JPS59155790A - Thermal power monitoring device - Google Patents

Thermal power monitoring device

Info

Publication number
JPS59155790A
JPS59155790A JP58029473A JP2947383A JPS59155790A JP S59155790 A JPS59155790 A JP S59155790A JP 58029473 A JP58029473 A JP 58029473A JP 2947383 A JP2947383 A JP 2947383A JP S59155790 A JPS59155790 A JP S59155790A
Authority
JP
Japan
Prior art keywords
flow rate
output
signal processing
reactor
monitoring device
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
JP58029473A
Other languages
Japanese (ja)
Inventor
松宮 章一
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP58029473A priority Critical patent/JPS59155790A/en
Publication of JPS59155790A publication Critical patent/JPS59155790A/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

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  • 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〕 本発明は沸騰水形原子炉の熱出力監視装置に係わり、特
に原子炉緊急停止(スクラム)用の設定値を決定するた
めに使用する再循環水流量信号を処理する回路を改善し
た熱出力監視装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a thermal power monitoring device for a boiling water nuclear reactor, and in particular to a recirculation system used to determine a set point for a reactor emergency shutdown (scram). The present invention relates to a thermal output monitoring device with improved circuitry for processing water flow signals.

〔従来技術〕[Prior art]

沸騰水形原子炉では、熱出力の制御を制御棒の他に再循
環水流量によって行なっておシ、熱出力がある限界をこ
えると緊急停止を行なうように構成されている。これを
行なうために熱出力監視装置が用いられているが、これ
には装置自体のメインテナンス性に問題があυ、その問
題点とこれに対する改善方法の説明が、特願昭56−8
7509に述べられている。第1図は熱出力監視装置の
全体の構成を示す図であり、上述の改善方法の例を示し
たのが第2図である。%願昭56−87509では説明
のため平均出力モニタ回路は51A−Dの4チヤンネル
構成としているが、実際のプラントでは通常51A−F
の6チヤンネル構成としている。
In a boiling water reactor, thermal output is controlled not only by control rods but also by the flow rate of recirculating water, and is configured to perform an emergency shutdown when the thermal output exceeds a certain limit. A thermal output monitoring device is used to do this, but this device has problems with its maintainability, and an explanation of the problem and how to improve it is published in Japanese Patent Application No. 1986-8.
7509. FIG. 1 is a diagram showing the overall configuration of the thermal output monitoring device, and FIG. 2 shows an example of the above-mentioned improvement method. % In Application No. 56-87509, the average output monitor circuit has a 4-channel configuration of 51A-D for explanation purposes, but in actual plants, it is usually configured with 51A-F.
It has a 6-channel configuration.

熱出力監視装置の概要および第1図、第2図の詳細説明
については特願昭56−87509に述べられているの
でここでは第2図について簡単に説明する。
Since the outline of the thermal output monitoring device and the detailed explanation of FIGS. 1 and 2 are described in Japanese Patent Application No. 56-87509, FIG. 2 will be briefly explained here.

第2図に示す回路はたとえば流量信号処理回路6Aのメ
インテナンス、あるいは試験のため、バイパススイッチ
13Aを操作し、内部の出力バッファ62の出力を平均
出力モニタ回路から切り離し、かつ低値選択回路91A
、91C,91Bの出力が、流量信号処理回路6Cから
の信号f6となるよう制御するものである。これにより
熱出力監視装置の全体の信号の流れは第3図に示す通り
となり、流量信号fムは装置内で使用されないため(破
線で示しである)、流量信号処理回路6Aのメインテナ
ンスが容易、かつ安全に行なえることになる。
The circuit shown in FIG. 2 is used, for example, for maintenance or testing of the flow rate signal processing circuit 6A, by operating the bypass switch 13A to disconnect the output of the internal output buffer 62 from the average output monitor circuit, and to cut off the output of the internal output buffer 62 from the average output monitor circuit.
, 91C, and 91B are controlled so that they become the signal f6 from the flow rate signal processing circuit 6C. As a result, the overall signal flow of the thermal output monitoring device becomes as shown in FIG. 3, and since the flow rate signal f is not used within the device (indicated by a broken line), maintenance of the flow rate signal processing circuit 6A is easy. And it can be done safely.

ところでこの場合第3図から明らかなように、平均出力
モニタ回路6A、6C,6Bのスクラム設定値は全て流
量信号fcによシ定まるため、万一、流量測定器3C1
あるいは信号処理回路6Cの内部で故障が発生し、流量
信号fCが通常値よりも異常に大きくなったと仮定する
と、平均出力モニタ回路51A、51C,51Eは原子
炉の異常時に正常なスクラム信号を発することができず
、熱出力監視装置としてはスクラム機能を喪失するとい
りことに表る。実際には流量信号処理回路にはモニタ回
路が設けられておシ、流量信号の異常は直ちに検出され
るためすぐさま対処することは可能である。
By the way, in this case, as is clear from FIG. 3, the scram setting values of the average output monitor circuits 6A, 6C, and 6B are all determined by the flow rate signal fc.
Alternatively, assuming that a failure occurs inside the signal processing circuit 6C and the flow rate signal fC becomes abnormally larger than the normal value, the average output monitor circuits 51A, 51C, and 51E will issue a normal scram signal when the reactor is abnormal. This means that the heat output monitoring device loses its scram function. In reality, the flow rate signal processing circuit is provided with a monitor circuit, and any abnormality in the flow rate signal is immediately detected, so that it is possible to take immediate action.

しかしながら原子炉の安全のためには、メインテナンス
時とはいえ一時的にでも単一故障によシ原子炉のスクラ
ム機能が喪失するようなことがあってはならない。
However, for the safety of a nuclear reactor, even during maintenance, the scram function of the reactor must not be lost even temporarily due to a single failure.

〔発明の目的〕[Purpose of the invention]

本発明はこのような問題点にかんがみなされたもので、
流量信号処理回路の点検を安全かつ容易に行なうにあた
って、他の動作中の流量信号処理回路に異常があっても
スクラム機能を喪失することのないようにした熱出力監
視装置を提供することにある。
The present invention was conceived in view of these problems.
An object of the present invention is to provide a thermal output monitoring device that prevents the scram function from being lost even if there is an abnormality in other operating flow signal processing circuits, in order to safely and easily inspect flow signal processing circuits. .

〔発明の概要〕[Summary of the invention]

本発明は、流量信号処理回路の点検時において、外部か
らのスイッチ操作によシ、この回路出力に代わって、互
いに異なる低値選択回路(すなわち平均出力モニタ)の
入力となっている他の流量信号に切り替える回路を設け
たことを特徴とする。
In the present invention, when inspecting a flow rate signal processing circuit, by operating a switch from the outside, instead of this circuit output, other flow rates that are input to different low value selection circuits (i.e., average output monitors) are detected. It is characterized by being equipped with a circuit that switches to a signal.

〔発明の実施例〕[Embodiments of the invention]

以下、本発明を第4図により説明する。まずバイパスス
イッチ13A〜13Dを設け、これによシいずれかのバ
イパスリレー61A〜61Dを動作させる。仮に流量信
号処理回路6Aをバイパスしたとすれば、その出力は低
値選択回路91A。
The present invention will be explained below with reference to FIG. First, bypass switches 13A to 13D are provided, and any one of bypass relays 61A to 61D is operated by these switches. If the flow rate signal processing circuit 6A is bypassed, its output is the low value selection circuit 91A.

91C,91Eの入力としていない信号に切替えるよう
にする。ここでは仮に流量信号処理回路6Bの出力に切
替えるものとする。これにより低値選択回路91A、9
1C,91Eには流量信号処理回路6Cと6Bの流量信
号が入力されてるため、たとえ6Cか6Bのどちらかで
故障が発生しその信号が異常に高くなったとしても、も
う一つの正常信号が低値として選択されるため、原子炉
のスクラム機能が支障をきたすことはない。他の流量信
号処理回路についても第4図に示すような切替え回路を
構成すれば、上述と同様な機能が達成される。。
Switch to a signal that is not input to 91C and 91E. Here, it is assumed that the output is temporarily switched to the output of the flow rate signal processing circuit 6B. As a result, the low value selection circuits 91A, 9
Since the flow signals of the flow signal processing circuits 6C and 6B are input to 1C and 91E, even if a failure occurs in either 6C or 6B and that signal becomes abnormally high, the other normal signal will be input. It is selected as a low value so that the scram function of the reactor is not disturbed. If the other flow rate signal processing circuits are configured with switching circuits as shown in FIG. 4, the same functions as described above can be achieved. .

なお第4図の実施例に限らず、流量信号を他の回路から
の信号に切替えるだめの同様な機能を有する補々の回路
構成が可能であることはいうまでもない。
It goes without saying that the present invention is not limited to the embodiment shown in FIG. 4, and that a complementary circuit configuration having a similar function of switching the flow rate signal to a signal from another circuit is possible.

〔発明の効果〕〔Effect of the invention〕

以上のように本発明によれば、点検しようとする流量信
号処理回路の出力を、互いに異なる平均出力モニタ回路
の入力となっている信号に切替えるため、容易に回路の
点検ができる上に他の流量信号処理系内で単一故障が発
生しても原子炉のスクラム機能を維持できるという効果
がある。
As described above, according to the present invention, the output of the flow rate signal processing circuit to be inspected is switched to the signal that is input to the different average output monitor circuits. This has the effect of maintaining the scram function of the reactor even if a single failure occurs within the flow signal processing system.

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

第1図、第2図、第3図は従来実施例を示す回路図、第
4図は本発明の実施例を示す回路図である。
1, 2, and 3 are circuit diagrams showing conventional embodiments, and FIG. 4 is a circuit diagram showing an embodiment of the present invention.

Claims (1)

【特許請求の範囲】[Claims] 1、沸騰水形原子炉の再循環水流量を複数の流量測定器
で測定した信号を、各々流量信号に変換するための流量
信号処理回路を有し、上記各流量信号を低値選択して得
た信号に応じて原子炉のスクラム値を定め、かつ原子炉
の熱出力が上記スクラム値をこえた時に原子炉の緊急停
止信号を出力する複数の平均出力モニタ回路を備えた熱
出力監視装置において、外部からの操作により上記流量
信号処理回路の出力を、互いに異なる平均出力モニタ回
路の入力となっている他の流量信号処理回路の出力に切
替えることを特徴とした熱出力監視装置。
1. It has a flow rate signal processing circuit for converting the signals obtained by measuring the flow rate of recirculating water in a boiling water reactor with a plurality of flow rate measuring devices into flow rate signals, and selects a low value for each of the flow rate signals. A thermal output monitoring device comprising a plurality of average output monitoring circuits that determine a reactor scram value according to the obtained signal and output an emergency shutdown signal for the reactor when the reactor thermal output exceeds the scram value. A thermal output monitoring device characterized in that the output of the flow rate signal processing circuit is switched by an external operation to the output of another flow rate signal processing circuit serving as an input of a mutually different average output monitor circuit.
JP58029473A 1983-02-25 1983-02-25 Thermal power monitoring device Pending JPS59155790A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58029473A JPS59155790A (en) 1983-02-25 1983-02-25 Thermal power monitoring device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58029473A JPS59155790A (en) 1983-02-25 1983-02-25 Thermal power monitoring device

Publications (1)

Publication Number Publication Date
JPS59155790A true JPS59155790A (en) 1984-09-04

Family

ID=12277061

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58029473A Pending JPS59155790A (en) 1983-02-25 1983-02-25 Thermal power monitoring device

Country Status (1)

Country Link
JP (1) JPS59155790A (en)

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