JP5551356B2 - Reactor criticality judgment data collection device - Google Patents

Reactor criticality judgment data collection device Download PDF

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JP5551356B2
JP5551356B2 JP2008311483A JP2008311483A JP5551356B2 JP 5551356 B2 JP5551356 B2 JP 5551356B2 JP 2008311483 A JP2008311483 A JP 2008311483A JP 2008311483 A JP2008311483 A JP 2008311483A JP 5551356 B2 JP5551356 B2 JP 5551356B2
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祐治 田角
三輝雄 小山
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Chugoku Electric Power Co Inc
Hitachi GE Nuclear Energy Ltd
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Description

本発明は、原子炉の臨界を監視するための装置に関し、特に、原子炉の臨界判定に係るデータを収集するための原子炉臨界データ収集装置に関する。   The present invention relates to an apparatus for monitoring the criticality of a nuclear reactor, and more particularly to an apparatus for collecting criticality data of a nuclear reactor for collecting data relating to criticality determination of a nuclear reactor.

一般に、軽水型原子炉である沸騰水型原子炉（以下ＢＷＲと呼ぶ）には、原子炉核計装系として、炉心に複数の中性子束検出装置が配置され、原子炉起動時における原子炉出力および炉心の軸方向，径方向の出力分布を監視している。そして、各中性子束検出装置は複数の中性子束検出器を有しており、中性子束検出器の個数はチャンネル（ＣＨ）と呼ばれている。   In general, a boiling water reactor (hereinafter referred to as a BWR), which is a light water reactor, has a plurality of neutron flux detectors arranged in the core as a nuclear reactor instrumentation system, The power distribution in the axial and radial directions of the core is monitored. Each neutron flux detector has a plurality of neutron flux detectors, and the number of neutron flux detectors is called a channel (CH).

さらに、原子炉起動時においては臨界判定を行うため、各チャンネルにおける中性子束の炉周期を採取するばかりでなく、計数率、制御棒（ＣＲ）引き抜きステップ、原子炉圧力、炉水温度、及び原子炉水位等の各種パラメータを採取して、これらパラメータに応じて臨界判定を行う必要がある。そして、臨界に達したと判定した際には、臨界状態におけるパラメータを運転員が原子炉臨界記録として採取するようにしている。   Furthermore, in order to perform criticality determination at the time of reactor startup, not only the reactor cycle of neutron flux in each channel is collected, but also the counting rate, control rod (CR) extraction step, reactor pressure, reactor water temperature, and atomic It is necessary to collect various parameters such as reactor water level and perform criticality judgment according to these parameters. When it is determined that the criticality has been reached, the parameters in the critical state are collected by the operator as reactor criticality records.

一方、中性子束検出に応じて炉心の出力変動を検出し、炉心の安全性と原子炉の稼働率を向上させるため、中性子束検出信号に基づいて炉心の中性子束分布を算出し、この算出結果に応じて中性子束分布の高次モードを得て、さらに、中性子束検出信号に基づいてその信号変動の特徴を抽出するフィルタを求め、このフィルタでフィルタリングされた中性子束検出信号を出力するようにしたものがある（特許文献１参照）。
特開平６−２０１８８４号公報 On the other hand, in order to detect core power fluctuations according to neutron flux detection and improve core safety and reactor availability, the neutron flux distribution of the core is calculated based on the neutron flux detection signal. To obtain a higher-order mode of the neutron flux distribution according to the neutron flux distribution, and to obtain a filter for extracting the characteristics of the signal fluctuation based on the neutron flux detection signal, and to output a neutron flux detection signal filtered by this filter (See Patent Document 1).
JP-A-6-201884

ところで、上述のように、運転員が各種パラメータを監視しつつ、原子炉が臨界に達したか否かを判定し、運転員は原子炉が臨界に達したと判定すると、その時点におけるパラメータを採取するようにすると、運転員個人の判断に起因する誤差が生じることになる。   By the way, as described above, while monitoring the various parameters, the operator determines whether or not the reactor has reached the criticality, and when the operator determines that the reactor has reached the criticality, the parameters at that time are determined. If the sampling is performed, an error caused by the judgment of the individual operator occurs.

さらに、運転員は、臨界点に達した際のパラメータを採取しなければならず、原子炉の運転・操作に当たって、臨界点におけるパラメータの採取も行わなければならないとすると、運転員に過剰な負担が掛かってしまう。   Furthermore, if the operator must collect parameters when the critical point is reached and must also collect parameters at the critical point when operating and operating the reactor, the operator will be overburdened. Will be applied.

従って、本発明は、運転員に負担を掛けることなく、臨界点における各種パラメータを採取して、これら採取されたパラメータを臨界判定の資料として用いることのできる原子炉臨界判定データ収集装置を提供することを目的とする。   Therefore, the present invention provides a reactor criticality judgment data collection device that can collect various parameters at critical points without using a burden on the operator, and can use these collected parameters as data for criticality judgment. For the purpose.

（１） 本発明は、原子炉からの熱出力に応じて発電を行う原子力発電システムに用いられ、前記原子炉の各種測定データをパラメータとして測定する測定手段を備える原子炉臨界判定データ収集装置であって、前記原子炉の起動の際に、前記測定手段で測定されたパラメータに基づいて前記原子炉が臨界点に達したと判定されると当該臨界点における前記パラメータを原子炉臨界判定データとするデータ収集手段と、前記原子炉臨界判定データを出力する出力手段とを有し、前記データ収集手段は、前記原子炉が臨界点に達したと判定された場合に、前記原子炉臨界判定データを前記出力手段に出力し、前記測定手段として、前記原子炉の炉心の中性子束を測定する中性子束測定手段、前記原子炉の炉水温度を測定する温度測定手段、前記原子炉内の圧力を測定する原子炉圧力測定手段、及び前記原子炉の水位を測定する原子炉水位測定手段が用いられ、前記臨界点の判定に当たっては前記炉心から引き抜かれる制御棒の引き抜きステップも用いるようにしたことを特徴とするものである。 (1) The present invention is a reactor criticality judgment data collection device that is used in a nuclear power generation system that generates power in accordance with heat output from a nuclear reactor, and includes measurement means that measures various measurement data of the nuclear reactor as parameters. When the reactor is started up, if it is determined that the reactor has reached a critical point based on the parameter measured by the measuring means, the parameter at the critical point is determined as reactor criticality determination data. Data collecting means and output means for outputting the reactor criticality judgment data, the data collecting means, when it is judged that the reactor has reached a critical point, the reactor criticality judgment data To the output means, and as the measurement means, a neutron flux measurement means for measuring the neutron flux in the core of the reactor, a temperature measurement means for measuring the reactor water temperature, and the original Reactor pressure measuring means for measuring the pressure in the sub-reactor and reactor water level measuring means for measuring the water level of the reactor are used, and in the determination of the critical point, a control rod withdrawing step is also carried out. it is characterized in that as used.

（１）に記載の原子炉臨界判定データ収集装置では、原子炉の起動の際に、測定されたパラメータに基づいて原子炉が臨界点に達したと判定された場合に、上記のパラメータを原子炉臨界判定データとしてプリントアウト等出力するようにしたので、自動で臨界判定を行い、しかもその時のパラメータが採取でき、運転員の負担を軽減することができる。   In the reactor criticality judgment data collection device described in (1), when it is determined that the reactor has reached the critical point based on the measured parameters at the time of starting up the reactor, Since the data such as printout is output as the furnace criticality judgment data, criticality judgment is automatically performed, and the parameters at that time can be collected, thereby reducing the burden on the operator.

また、（１）に記載の原子炉臨界判定データ収集装置では、原子炉の炉心の中性子束測定結果、炉水温度、原子炉圧力、及び原子炉水位に加えて、制御棒の引き抜きステップに応じて臨界判定を行うようにしたので、精度よく臨界点を判定することができる。 In addition, in the reactor criticality judgment data collection device described in (1 ), in addition to the neutron flux measurement result of the reactor core, the reactor water temperature, the reactor pressure, and the reactor water level, in accordance with the control rod extraction step Therefore, the critical point can be accurately determined.

（２） 本発明は、（１）に記載の原子炉臨界判定データ収集装置において、前記原子炉の起動毎にその日付日時に対応付けて前記原子炉臨界判定データを記録するデータベースを有することを特徴とするものである。 ( 2 ) The present invention has a database for recording the reactor criticality judgment data in association with the date and time each time the reactor is started up in the reactor criticality judgment data collection device described in ( 1). It is a feature.

（２）に記載の原子炉臨界判定データ収集装置では、原子炉の起動毎にその日付日時に対応付けてパラメータをデータベースに原子炉臨界判定データとして記録するようにしたので、後日臨界点の分析に用いることができるばかりでなく、臨界点の判定データを蓄積して、臨界点の判定に用いれば、臨界点の判定精度を向上させることができる。 In the reactor criticality judgment data collection device described in ( 2 ), the parameters are recorded in the database as reactor criticality judgment data in association with the date and time each time the reactor is started. If critical point determination data is accumulated and used for critical point determination, the critical point determination accuracy can be improved.

以上のように、本発明によれば、原子炉の起動の際に、測定されたパラメータに基づいて原子炉が臨界点に達したと判定された場合に、上記のパラメータを原子炉臨界判定データとして出力するようにしたので、運転員に負担を掛けることなく、臨界点における各種パラメータを採取することができるという効果がある。   As described above, according to the present invention, when it is determined that the reactor has reached the critical point based on the measured parameters at the time of starting the reactor, the above parameters are used as the reactor criticality determination data. As a result, it is possible to collect various parameters at critical points without imposing a burden on the operator.

以下、本発明の実施形態による原子炉臨界判定データ収集装置の一例について図面を参照して説明する。   Hereinafter, an example of a reactor criticality judgment data collection device according to an embodiment of the present invention will be described with reference to the drawings.

図１は、本発明の実施の形態による原子炉臨界判定データ収集装置の構成を示す図である。図１において、軽水炉である沸騰水型原子炉（ＢＷＲ）等の原子炉１１には炉心１２が格納されており、この炉心１２に中性子計測装置１３が配置されている。   FIG. 1 is a diagram showing a configuration of a reactor criticality judgment data collection apparatus according to an embodiment of the present invention. In FIG. 1, a core 12 is stored in a nuclear reactor 11 such as a boiling water reactor (BWR) which is a light water reactor, and a neutron measuring device 13 is disposed in the core 12.

この中性子計測装置１３は、例えば、原子炉１１の出力運転時等において原子炉出力及び炉心１２における軸方向及び径方向の出力分布を監視する（つまり、中性子計測装置１３は各チャンネル（ＣＨ）の炉周期及び計数率を計測することになる）。そして、中性子計測装置１３は、ＣＨ毎にその中性子束測定結果を示す中性子出力信号を、データ収集器１６に送出する。   The neutron measurement device 13 monitors the nuclear power and the power distribution in the axial direction and the radial direction in the core 12 at the time of, for example, the power operation of the reactor 11 (that is, the neutron measurement device 13 is connected to each channel (CH)). The furnace cycle and counting rate will be measured). Then, the neutron measurement device 13 sends a neutron output signal indicating the neutron flux measurement result for each CH to the data collector 16.

一方、原子炉１１内には、原子炉１１の現況を計測するための現況測定器（以下単に測定器と呼ぶ）１４が配置されている。この測定器１４として、例えば、炉水温度を計測する炉水温度計測センサー、原子炉圧力を計測する原子炉圧力計測センサー、及び原子炉水位を計測する原子炉水位センサーがある。そして、これら炉水温度計測センサー、原子炉圧力計測センサー、及び原子炉水位センサーは、それぞれ炉水温度計測信号、原子炉圧力計測信号、及び原子炉水位信号を、データ収集器１６に送る。   On the other hand, in the reactor 11, a current state measuring device (hereinafter simply referred to as a measuring device) 14 for measuring the current state of the nuclear reactor 11 is disposed. Examples of the measuring instrument 14 include a reactor water temperature measuring sensor that measures the reactor water temperature, a reactor pressure measuring sensor that measures the reactor pressure, and a reactor water level sensor that measures the reactor water level. The reactor water temperature measurement sensor, the reactor pressure measurement sensor, and the reactor water level sensor send the reactor water temperature measurement signal, the reactor pressure measurement signal, and the reactor water level signal to the data collector 16, respectively.

炉心１２内には燃料棒（図示せず）とともに、制御棒１５ａが挿入されており、原子炉１１を起動する際には、制御棒１５ａが引き抜かれる。制御棒１５ａは制御棒駆動制御装置１５によって挿入・引き抜き駆動制御される。原子炉１１を起動する際において、制御棒駆動制御装置１５は、引き抜き指令があると、当該引き抜き指令で示された引き抜きステップで制御棒１５を引き抜き駆動制御する。   A control rod 15a is inserted into the reactor core 12 together with a fuel rod (not shown). When the nuclear reactor 11 is started, the control rod 15a is pulled out. The control rod 15a is controlled to be inserted and pulled out by the control rod drive control device 15. When starting up the nuclear reactor 11, if there is an extraction command, the control rod drive control device 15 controls the extraction of the control rod 15 at the extraction step indicated by the extraction command.

データ収集器１６は、予め設定された周期（例えば、１秒）毎に、中性子出力信号、炉水温度計測信号、原子炉圧力計測信号、及び原子炉水位信号を収集し、デジタル信号に変換して、プロセス計算機１７に与える。さらに、プロセス計算機１７には、制御棒駆動制御装置１５から制御棒１５ａの引き抜きステップを示す制御棒引き抜きステップ信号が与えられる。   The data collector 16 collects a neutron output signal, a reactor water temperature measurement signal, a reactor pressure measurement signal, and a reactor water level signal every predetermined period (for example, 1 second) and converts them into digital signals. To the process computer 17. Further, the process computer 17 is given a control rod extraction step signal indicating the extraction step of the control rod 15a from the control rod drive control device 15.

プロセス計算機１７には、表示装置（例えば、ＣＲＴ）１８、出力装置（例えば、プリンター）１９、データベース（記憶装置）２０、及び入力装置（キーボード等の各種入力手段）２１が接続されている。プロセス計算機１７は、後述するようにして、前述の中性子出力信号、炉水温度計測信号、原子炉圧力計測信号、原子炉水位信号、及び制御棒引き抜きステップ信号に応じて臨界判定を行う。   A display device (for example, CRT) 18, an output device (for example, printer) 19, a database (storage device) 20, and an input device (various input means such as a keyboard) 21 are connected to the process computer 17. As will be described later, the process computer 17 performs criticality determination according to the above-described neutron output signal, reactor water temperature measurement signal, reactor pressure measurement signal, reactor water level signal, and control rod extraction step signal.

なお、表示装置１８には、中性子出力信号で示される各ＣＨの出力分布（炉周期及び計数率）が表示されるとともに、炉水温度、原子炉圧力、原子炉水位、及び制御棒引き抜きステップが各種パラメータとして表示される。これら各種パラメータは、入力装置２１からの表示指令に応じて選択的に表示させることができる。   The display device 18 displays the output distribution (reactor cycle and count rate) of each CH indicated by the neutron output signal, as well as the reactor water temperature, reactor pressure, reactor water level, and control rod extraction steps. Displayed as various parameters. These various parameters can be selectively displayed in accordance with a display command from the input device 21.

プロセス計算機１７はプリントアウト指令に応じて前述の各種パラメータを出力装置１９にプリントアウトする。さらに、プロセス計算機１７は、臨界判定を行った際には、つまり、臨界点に達した際には、自動的に前述の各種パラメータを出力装置にプリントアウトするとともに、データベース２０に臨界点におけるパラメータとして格納する。   The process computer 17 prints out the various parameters described above to the output device 19 in response to a printout command. Further, the process computer 17 automatically prints out the above-mentioned various parameters to the output device when the criticality judgment is made, that is, when the critical point is reached, and the database 20 sets the parameters at the critical point in the database 20. Store as.

データベース２０には、原子炉１１の起動毎の臨界点における各種パラメータが日付に対応付けて格納され、データベース２０に格納された各種パラメータは、入力装置２１からのデータベース出力指令に応じて表示装置１８に表示させることができる。また、適宜出力装置１９からプリントアウトすることもできる。   In the database 20, various parameters at the critical point for each start-up of the reactor 11 are stored in association with dates, and the various parameters stored in the database 20 are displayed in accordance with a database output command from the input device 21. Can be displayed. Further, it is possible to print out from the output device 19 as appropriate.

また、データベース２０には臨界点を判定するための臨界点判定データ（臨界点閾値）が格納され、プロセス計算機１７は、臨界点判定データを参照して、前述の中性子出力信号、炉水温度計測信号、原子炉圧力計測信号、原子炉水位信号、及び制御棒引き抜きステップ信号に基づいて臨界点を判定する。   The database 20 stores critical point determination data (critical point threshold value) for determining the critical point, and the process computer 17 refers to the critical point determination data to measure the neutron output signal and the reactor water temperature. The critical point is determined based on the signal, the reactor pressure measurement signal, the reactor water level signal, and the control rod extraction step signal.

ここで、図２も参照して、原子炉１１を起動する際のデータ（各種パラメータ）の収集について説明する。   Here, the collection of data (various parameters) when starting up the nuclear reactor 11 will be described with reference to FIG.

原子炉１１を起動する際には、制御棒駆動制御装置１５に対して引き抜き指令が与えられる（ステップＳ１）。制御棒駆動制御装置１５は、引き抜き指令で示される引き抜きステップに応じて制御棒１５ａを炉心１２から引き抜き制御する（ステップＳ２）。この際、前述のように、制御棒駆動制御装置１５から引き抜きステップを表す制御棒引き抜きステップ信号がプロセス計算機１７に与えられる。   When starting up the nuclear reactor 11, an extraction command is given to the control rod drive control device 15 (step S1). The control rod drive control device 15 controls the extraction of the control rod 15a from the core 12 in accordance with the extraction step indicated by the extraction command (step S2). At this time, as described above, a control rod extraction step signal indicating an extraction step is given from the control rod drive control device 15 to the process computer 17.

前述したように、中性子計測装置１３は、各ＣＨにおける中性子束を測定しており、データ収集器１６は、中性子束測定信号をサンプリングしてプロセス計算機１７に送る。同様に、測定器１４によって、炉水温度、原子炉圧力、及び原子炉水位が計測され、データ収集器１６はこれら炉水温度計測信号、原子炉圧力計測信号、及び原子炉水位信号をサンプリングしてプロセス計算機１７に送る（各種パラメータの収集：ステップＳ３）。   As described above, the neutron measurement device 13 measures the neutron flux in each CH, and the data collector 16 samples the neutron flux measurement signal and sends it to the process computer 17. Similarly, the reactor 14 measures the reactor water temperature, reactor pressure, and reactor water level. The data collector 16 samples the reactor water temperature measurement signal, reactor pressure measurement signal, and reactor water level signal. To the process computer 17 (collection of various parameters: step S3).

プロセス計算機１７は、データベース２０から臨界点判定データを読み出して、中性子束測定結果、炉水温度、原子炉圧力、原子炉水位、及び制御棒引き抜きステップ（各種パラメータ）と臨界点判定データとを比較し（ステップＳ４）、原子炉１１が臨界点に達したか否かを判定する（ステップＳ５）。   The process computer 17 reads the critical point determination data from the database 20 and compares the neutron flux measurement result, the reactor water temperature, the reactor pressure, the reactor water level, and the control rod extraction step (various parameters) with the critical point determination data. (Step S4), it is determined whether or not the reactor 11 has reached a critical point (Step S5).

プロセス計算機１７では、臨界点に達したと判定すると、前述の各種パラメータを表示装置１８に表示するとともに、各種パラメータを出力装置１９に原子炉臨界点判定データとしてプリントアウトする（ステップＳ６）。また、プロセス計算機１７は臨界点における各種パラメータを日付（日時）に対応付けて、原子炉臨界点判定データとしてデータベース２０に格納し、臨界点におけるデータベースを構築することになる（ステップＳ７）。   If it is determined that the critical point has been reached, the process computer 17 displays the various parameters described above on the display device 18 and prints out the various parameters on the output device 19 as reactor critical point determination data (step S6). Further, the process computer 17 associates various parameters at the critical point with the date (date and time) and stores them in the database 20 as reactor critical point determination data, thereby constructing a database at the critical point (step S7).

このようにして、臨界点に達すると、自動的に臨界点における各種パラメータをプリントアウトするようにしたので、運転員に負担を掛けることなく、臨界点における各種パラメータを採取することができ、しかも、後日これら採取されたパラメータを臨界判定の資料として用いることもできる。   In this way, when the critical point is reached, various parameters at the critical point are automatically printed out, so that various parameters at the critical point can be collected without imposing a burden on the operator. Later, these collected parameters can be used as criticality judgment data.

本発明の実施の形態による原子炉臨界判定データ収集装置の構成の一例を概略的に示す図である。It is a figure which shows roughly an example of a structure of the reactor criticality determination data collection apparatus by embodiment of this invention. 図１に示す原子炉臨界判定データ収集装置の動作を説明するためのフロー図である。It is a flowchart for demonstrating operation | movement of the reactor criticality judgment data collection apparatus shown in FIG.

符号の説明Explanation of symbols

１１ 原子炉
１２ 炉心
１３ 中性子計測装置
１４ 現況測定器
１５ａ 制御棒
１５ 制御棒駆動制御装置
１６ データ収集器
１７ プロセス計算機
１８ 表示装置
１９ 出力装置
２０ データベース
２１ 入力装置 DESCRIPTION OF SYMBOLS 11 Reactor 12 Core 13 Neutron measuring device 14 Current measuring device 15a Control rod 15 Control rod drive control device 16 Data collector 17 Process computer 18 Display device 19 Output device 20 Database 21 Input device

Claims (2)

原子炉からの熱出力に応じて発電を行う原子力発電システムに用いられ、前記原子炉の各種測定データをパラメータとして測定する測定手段を備える原子炉臨界判定データ収集装置であって、
前記原子炉の起動の際に、前記測定手段で測定されたパラメータに基づいて前記原子炉が臨界点に達したと判定されると当該臨界点における前記パラメータを原子炉臨界判定データとするデータ収集手段と、
前記原子炉臨界判定データを出力する出力手段とを有し、
前記データ収集手段は、前記原子炉が臨界点に達したと判定された場合に、前記原子炉臨界判定データを前記出力手段に出力し、
前記測定手段として、前記原子炉の炉心の中性子束を測定する中性子束測定手段、前記原子炉の炉水温度を測定する温度測定手段、前記原子炉内の圧力を測定する原子炉圧力測定手段、及び前記原子炉の水位を測定する原子炉水位測定手段が用いられ、
前記臨界点の判定に当たっては前記炉心から引き抜かれる制御棒の引き抜きステップも用いるようにしたことを特徴とする原子炉臨界判定データ収集装置。 Reactor criticality determination data collection device used in a nuclear power generation system that generates power in accordance with heat output from a nuclear reactor, comprising measurement means for measuring various measurement data of the nuclear reactor as parameters,
When it is determined that the reactor has reached a critical point based on the parameters measured by the measuring means when the reactor is started up, data collection using the parameters at the critical point as reactor criticality determination data Means,
Output means for outputting the reactor criticality judgment data,
The data collection means outputs the reactor criticality judgment data to the output means when it is determined that the reactor has reached a critical point ,
As the measuring means, a neutron flux measuring means for measuring the neutron flux of the reactor core, a temperature measuring means for measuring the reactor water temperature of the reactor, a reactor pressure measuring means for measuring the pressure in the reactor, And a reactor water level measuring means for measuring the water level of the reactor is used,
In the determination of the critical point, the reactor criticality determination data collecting apparatus is characterized in that a control rod extraction step that is extracted from the core is also used . 前記原子炉の起動毎にその日付日時に対応付けて前記原子炉臨界判定データを記録するデータベースを有することを特徴とする請求項１記載の原子炉臨界判定データ収集装置。 Reactor criticality judging data collecting device according to claim 1, characterized in that it has a database that records the reactor criticality judging data in association with the date time for each startup of the nuclear reactor.
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