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JPS6025754B2 - Abnormality diagnosis device for reactor water supply control system - Google Patents
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JPS6025754B2 - Abnormality diagnosis device for reactor water supply control system - Google Patents

Abnormality diagnosis device for reactor water supply control system

Info

Publication number
JPS6025754B2
JPS6025754B2 JP55119283A JP11928380A JPS6025754B2 JP S6025754 B2 JPS6025754 B2 JP S6025754B2 JP 55119283 A JP55119283 A JP 55119283A JP 11928380 A JP11928380 A JP 11928380A JP S6025754 B2 JPS6025754 B2 JP S6025754B2
Authority
JP
Japan
Prior art keywords
signal
abnormality
water level
control system
water supply
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
Application number
JP55119283A
Other languages
Japanese (ja)
Other versions
JPS5744891A (en
Inventor
士郎 大塚
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
Tokyo Shibaura Electric Co Ltd
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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP55119283A priority Critical patent/JPS6025754B2/en
Publication of JPS5744891A publication Critical patent/JPS5744891A/en
Publication of JPS6025754B2 publication Critical patent/JPS6025754B2/en
Expired 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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は沸騰水型原子力発電設備における原子炉給水制
御系全体の異常を診断する装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an apparatus for diagnosing abnormalities in the entire reactor water supply control system in boiling water nuclear power generation equipment.

従来のこの種の給水制御系異常診断装置には■原子炉の
水位が許容変動範囲内にあるか否かによって異常判定を
行なう方式のもの、■給水ポンプ等の給水制御機器の異
常を機器のトリップ信号によって検知し異常判定を行な
う方式のもの、■給水制御装置からの制御信号の喪失(
スケールダウン)を検知し異常判定を行なう方式のもの
等がある。
Conventional equipment for diagnosing abnormalities in water supply control systems of this type includes: ■ one that determines an abnormality based on whether or not the reactor water level is within the permissible fluctuation range; A method that detects and determines an abnormality using a trip signal, ■ Loss of control signal from the water supply control device (
There are methods to detect abnormality (scaling down) and determine abnormality.

しかしながら、上記■の方式のものは給水制御系に異常
が生じた結果としての最終的現象である水位変動から異
常判定を行なうものであるが故に、早期異常診断を行な
い難い欠点がある。
However, since the method (2) above determines an abnormality based on the water level fluctuation, which is the final phenomenon resulting from an abnormality in the water supply control system, it has the disadvantage that early abnormality diagnosis is difficult.

また■,■の方式のものはそれぞれ給水制御機器のトリ
ップ信号が得られる場合や、給水制御装置からの制御信
号が喪失する場合に限り異常判定がなされるだけで、上
記の場合以外の異常事態発生については無能なものとい
える。したがって■,■の方式のものは結局は■の診断
方式を併用する必要があるが既に述べたように■の方式
のものは異常発生の結果として実際に炉水位が変動して
許容変動範囲を逸脱してからでないと異常判定がなされ
ないため、通常はプラントの停止を余儀なくされる。こ
のように従釆の装置には給水制御系の異常を迅速かつ適
確に診断することができず、プラントの稼動率を低下さ
せる欠点があった。本発明はこのような事情を考慮して
なされたものであり、その目的は給水制御系における異
常事態の発生を迅速かつ適確に知ることができ、プラン
トの停止を必要最小限に抑制することが可能でプラント
の稼動率を向上させることのできる原子炉給水制御系の
異常診断装置を提供することである。
In addition, with methods ■ and ■, an abnormality is only determined when a trip signal from the water supply control device is obtained or a control signal from the water supply control device is lost, respectively; It can be said that they are incompetent when it comes to occurrence. Therefore, in the case of methods ■ and ■, it is ultimately necessary to use the diagnostic method of ■, but as mentioned above, in the case of method ■, the reactor water level actually fluctuates as a result of an abnormality, and the allowable fluctuation range Normally, the plant is forced to shut down because it is not determined that there is an abnormality until after the deviation occurs. As described above, the related device has the disadvantage that it cannot quickly and accurately diagnose abnormalities in the water supply control system, which reduces the operating rate of the plant. The present invention has been made in consideration of these circumstances, and its purpose is to quickly and accurately know the occurrence of an abnormal situation in the water supply control system, and to suppress plant shutdowns to the necessary minimum. An object of the present invention is to provide an abnormality diagnosing device for a reactor water supply control system, which is capable of improving the operating rate of a plant.

以下、本発明詳細を図面に示す実施例によって明らかに
する。
Hereinafter, details of the present invention will be clarified with reference to embodiments shown in the drawings.

第1図は本発明の一実施例の構成を示す図、1は原子炉
圧力容器であり、この圧力容器1の中には給水制御系の
ポンプ2によって送り出された水が給水管3を介して供
V給される。圧力容器1によって発生した蒸気は主蒸気
管4を通してタービン5へ送り込まれる。タービン5は
発電機6を回転させ発電を行なう。タービン5で使用さ
れた蒸気は復水器7で復水され、管8を通して給水ポン
プ2に戻される。一方、圧力容器1の中に供給された水
9の水位は水位検出器1川こよって検出され、この検出
された水位信号と端子TOに与えられる水位設定信号と
に応じて給水制御装置11が作動しポンプモータ12を
回転制御する。
FIG. 1 is a diagram showing the configuration of an embodiment of the present invention. 1 is a reactor pressure vessel, into which water pumped by a pump 2 of the water supply control system is fed through a water supply pipe 3. V is supplied. Steam generated by the pressure vessel 1 is sent to the turbine 5 through the main steam pipe 4. The turbine 5 rotates the generator 6 to generate electricity. The steam used in the turbine 5 is condensed in a condenser 7 and returned to the water pump 2 through a pipe 8. On the other hand, the water level of the water 9 supplied into the pressure vessel 1 is detected by the water level detector 1, and the water supply control device 11 is activated according to the detected water level signal and the water level setting signal given to the terminal TO. It operates to control the rotation of the pump motor 12.

ポンプモータ12は前記給水ポンプ2を駆動し圧力容器
1の中へ所定量の給水を行なわせる。第1図中、下方に
示した20は被操作機器(アクチュェータ)を含めた給
水制御系の異常診断を行なう異常診断装置である。
The pump motor 12 drives the water supply pump 2 to supply a predetermined amount of water into the pressure vessel 1. In FIG. 1, reference numeral 20 shown at the bottom is an abnormality diagnosis device for diagnosing abnormalities in a water supply control system including operated equipment (actuators).

この異常診断装置20は、端子TIに到釆する主蒸気流
量信号S1、端子T2に到来する給水流量信号S2、端
子T3に到来する原子炉水位信号S3をそれぞれ個別に
診断する第1、第2、第3の入力信号診断回路301,
302,303と、第1、第2の入力信号診断回路30
1,302を通過した信号SIIとSI2との差に基い
て給水制御系の異常を判定する第1の判定回路40と、
第3の入力信号診断回路303を通過した信号S13を
端子T5に到来する水位設定信号S5と比較し、その差
に基いて給水制御系の異常を判定する第2の判定回路5
0と、前記第1〜第3の入力信号診断回路301〜30
3から送出される異常信号S31,S32,S33およ
び前記第1、第2の判定回路40,50からそれぞれ送
出される異常信号S40,S50の論理和世力信号を得
、この信号を給水制御系異常信号S60として端子T6
から送出する論理回路60とで構成されている。第2図
は上記診断装置20の各部構成をより詳細に示したブロ
ック図である。
This abnormality diagnosis device 20 has first and second signals that individually diagnose the main steam flow rate signal S1 arriving at the terminal TI, the feed water flow rate signal S2 arriving at the terminal T2, and the reactor water level signal S3 arriving at the terminal T3. , third input signal diagnosis circuit 301,
302, 303, and the first and second input signal diagnostic circuits 30
a first determination circuit 40 that determines an abnormality in the water supply control system based on the difference between the signals SII and SI2 that have passed through SII and SI2;
A second determination circuit 5 compares the signal S13 that has passed through the third input signal diagnosis circuit 303 with the water level setting signal S5 that arrives at the terminal T5, and determines whether there is an abnormality in the water supply control system based on the difference.
0, and the first to third input signal diagnostic circuits 301 to 30
3 and abnormal signals S40 and S50 sent from the first and second determination circuits 40 and 50, respectively, and output this signal to the water supply control system. Terminal T6 as abnormal signal S60
It consists of a logic circuit 60 that sends out signals from the FIG. 2 is a block diagram showing the configuration of each part of the diagnostic device 20 in more detail.

第1〜第3の入力信号診断回路301,302,303
は全く同一の構成である。したがって第2図には第1の
入力信号診断回路301についてのみその構成を図示し
、第2、第3の入力信号診断回路302,303につい
ては省略してある。第1の入力信号診断回路301は、
端子TIに到来する入力信号すなわち主蒸気流量信号S
Iを増幅して端子TIIから信号SIIを送出する絶縁
増幅器31と、この増幅器31の出力信号SI1のレベ
ルが予め設定された範囲内にあるか杏かを常時監視し、
設定範囲を逸脱したときに異常信号S21を出力するレ
ベル判定器32と、上記信号SI Iの変イG率が予め
設定された変化率以下であるか否かを常時監視し、設定
範囲を逸脱したときに異常信号S22を出力する信号変
化率判定器33と、上記各判定器32,33の出力信号
S21,S22のオア出力を得、このオア出力信号すな
わち異常信号S31を端子T31から送出するオア回路
34とで構成されている。なお絶縁増幅器31は高入力
インピーダンスを有しており、診断装置20内の電気回
路的故障が入力信号SIの入力点に影響を与えないよう
に配慮されている。同様に第2の入力信号診断装置30
2は端子T2に到来する給水流量信号S2を増幅して信
号S12を得、この信号S12を端子T12から送出す
ると共に、上記信号S12のレベル、変化率が設定範囲
を逸脱したとき異常信号S32を端子T32から送出す
る如く構成されている。
First to third input signal diagnostic circuits 301, 302, 303
have exactly the same configuration. Therefore, in FIG. 2, only the configuration of the first input signal diagnosis circuit 301 is illustrated, and the second and third input signal diagnosis circuits 302 and 303 are omitted. The first input signal diagnosis circuit 301 is
The input signal arriving at terminal TI, that is, the main steam flow rate signal S
an isolation amplifier 31 that amplifies the signal I and sends the signal SII from the terminal TII, and constantly monitors whether the level of the output signal SI1 of the amplifier 31 is within a preset range;
A level determiner 32 that outputs an abnormal signal S21 when the set range is exceeded, and a level determiner 32 that constantly monitors whether the change rate of the signal SI I is below a preset rate of change and detects whether the set range is exceeded. A signal change rate determiner 33 that outputs an abnormal signal S22 when the above-mentioned determination devices 32 and 33 output an OR output of the output signals S21 and S22 is obtained, and this OR output signal, that is, an abnormal signal S31 is sent from a terminal T31. It is composed of an OR circuit 34. Note that the isolation amplifier 31 has a high input impedance, and is designed to prevent an electrical circuit failure within the diagnostic device 20 from affecting the input point of the input signal SI. Similarly, the second input signal diagnostic device 30
2 amplifies the water supply flow rate signal S2 arriving at the terminal T2 to obtain a signal S12, and sends this signal S12 from the terminal T12, and also outputs an abnormality signal S32 when the level and rate of change of the signal S12 deviates from a set range. The signal is configured to be sent out from the terminal T32.

同様に第3の入力信号診断装置303は、端子T3に到
釆する原子炉水位信号S3を増幅して信号S13を得、
この信号S13を端子T13から送出すると共に、上記
信号S13のレベル変化率が設定範囲を逸脱したとき異
常信号S33を端子T33から送出する如く構成されて
いる。
Similarly, the third input signal diagnosis device 303 amplifies the reactor water level signal S3 arriving at the terminal T3 to obtain the signal S13,
This signal S13 is sent out from the terminal T13, and an abnormality signal S33 is sent out from the terminal T33 when the level change rate of the signal S13 deviates from a set range.

第1の判定回路40は、前記第1の入力信号診断回路3
01から送出される増幅された主蒸気流量信号SIIと
、前記第2の入力信号診断回路302から送出される増
幅された給水流量信号S12との差信号S41を得る加
減演算器41と、この加減演算器41からの差信号S4
1の大きさが所定時間以上継続して設定範囲を逸脱した
とき異常信号S42を送出する偏差判定器42と、前記
差信号S41を例えば積分演算することによって原子炉
水位の変動を予測する演算器43と、この演算器43に
て演算された水位変動分を含めた予測水位信号S43が
設定範囲を逸脱したとき異常信号S44を送出する予測
水位判定器44と、上記各判定器42,44から送出さ
れる異常信号のオア出力を得、このオア出力信号を異常
信号S40として外部へ送出するオア回路45とで構成
されている。
The first determination circuit 40 includes the first input signal diagnosis circuit 3
01 and the amplified feedwater flow rate signal S12 sent from the second input signal diagnosis circuit 302; Difference signal S4 from arithmetic unit 41
1 continues for a predetermined time or more and deviates from a set range, a deviation determiner 42 sends out an abnormal signal S42, and a calculator 42 predicts fluctuations in the reactor water level by, for example, performing an integral calculation on the difference signal S41. 43, a predicted water level determiner 44 that sends out an abnormal signal S44 when the predicted water level signal S43 including the water level fluctuation calculated by the calculator 43 deviates from the set range, and from each of the above-mentioned determiners 42, 44. It is comprised of an OR circuit 45 that obtains an OR output of the abnormal signal to be sent out and sends this OR output signal to the outside as an abnormal signal S40.

第2の判定回路5川ま、前記第3の入力信号診断回路3
03から送出される増幅された炉水位信号SI3を端子
T5に到来する水位設定信号S5と比較し、その差信号
S51を得る加減演算器51と、この加減演算器51か
ら出力される差信号S51が所定時間以上継続して設定
範囲を逸脱したとき異常信号S50として外部へ送出す
る水位判定器52とで構成されている。
the second judgment circuit 5; the third input signal diagnosis circuit 3;
An adder/subtractor 51 that compares the amplified reactor water level signal SI3 sent from the terminal T5 with the water level setting signal S5 arriving at the terminal T5 to obtain a difference signal S51, and a difference signal S51 output from the adder/subtractor 51. The water level determiner 52 sends an abnormality signal S50 to the outside when the water level exceeds the set range for a predetermined period of time or more.

論理回路6川こついては第1図に示したとおりのもので
あるからここでは格別に説明はしない。
The details of the logic circuit 6 are as shown in FIG. 1, so no special explanation will be given here.

本異常診断装置は上記の如く構成されているので、端子
T1,T2,T3に到来する主蒸気流量信号SI、給水
流量信号S2、原子炉水位信号S3などの各プロセス信
号のいずれかがレベル的にいるし、は変化率の点で異常
がある場合には、入力信号診断回路301,302,3
03から異常信号S31,S32,S33等が送出され
、これが論理回路60を通して端子T6から給水制御系
異常信号S60として出力される。したがってたとえば
給水制御装置11や各機器に異常が生じそれに伴い上記
各信号S1,S2が異常を呈すれば炉水位が禾だ異常を
呈していない時でも直ちに異常が検知されることになる
。また主蒸気流量信号SIと給水流量信号S2との差信
号そのものが異常な状態を呈する場合、あるいはその蓋
信号から予測される原子炉の予測水位が異常である場合
には、第1の判定回路40から異常信号S40が送出さ
れ、これが論理回路60を通して給水制御系異常信号S
60として出力される。したがってトリツプ信号が送出
されないようなたぐいの異常が給水制御機器等に発生し
、給水制御に支障が生じはじめたような場合においても
、直ちに上記異常が検知されることになる。さらに何ら
かの原因により原子炉水位が設定水位に対し大きくかけ
離れ、その差が設定範囲を越えると、第2の判定回路5
0から異常信号S50が送出され、これが論理回路60
を通して給水制御系異常信号S60として出力される。
したがって、圧力容器1自体に故障が生じたような場合
は勿論、他の異常検知手段に故障が生じたような場合で
も、現実の炉水位に異常が起こればその異常が起った時
点で異常事態発生が検知されることになる。このため極
めて信頼性が高いものとなる。なお本発明は前記実施例
に限定されるものではない。
Since this abnormality diagnosis device is configured as described above, any one of the process signals such as the main steam flow rate signal SI, the feed water flow rate signal S2, and the reactor water level signal S3 that arrive at the terminals T1, T2, and T3 has a certain level. If there is an abnormality in the rate of change, the input signal diagnostic circuits 301, 302, 3
03, abnormal signals S31, S32, S33, etc. are sent out through the logic circuit 60 and output from the terminal T6 as the water supply control system abnormal signal S60. Therefore, for example, if an abnormality occurs in the water supply control device 11 or each device and the signals S1 and S2 become abnormal, the abnormality will be immediately detected even when the reactor water level is not abnormal. Further, if the difference signal between the main steam flow rate signal SI and the feedwater flow rate signal S2 itself is abnormal, or if the predicted reactor water level predicted from the lid signal is abnormal, the first determination circuit 40 sends out an abnormality signal S40, which is transmitted through the logic circuit 60 as a water supply control system abnormality signal S.
It is output as 60. Therefore, even if an abnormality such as a trip signal not being sent occurs in the water supply control equipment or the like and water supply control begins to be affected, the abnormality will be immediately detected. Furthermore, if the reactor water level deviates significantly from the set water level for some reason and the difference exceeds the set range, the second judgment circuit 5
An abnormal signal S50 is sent from the logic circuit 60.
The water supply control system abnormality signal S60 is outputted through the water supply control system abnormality signal S60.
Therefore, not only in the case of a failure in the pressure vessel 1 itself, but also in the case of a failure in other abnormality detection means, if an abnormality occurs in the actual reactor water level, the system will automatically detect the The occurrence of an abnormal situation will be detected. This makes it extremely reliable. Note that the present invention is not limited to the above embodiments.

例えば前記実施例では入力信号診断回路301,302
,303の各出力端にオア回路34を設けると共に、第
1の判定器40の出力端にもオア回路45を設け、これ
らのオア回路出力を論理回路6川こ入力させているが、
論理回路60の論理和(OR)機能を利用することによ
り上記オア回路34,45は省略してもよい。また前記
実施例では論理回路60として論理和のみを得るものを
例示したが、必要ならば一部または全部を論理積回路で
構成してもよい。つまり論理回路60は入力する各異常
信号を所要条件のもとに論理演算することによって給水
制御系異常信号をつくり出すものであればよい。このほ
か本発明の要旨を変えない範囲で種々変形実施可能であ
るのは勿論である。以上説明したように本発明によれば
Z ‘里信号、給水流量信号、炉水位信号などのプロ
セス信号に基いて給水制御系の異常を多面的にかつ総合
的に判定検知しているので、異常事態の発生によって炉
水位が最終的に変動をきたす前の時点で異常事態発生を
迅速かつ適確に知ることができると共に、適切な措置を
早期に施すことが可能となるので、プラント停止を必要
最小限にとどめることができプラント稼動率を向上させ
得る原子炉給水制御系の異常診断装置を提供できる。
For example, in the embodiment, the input signal diagnostic circuits 301 and 302
.
By utilizing the logical sum (OR) function of the logic circuit 60, the OR circuits 34 and 45 may be omitted. Further, in the embodiment described above, the logic circuit 60 is exemplified as one that obtains only a logical sum, but if necessary, part or all of the logic circuit 60 may be constituted by a logical product circuit. In other words, the logic circuit 60 may be one that generates the water supply control system abnormality signal by performing a logical operation on each input abnormality signal under required conditions. It goes without saying that various other modifications can be made without departing from the gist of the present invention. As explained above, according to the present invention, abnormalities in the water supply control system are determined and detected from multiple aspects and comprehensively based on process signals such as the Z'ri signal, the water supply flow rate signal, and the reactor water level signal. This makes it possible to quickly and accurately detect the occurrence of an abnormal situation before the reactor water level ultimately changes due to the occurrence of the situation, and to take appropriate measures at an early stage, making it necessary to shut down the plant. It is possible to provide an abnormality diagnosis device for a reactor feed water control system that can minimize abnormality and improve plant operation rate.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明の一実施例の構成を示す図、第2図は同
実施例の主要部の構成をより詳細に示したブロック図で
ある。 1・・・・・・原子炉圧力容器、2・・・…給水ポンプ
、3・・・・・・給水管、4・・・・・・主蒸気管、5
・・・・・・タービン、6・・・・・・発電機、7・・
・・・・復水器、10・・・・・・水位検出器、20・
・・・・・診断装置。 第1図 図 N 縦
FIG. 1 is a diagram showing the configuration of an embodiment of the present invention, and FIG. 2 is a block diagram showing the configuration of the main part of the embodiment in more detail. 1... Reactor pressure vessel, 2... Water supply pump, 3... Water supply pipe, 4... Main steam pipe, 5
... Turbine, 6... Generator, 7...
... Condenser, 10 ... Water level detector, 20.
...Diagnostic device. Figure 1 Figure N Vertical

Claims (1)

【特許請求の範囲】 1 原子炉水位信号、給水流量信号、主蒸気流量信号の
各信号についてそれぞれ信号レベルおよび信号変化率を
監視し信号レベルが設定範囲を逸脱したとき並びに信号
変化率が設定範囲を逸脱したときに異常信号を送出する
入力信号診断回路群と、前記給水流量信号と主蒸気流量
信号との差信号が所定時間以上継続して設定範囲を逸脱
したとき並びに上記偏差値から原子炉水位の変動を予測
演算しこの予測演算された変動分を含めた水位が設定範
囲を逸脱したときに異常信号を送出する第1の判定回路
と、前記原子炉水位信号と水位設定信号との差信号が所
定時間以上継続して設定範囲を逸脱したとき異常信号を
送出する第2の判定回路と、前記第1、第2の判定回路
および前記入力信号診断回路群からそれぞれ送出される
各異常信号を論理演算して給水制御系異常信号を出力す
る論理和回路とを具備したことを特徴とする原子炉給水
制御系の異常診断装置。 2 第1の判定回路は給水流量信号と主蒸気流量信号と
の差信号を積分演算して原子炉の水位変動を予測する演
算器を備えていることを特徴とする特許請求の範囲第1
項記載の原子炉給水制御系の異常診断装置。
[Claims] 1. Monitor the signal level and signal change rate for each of the reactor water level signal, feed water flow rate signal, and main steam flow rate signal, and detect when the signal level deviates from the set range or when the signal change rate exceeds the set range. an input signal diagnostic circuit group that sends out an abnormal signal when the signal deviates from the set range; a first determination circuit that predicts and calculates water level fluctuations and sends an abnormal signal when the water level including the predicted fluctuations deviates from a set range; and a difference between the reactor water level signal and the water level setting signal. a second determination circuit that sends out an abnormality signal when the signal deviates from a set range for a predetermined period of time or more; and each abnormality signal that is sent out from the first and second determination circuits and the input signal diagnosis circuit group, respectively. What is claimed is: 1. An abnormality diagnosis device for a nuclear reactor feed water control system, comprising: an OR circuit that performs a logical operation on and outputs a water supply control system abnormality signal. 2. Claim 1, characterized in that the first determination circuit is equipped with an arithmetic unit that integrates the difference signal between the feed water flow rate signal and the main steam flow rate signal to predict water level fluctuations in the reactor.
An abnormality diagnosis device for a nuclear reactor feed water control system as described in .
JP55119283A 1980-08-29 1980-08-29 Abnormality diagnosis device for reactor water supply control system Expired JPS6025754B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP55119283A JPS6025754B2 (en) 1980-08-29 1980-08-29 Abnormality diagnosis device for reactor water supply control system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP55119283A JPS6025754B2 (en) 1980-08-29 1980-08-29 Abnormality diagnosis device for reactor water supply control system

Publications (2)

Publication Number Publication Date
JPS5744891A JPS5744891A (en) 1982-03-13
JPS6025754B2 true JPS6025754B2 (en) 1985-06-20

Family

ID=14757548

Family Applications (1)

Application Number Title Priority Date Filing Date
JP55119283A Expired JPS6025754B2 (en) 1980-08-29 1980-08-29 Abnormality diagnosis device for reactor water supply control system

Country Status (1)

Country Link
JP (1) JPS6025754B2 (en)

Also Published As

Publication number Publication date
JPS5744891A (en) 1982-03-13

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