JPH0458913B2 - - Google Patents

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Publication number
JPH0458913B2
JPH0458913B2 JP60199999A JP19999985A JPH0458913B2 JP H0458913 B2 JPH0458913 B2 JP H0458913B2 JP 60199999 A JP60199999 A JP 60199999A JP 19999985 A JP19999985 A JP 19999985A JP H0458913 B2 JPH0458913 B2 JP H0458913B2
Authority
JP
Japan
Prior art keywords
temperature
moderator
reactivity
coefficient
reactor
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
Application number
JP60199999A
Other languages
Japanese (ja)
Other versions
JPS6259899A (en
Inventor
Juzo Nakano
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP60199999A priority Critical patent/JPS6259899A/en
Publication of JPS6259899A publication Critical patent/JPS6259899A/en
Publication of JPH0458913B2 publication Critical patent/JPH0458913B2/ja
Granted 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】[Detailed description of the invention]

〈産業上の利用分野〉 本発明は、原子炉の起動試験、定期試験等で実
施される炉心特性調査の一環として行われる減速
材温度係数測定に使用する装置に関するものであ
る。 〈従来の技術〉 従来、原子炉反応度を求める一つの方法とし
て、炉心内又は炉心付近に設置した中性子束検出
器から得られる微小電流を、電流増幅器で電圧変
換した後、動特性方程式を解く原子炉反応度計の
入力信号として用い、得られた反応度をXY記録
のY軸へ記録し、他方のX軸には減速材温度計か
らの温度信号を測定温度範囲に調整されたものを
接続し記録する。 次に、このように記録された反応度トレースか
ら目的とする減速材温度係数を求める方法につい
て述べる。第4図は上述したXY記録計に記録さ
れた減速材温度変化ロに対する反応度変化イであ
り、炉心の減速材温度変化に伴う反応度変化がこ
のトレースの傾きとして記録される。この傾きか
ら単位温度当りの反応度変化として得られるもの
が等温度係数とよ呼ばれ、減速材温度係数とドツ
プラ温度係数が加算されたものである。従つて目
的とする減速材温度係数は、この等温度係数から
ドツプラ温度係数を手計算により差し引くことに
より求める。 このように従来技術では、トレースから傾きを
求める際に、あらかじめ予定していた測定温度範
囲の測定が終了した後に、人手処理によりトレー
スの傾きを求めていた。従つて、結果が得られる
までに時間が必要とされ、人為処理の煩わしさが
あつた。 またこの測定値を所定の記録様式、第1表を作
成するための処理作業も必要とされている。
<Industrial Field of Application> The present invention relates to an apparatus used for measuring the temperature coefficient of a moderator, which is carried out as part of a core characteristic investigation carried out in a nuclear reactor start-up test, periodic test, etc. <Conventional technology> Conventionally, one method for determining reactor reactivity is to convert the minute current obtained from a neutron flux detector installed in or near the reactor core into voltage using a current amplifier, and then solve the dynamic characteristic equation. Used as an input signal for the reactor reactivity meter, the obtained reactivity is recorded on the Y axis of the XY record, and the temperature signal from the moderator thermometer is adjusted to the measurement temperature range on the other X axis. Connect and record. Next, a method for determining the desired moderator temperature coefficient from the reactivity trace recorded in this manner will be described. FIG. 4 shows the change in reactivity (A) with respect to the change in moderator temperature (B) recorded by the XY recorder mentioned above, and the change in reactivity accompanying the change in moderator temperature in the core is recorded as the slope of this trace. The change in reactivity per unit temperature obtained from this slope is called the isotemperature coefficient, and is the sum of the moderator temperature coefficient and the Doppler temperature coefficient. Therefore, the desired moderator temperature coefficient is determined by manually subtracting the Doppler temperature coefficient from this isotemperature coefficient. As described above, in the prior art, when determining the slope from a trace, the slope of the trace is determined by manual processing after the measurement in a predetermined measurement temperature range is completed. Therefore, it takes time to obtain results, and manual processing is cumbersome. Processing work is also required to prepare the measured values in a predetermined recording format, Table 1.

【表】【table】

【表】 〈発明が解決しようとする問題点〉 従来技術で、人手処理により求めている減速材
温度係数測定には、その結果を得るために、煩わ
しさが伴い、かつ結果が得られるために時間が必
要とされていた。本発明はかかる問題点を速やか
に解決する原子炉の減速材温度係数測定装置を提
供することを目的とするものである。 〈問題点を解決するための手段〉 そのため、本発明の減速材温度係数測定装置
は、炉心又は炉心付近に設置した中性子束検出器
から得られた電流を電圧変換して動特性方程式を
解く原子炉反応度計と減速材平均温度計と制御棒
位置指示計を設置した原子炉において、 (イ) 制御棒の位置を検出する手段、 (ロ) 原子炉の反応度を検出する手段、 (ハ) 減速材の温度を検出する手段、 (ニ) 上記制御棒位置、反応度及び減速材温度を記
憶すると共にドツプラ温度係数の設計値を記憶
する手段、 (ホ) 上記記憶手段から同一制御棒位置において減
速材の温度変化が等しくなる間隔で反応度と減
速材温度より回帰計算を行つて等温度係数を算
出し、この等温度係数とドツプラ温度係数より
減速材温度係数を算出する手段、 (ヘ) 反応度と減速材温度の関係を連続的にXY記
録計に作図する手段。 (ト) 上記記憶した数値及び算出結果を逐次表示す
る手段。 (チ) 予定された温度範囲の測定が終了すればその
結果を印字する手段、 とよりなるものである。 〈実施例〉 以下、添付図に基づいて本発明の原子炉の減速
材温度係数測定装置を詳細に説明する。 第1図は本発明の測定装置の機能実現手段を示
すブロツク図、第2図は本発明測定装置の一実施
例の構造を示すブロツク図でAの鎖線部分が本発
明の装置、第3図は本発明測定装置による処理ス
テツプを示すフローチヤート図、第4図は作図装
置で作図した減速材温度に対する反応度のグラフ
である。 原子炉には、炉心又は炉心付近に設置した中性
子束を検出する中性子検出器1aから得られた電
流を電圧変換して動特性方程式を解く原子炉反応
度計1が設けられ、反応度の信号が供給される。 また、制御棒位置は制御棒駆動装置(図示せ
ず)の制御棒位置指示計2から、減速材温度は減
速材平均温度計3から信号が本発明の装置に供給
される。上記減速材平均温度計3の信号はA/D
コンバーター4で変換され、原子炉反応度計1の
信号はシリアルインターフエース5で変換され、
また制御棒位置指示計2の信号はA/D変換又は
パルスカウンター6を通り、I/Oポート7を経
てCPU8に供給される。上記制御棒位置指示計
2にはアナログ発信のものとパルス発信のものが
あるが、パルス発信のものが精度がよい。このパ
ルス発信の信号は制御棒引き抜き信号と制御棒挿
入信号とに分けられていて、それぞれの引き抜き
時と挿入時に独立してパルス信号を発信し、この
引き抜き及び挿入のパルスをパルスカウンター6
で積算し、2種類のパルスを減算することで制御
棒の位置を求める。上記CPU8にはRAM9及び
外部記憶装置10に接続され、以下の如きステツ
プで処理を行う。 減速材温度が変化すると、炉心固有の温度係数
により炉心反応度が変化する。この反応度変化は
例えば2℃程度の温度変化巾では直線状に変化す
るものであるため、微小温度変化(0.01℃程度)
毎にそのときの温度と反応度を測定し、XY記録
計の作図装置14に作図し、外部記憶装置10に
記憶すると共に回帰計算を行い等温度係数を計算
し、該計算値と、予め上記外部記憶装置10に記
憶されたドツプラ温度係数の設計値により減速材
温度係数を算出する。加えて、制御棒位置が測定
中に変化した場合(測定中の中性子束調整のた
め)、この間のデータを削除することにより同一
制御棒位置における減速材温度係数の測定を可能
にできる。処理結果は、測定開始後数点のデータ
を採取すると逐次、減速材温度係数を表示装置1
2に表示すると共に、規定の測定が終了すれば、
従来同様第1表のような測定結果を印字装置13
に出力する。処理手順を第3図に示す。この図は
制御棒位置指示計2がパルス発信の場合を示す。 先ず、初期化21の部分で、初期制御棒位置の更
新を行う。ステツプ22で微小温度が変化したかを
判断し、Yesの場合、ステツプ23で制御棒位置が
変わつたことを判断する。Noの場合ステツプ24
で作図(第3図で示せばジグザグの各測定点14
a)及び回帰計算(作図は作図装置14で、回帰
計算はCPU8で行う)をし、ステツプ26でパラ
メータ及び演算結果の外部記憶と表示装置12へ
の表示を行う。次にステツプ27で測定終了かを判
断し、Yesの場合ステツプ28で測定結果の印字及
び作図(印字は印字装置13で、作図は作図装置
14で行い、作図を第3図で示せば各測定点14
aを結ぶ直線14b)を行う。ステツプ22でNo
又はステツプ23でYesの場合、即ち、減速材温度
が変化しないか又は制御棒位置が変化中の場合は
作図及び回帰計算処理を行わない。ステツプ27で
測定終了していない(No)場合、引き続きステ
ツプ22に戻り繰り返す。 〈発明の効果〉 以上詳細に説明した原子炉の減速材温度係数測
定装置は次のような効果を奏する。 実時間処理が行われ、試験終了後直ちに設計
値と測定値とを比較できるので、処理時間の大
巾な短縮となるほか、省力化及び原子炉の稼動
率向上が図れる。 処理手順の中で、回帰計算を行う間隔を微少
減速材温度の変化が生じた時に実施しているの
で、減速材温度の変化割合が測定途中で変化し
た場合でも、精度よく処理を行うことができ
る。 測定装置が小型化できるため、中央制御室の
ような試験実施場所で使用できる。このため、
試験員及びデータ整理員の削減が可能である。
[Table] <Problems to be solved by the invention> In the prior art, moderator temperature coefficient measurement, which is determined by manual processing, involves a lot of trouble in order to obtain the results. Time was needed. It is an object of the present invention to provide a moderator temperature coefficient measuring device for a nuclear reactor that can quickly solve these problems. <Means for Solving the Problems> Therefore, the moderator temperature coefficient measurement device of the present invention is an atomic moderator that solves the dynamic characteristic equation by converting the current obtained from the neutron flux detector installed in or near the reactor core into a voltage. In a nuclear reactor equipped with a reactor reactivity meter, a moderator average temperature meter, and a control rod position indicator, (a) means for detecting the position of the control rods, (b) means for detecting the reactivity of the reactor, (c) ) Means for detecting the moderator temperature; (d) Means for storing the control rod position, reactivity and moderator temperature as well as the design value of the Doppler temperature coefficient; (e) Means for detecting the same control rod position from the above storage means. A method for calculating the isotemperature coefficient by performing regression calculation from the reactivity and the moderator temperature at intervals where the temperature change of the moderator is equal, and calculating the moderator temperature coefficient from the isotemperature coefficient and the Doppler temperature coefficient. ) A means of continuously plotting the relationship between reactivity and moderator temperature on an XY recorder. (g) Means for sequentially displaying the above-mentioned memorized numerical values and calculation results. (H) A means for printing out the results once the measurement in the scheduled temperature range is completed; <Example> Hereinafter, the moderator temperature coefficient measuring device for a nuclear reactor of the present invention will be described in detail based on the accompanying drawings. FIG. 1 is a block diagram showing the function implementation means of the measuring device of the present invention, and FIG. 2 is a block diagram showing the structure of an embodiment of the measuring device of the present invention. 4 is a flowchart showing processing steps performed by the measuring device of the present invention, and FIG. 4 is a graph of reactivity versus moderator temperature drawn by the plotting device. The reactor is equipped with a reactor reactivity meter 1 that converts the current obtained from a neutron detector 1a installed in or near the core to a voltage to solve a dynamic characteristic equation, and generates a signal of reactivity. is supplied. Furthermore, signals for control rod position are supplied to the apparatus of the present invention from a control rod position indicator 2 of a control rod drive device (not shown), and signals for moderator temperature are supplied from a moderator average thermometer 3. The signal of the moderator average thermometer 3 is A/D
The signal from the reactor reactivity meter 1 is converted by the serial interface 5.
Further, the signal from the control rod position indicator 2 passes through an A/D converter or a pulse counter 6, and is supplied to the CPU 8 via an I/O port 7. There are two types of control rod position indicators 2, one that emits analog signals and one that emits pulse signals, but the one that emits pulse signals is more accurate. This pulse transmission signal is divided into a control rod withdrawal signal and a control rod insertion signal. Pulse signals are transmitted independently at the time of each withdrawal and insertion, and the pulses of this withdrawal and insertion are sent to a pulse counter 6.
The position of the control rod is determined by integrating the two types of pulses and subtracting the two types of pulses. The CPU 8 is connected to a RAM 9 and an external storage device 10, and performs processing in the following steps. When the moderator temperature changes, the core reactivity changes due to the temperature coefficient specific to the core. For example, this change in reactivity changes linearly within a temperature change range of about 2℃, so it is a small temperature change (about 0.01℃).
The temperature and reaction rate at each time are measured, plotted in the drawing device 14 of the XY recorder, stored in the external storage device 10, and a regression calculation is performed to calculate the isotemperature coefficient. The moderator temperature coefficient is calculated based on the design value of the Doppler temperature coefficient stored in the external storage device 10. In addition, if the control rod position changes during the measurement (due to neutron flux adjustment during the measurement), data during this time can be deleted to enable measurement of the moderator temperature coefficient at the same control rod position. As for the processing results, when several points of data are collected after the start of measurement, the moderator temperature coefficient is displayed on the display device 1.
2 and when the specified measurement is completed,
As before, the measurement results as shown in Table 1 are printed on the printing device 13.
Output to. The processing procedure is shown in FIG. This figure shows a case where the control rod position indicator 2 emits pulses. First, in the initialization 21 part, the initial control rod position is updated. In step 22, it is determined whether the minute temperature has changed, and if yes, in step 23, it is determined that the control rod position has changed. If no, step 24
(as shown in Figure 3, each measurement point 14 of the zigzag
a) and regression calculations (plotting is performed by the drawing device 14 and regression calculations by the CPU 8), and in step 26, parameters and calculation results are stored externally and displayed on the display device 12. Next, in step 27, it is determined whether the measurement is completed, and if Yes, in step 28, the measurement results are printed and plotted (printing is done by the printing device 13, and plotting is done by the plotting device 14. point 14
A straight line 14b) connecting points a is performed. No on step 22
Or, if Yes in step 23, that is, if the moderator temperature is not changing or the control rod position is changing, the drawing and regression calculation processes are not performed. If the measurement is not completed at step 27 (No), return to step 22 and repeat. <Effects of the Invention> The nuclear reactor moderator temperature coefficient measuring device described in detail above has the following effects. Since real-time processing is performed and design values and measured values can be compared immediately after the test is completed, processing time can be significantly shortened, and labor savings and reactor operating rates can be improved. In the processing procedure, regression calculations are performed at intervals when a slight change in moderator temperature occurs, so even if the rate of change in moderator temperature changes during measurement, the process can be performed accurately. can. Since the measuring device can be made smaller, it can be used in test locations such as central control rooms. For this reason,
It is possible to reduce the number of testers and data organizers.

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

第1図は本発明の減速材温度係数測定装置によ
る機能実現手段を示すブロツク図、第2図は本発
明測定装置の一実施例の構造を示すブロツク図、
第3図は本発明測定装置による処理ステツプを示
すフローチヤート図、第4図は作図装置で作図し
た減速材温度に対する反応度のグラフである。 1……原子炉反応度計、1a……中性子束検出
器、2……制御棒位置指示計、3……減速材平均
温度計、4……A/Dコンバーター、5……シリ
アルインターフエース、6……A/Dコンバータ
ー又はパルスカウンター、7,11……I/Oポ
ート、8……CPU、9……RAM、10……外部
記憶装置、12……表示装置、13……印字装
置、14……作図装置。
FIG. 1 is a block diagram showing the means for realizing functions by the moderator temperature coefficient measuring device of the present invention, and FIG. 2 is a block diagram showing the structure of an embodiment of the measuring device of the present invention.
FIG. 3 is a flowchart showing processing steps by the measuring device of the present invention, and FIG. 4 is a graph of reactivity versus moderator temperature drawn by the plotting device. 1... Reactor reactivity meter, 1a... Neutron flux detector, 2... Control rod position indicator, 3... Moderator average temperature meter, 4... A/D converter, 5... Serial interface, 6...A/D converter or pulse counter, 7, 11...I/O port, 8...CPU, 9...RAM, 10...external storage device, 12...display device, 13...printing device, 14...Drawing device.

Claims (1)

【特許請求の範囲】 1 炉心又は炉心付近に設置した中性子束検出器
から得られた電流を電圧変換して動特性方程式を
解く原子炉反応度計と減速材平均温度計と制御棒
位置指示計を設置した原子炉において、 (イ) 制御棒の位置を検出する手段、 (ロ) 原子炉の反応度を検出する手段、 (ハ) 減速材の温度を検出する手段、 (ニ) 上記制御棒位置、反応度及び減速材温度を記
憶すると共にドツプラ温度係数の設計値を記憶
する手段、 (ホ) 上記記憶手段から同一制御棒位置において減
速材の温度変化が等しくなる間隔で反応度と減
速材温度より回帰計算を行つて等温度係数を算
出し、この等温度係数とドツプラ温度係数より
減速材温度係数を算出する手段、 (ヘ) 反応度と減速材温度の関係を連続的にXY記
録計に作図する手段、 (ト) 上記記憶した数値及び算出結果を逐次表示す
る手段、 (チ) 予定された温度範囲の測定が終了すればその
結果を印字する手段 とよりなることを特徴とする原子炉の減速材温度
係数測定装置。
[Scope of Claims] 1. A reactor reactivity meter, moderator average temperature meter, and control rod position indicator that converts the current obtained from a neutron flux detector installed in or near the reactor core into voltage to solve a dynamic characteristic equation. (a) means for detecting the position of the control rods, (b) means for detecting the reactivity of the reactor, (c) means for detecting the temperature of the moderator, and (d) the above control rods. (e) means for storing the position, reactivity, and moderator temperature as well as the design value of the Doppler temperature coefficient; A method for calculating an isotemperature coefficient by performing regression calculation from temperature, and calculating a moderator temperature coefficient from this isotemperature coefficient and Doppler temperature coefficient; (g) means for sequentially displaying the memorized numerical values and calculation results; and (h) means for printing the results when the measurement in the scheduled temperature range is completed. Furnace moderator temperature coefficient measuring device.
JP60199999A 1985-09-10 1985-09-10 Measuring device for temperature coefficient of moderator ofnuclear reactor Granted JPS6259899A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60199999A JPS6259899A (en) 1985-09-10 1985-09-10 Measuring device for temperature coefficient of moderator ofnuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60199999A JPS6259899A (en) 1985-09-10 1985-09-10 Measuring device for temperature coefficient of moderator ofnuclear reactor

Publications (2)

Publication Number Publication Date
JPS6259899A JPS6259899A (en) 1987-03-16
JPH0458913B2 true JPH0458913B2 (en) 1992-09-18

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Family Applications (1)

Application Number Title Priority Date Filing Date
JP60199999A Granted JPS6259899A (en) 1985-09-10 1985-09-10 Measuring device for temperature coefficient of moderator ofnuclear reactor

Country Status (1)

Country Link
JP (1) JPS6259899A (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR940007114B1 (en) * 1990-11-23 1994-08-05 한국원자력안전기술원 Reactor Physics Test Method Using Digital Reactivity Calculator
JP4607713B2 (en) * 2005-09-02 2011-01-05 日立Geニュークリア・エナジー株式会社 Moderator temperature coefficient positive / negative judgment method and positive / negative judgment device
JP5725792B2 (en) * 2010-10-25 2015-05-27 三菱重工業株式会社 Moderator temperature coefficient measuring device and moderator temperature coefficient measuring method
JP6139175B2 (en) * 2013-02-25 2017-05-31 三菱重工業株式会社 Reactivity temperature coefficient estimation apparatus and method

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS56120988A (en) * 1980-02-29 1981-09-22 Sumitomo Electric Industries Nuclear reactor signal processing device

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JPS6259899A (en) 1987-03-16

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