圧力が低下せず、制御に使用できない。従っ
て、この時点で圧力制御は、冷却材量（＝充填量−抽出
量）の制御で行われる。但し、スプレイを完全に止める
と、残存蒸気が加圧器壁の残留熱により加熱（飽和温度
以上になると）され、不具合を生ずるので、一定少量の
冷却材をスプレイ続ける。Further, when the water level rises and the water level of the pressurizer becomes closer to the spray nozzle 12, the contact between the sprayed low-temperature coolant and the steam becomes insufficient, so that even if the spray is performed, the pressure does not readily decrease. Cannot be used for control. Therefore, at this point, the pressure control is performed by controlling the coolant amount (= filled amount−extracted amount). However, if the spray is completely stopped, the residual steam is heated by the residual heat of the pressurizer wall (when the temperature exceeds the saturation temperature), causing a problem.
【００１５】このように、上記実施例に係る運転制御装
置によれば、前記加圧器５の上方に設けられ低温冷却材
を供給するスプレイノズル12と、前記加圧器５に設けら
れたヒ−タ11と、前記配管に設けられ充填ポンプを有す
る冷却材充填ライン15と、前記配管に設けられ冷却材を
取り出す抽出ライン17等を備え、充填量を増し抽出量を
一定または減少することにより加圧器５内の水位を上昇
させて圧力制御を行い、また水位が上昇して前記スプレ
イノズル12に近くなった時は充填量から抽出量を引いた
冷却材量を制御することにより、圧力制御を行う自動化
が可能となる。従って、運転者の負担は大幅に軽くなる
とともに、運転者によるＲＣＳ圧力急降下という誤操作
を回避できる。これに対し、従来の場合は、加圧器気相
消滅操作は極めて難しい操作で、運転者がつきっきりに
なるため、運転者の負担が非常に大きかった。As described above, according to the operation control device of the above embodiment, the spray nozzle 12 provided above the pressurizer 5 for supplying the low-temperature coolant, and the heater provided in the pressurizer 5 11, a coolant filling line 15 having a filling pump provided in the pipe, and an extraction line 17 provided in the pipe to take out a coolant, etc., and the pressurizer is provided by increasing the filling amount and keeping the extraction amount constant or decreasing. Pressure control is performed by raising the water level in 5 and when the water level rises and approaches the spray nozzle 12, pressure control is performed by controlling the coolant amount obtained by subtracting the extraction amount from the filling amount. Automation becomes possible. Therefore, the burden on the driver is greatly reduced, and the erroneous operation of the RCS pressure drop by the driver can be avoided. On the other hand, in the conventional case, the operation of extinguishing the gas phase of the pressurizer is an extremely difficult operation, and the driver becomes sharp, so that the burden on the driver is very large.
【００１６】[0016]
【考案の効果】以上詳述した如く本考案によれば、加圧
器の満水操作を自動化することにより、満水時に加圧器
の圧力が急上昇したり、加圧器の圧力が急降下するのを
回避し、充填，抽出による加圧器の圧力制御を円滑にな
し得る加圧水型原子炉の運転制御装置を提供できる。According to the present invention, as described in detail above, by automating the water filling operation of the pressurizer, it is possible to prevent the pressure of the pressurizer from rapidly rising or dropping when the water is full, An operation control device for a pressurized water reactor that can smoothly control the pressure of a pressurizer by filling and extraction can be provided.
【図１】本考案の一実施例に係る加圧水型原子炉の運転
制御装置の説明図。FIG. 1 is an explanatory diagram of an operation control device of a pressurized water reactor according to an embodiment of the present invention.
【図２】加圧原子炉の原理説明図。FIG. 2 is a diagram illustrating the principle of a pressurized nuclear reactor.
１…原子炉容器、２…冷却材循環ポンプ、４…蒸発発生
器、５…加圧器、６…加圧器スプレイライン、11…ヒ−
タ、12…スプレイノズル、13…水位計、14…充填流量制
御器、15…冷却剤充填ライン、17…抽出ライン、18a ，
18ｂ…流量計、19…充填流量制御器、20…圧力制御器、
21…加圧器スプレイ弁。DESCRIPTION OF SYMBOLS 1 ... Reactor vessel, 2 ... Coolant circulation pump, 4 ... Evaporation generator, 5 ... Pressurizer, 6 ... Pressurizer spray line, 11 ... Heat
, 12 ... spray nozzle, 13 ... water level gauge, 14 ... filling flow rate controller, 15 ... coolant filling line, 17 ... extraction line, 18a,
18b: flow meter, 19: filling flow rate controller, 20: pressure controller,
21 ... Pressurizer spray valve.
Claims (1)
発生器を配管を用いてル−プ状に連絡させ、前記原子炉
容器と蒸気発生器とを連絡する配管に加圧器を設け、更
に前記冷却材循環ポンプ，原子炉容器間を連絡する配管
と前記加圧器間に加圧器スプレイラインを設けた加圧水
型原子炉の運転を制御する装置において、 前記加圧器内の上方に設けられ低温冷却材を供給するス
プレイノズルと、このスプレイノズルに供給する低温冷
却材の供給流量を調節するためのスプレイ弁と、前記加
圧器内の下方に設けられたヒ−タと、前記加圧器の圧力
を測定するための圧力測定手段と、前記配管に設けられ
充填ポンプを有する冷却材充填ラインと、前記配管に設
けられ冷却材を取り出す抽出ラインとを備え、充填量を
増し抽出量を一定または減少することにより加圧器内の
水位を上昇させて水位上昇に伴う圧力上昇を前記ヒータ
および前記スプレイ弁により圧力制御を行い、また水位
が上昇して前記スプレイノズルに近くなり、スプレイ効
果がなくなって前記圧力測定手段での圧力上昇を検知し
た時は前記冷却材充填ラインおよび抽出ラインの制御に
切替えて充填量から抽出量を引いた冷却材量を制御する
ことにより圧力制御を行うことを特徴とする加圧水型原
子炉の運転制御装置。A coolant circulation pump, a reactor vessel and a steam generator are connected in a loop using piping, and a pressurizer is provided in a pipe connecting the reactor vessel and the steam generator. an apparatus for controlling the operation of the coolant circulation pump, pressurized water reactor the pressurizer spray line is provided between the pipe and the pressurizer to contact between the reactor vessel, cryogenic cooling provided above the the pressurizer Spray nozzle for supplying material and low-temperature cooling for supplying to this spray nozzle
And spray valve for regulating the supply flow rate of却材, heat the provided below the pressurizer - motor and the pressure of the pressurizer
Pressure measuring means for measuring the temperature, a coolant filling line provided with a filling pump provided in the pipe, and an extraction line provided in the pipe to take out the coolant, increasing the filling amount and keeping the extraction amount constant or decreasing the heater raises the water level in the pressurizer pressure rise due to the water level rises by
And wherein performs pressure control by spray valve, also Ri that closer to the spray nozzle the water level rises, the spray efficiency
The result is lost and the pressure rise in the pressure measuring means is detected.
Control the coolant filling line and extraction line
An operation control device for a pressurized water reactor, wherein pressure control is performed by switching and controlling a coolant amount obtained by subtracting an extraction amount from a filling amount.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1991026377U JP2534546Y2 (en) | 1991-04-18 | 1991-04-18 | Operation control device for pressurized water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1991026377U JP2534546Y2 (en) | 1991-04-18 | 1991-04-18 | Operation control device for pressurized water reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH04122398U JPH04122398U (en) | 1992-11-02 |
| JP2534546Y2 true JP2534546Y2 (en) | 1997-04-30 |
Family
ID=31910882
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1991026377U Expired - Lifetime JP2534546Y2 (en) | 1991-04-18 | 1991-04-18 | Operation control device for pressurized water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2534546Y2 (en) |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0631810B2 (en) * | 1986-07-02 | 1994-04-27 | 三菱重工業株式会社 | Reactor shutdown operation control method |
-
1991
- 1991-04-18 JP JP1991026377U patent/JP2534546Y2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH04122398U (en) | 1992-11-02 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 Effective date: 19961203 |
|
| EXPY | Cancellation because of completion of term |