JPS6259899A - Measuring device for temperature coefficient of moderator ofnuclear reactor - Google Patents
Measuring device for temperature coefficient of moderator ofnuclear reactorInfo
- Publication number
- JPS6259899A JPS6259899A JP60199999A JP19999985A JPS6259899A JP S6259899 A JPS6259899 A JP S6259899A JP 60199999 A JP60199999 A JP 60199999A JP 19999985 A JP19999985 A JP 19999985A JP S6259899 A JPS6259899 A JP S6259899A
- Authority
- JP
- Japan
- Prior art keywords
- moderator
- temperature
- reactor
- reactivity
- temperature coefficient
- 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.)
- Granted
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- 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】
〈産業上の利用分舒〉
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。[Detailed Description of the Invention] <Industrial Application> The present invention relates to an apparatus used for measuring the moderator temperature coefficient, which is carried out as part of the core characteristic investigation carried out in nuclear reactor start-up tests, periodic tests, etc. It is something.
〈従来の技術〉
従来、原子炉反応度を求めろ一つの方法として、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。<Conventional technology> Conventionally, one method for determining the 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 to calculate the dynamic characteristic equation. The obtained reactivity is recorded on the Y axis of the XY record, and the temperature signal from the thermometer (moderator on the other X axis) is adjusted to the measurement temperature range. Connect and record things.
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へろ。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
て得られろものが等）温度係数とよ呼ばれ、減速材温度
係数とド・ソゴラ扁度係数が加算されたものである。Next, a method for determining the desired moderator temperature coefficient from the reactivity trace recorded in this manner will be described. Fourth
The figure shows the moderator temperature change (
This is the reactivity change (a) with respect to b), and the reactivity change accompanying the change in core moderator temperature is recorded as the slope of this trace. The value obtained from this slope as a change in reactivity per unit temperature is called the temperature coefficient, and is the sum of the moderator temperature coefficient and de Sogolla flatness coefficient.
従って目的とする減速材ｌ温度係数は、この等温度係数
からドッ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。Therefore, the desired moderator l temperature coefficient is determined by manually subtracting the Doppler temperature coefficient from this isotemperature coefficient.
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
。従って、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った。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 troublesome.
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。Processing work is also required to prepare the measured values in a predetermined recording format, Table 1.
（以下余白）
〈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
。(The following is a blank space) <Problems to be solved by the invention> In the prior art, moderator temperature coefficient measurement, which is determined by manual processing, requires a lot of trouble 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.
く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
（よ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
ると共にドップラ温度係数の設計値を記憶する手段、
（ポ）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
回帰計算を行って等温度係数を算出し、この等温度係数
とドップラ温度係数より減速材温度係数を算出する手段
、
（へ）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。Means for Solving the Problems> Therefore, the moderator temperature coefficient measuring device of the present invention converts the current obtained from the neutron flux detector installed in the reactor core (or near the reactor core) into a voltage to calculate the dynamic characteristic equation. Solve In a nuclear reactor equipped with a reactor reactivity meter, moderator average temperature meter, and 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 temperature of the moderator; (D) Means for storing the control rod position, reactivity and moderator temperature as well as the design value of the Doppler temperature coefficient; (P) Same control from the above storage means. Means for calculating an isotemperature coefficient by performing regression calculation from the reactivity and the moderator temperature at intervals where the temperature change of the moderator is equal at the rod position, and calculating a moderator temperature coefficient from the isotemperature coefficient and the Doppler temperature coefficient; (f) A means for continuously plotting the relationship between reactivity and moderator temperature on an XY recorder.
（ト）上記記憶した数値及び算出結果を逐次表示する手
段。(g) Means for sequentially displaying the stored numerical values and calculation results.
（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。(H) A means for printing the results once the measurement in the scheduled temperature range is completed.
〈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。<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.
第１図は本発明の測定装置の機能実現手段を示すブロッ
ク図、第２図は本発明測定装置の一実施例の構造を示す
ブロック図でＡの鎖線部分力９本発明の装置、第３図は
本発明測定装置による処理ステ、ツブを示すフローチャ
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。FIG. 1 is a block diagram showing the function realizing means of the measuring device of the present invention, and FIG. 2 is a block diagram showing the structure of one embodiment of the measuring device of the present invention. The figure is a flowchart showing the processing steps and tubes by the measuring device of the present invention, and FIG. 4 is a graph of the reactivity against moderator temperature drawn by the plotting device.
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。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.
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、減速材湿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ろ。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ェース５で
変換され、また制御棒位置指示計２の（３号はＡ／Ｄ変
換又はパルスカウンター６を通り、Ｉｌｏ、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、この引き抜キ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、以下の如きステップで処
理を行う。In addition, the control rod position is determined from the control rod position indicator 2 of the control rod drive device (not shown), and the moderator humidity is determined from the moderator average thermometer 3.
A signal is supplied to the apparatus of the present invention from. The signal of the moderator average thermometer 3 is converted by the A/D converter 4, the signal of the reactor reactivity meter 1 is converted by the serial interface 5, and the signal of the control rod position indicator 2 (No. 3 is an A/D converter). It passes through a conversion or pulse counter 6, and is supplied to the CPU 8 via Ilo and port 7.The control rod position indicator 2 has two types: 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, and pulse signals are transmitted independently at each time of withdrawal and insertion, and the pulses of this withdrawal and insertion are detected by a pulse counter. The position of the control rod is determined by integrating the pulses in step 6 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.
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
の温度変化中では直線状に変化するものであるため、微
小温度変化（００１℃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、該計算
値と、予め上記外部記憶装置１０に記憶されたドップラ
温度係数の設計値により減速材温度係数を算出ずろ。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 during a temperature change of about 2°C, so the temperature and reactivity are measured every minute temperature change (about 001°C), and the XY recorder is plotted. A diagram is drawn in the device 14, stored in the external storage device 10, and a regression calculation is performed, and the moderator temperature coefficient is calculated from the calculated value and the design value of the Doppler temperature coefficient stored in advance in the external storage device 10.
加えて、制御棒位置が測定中に変化した場合（、’！Ｉ
’１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
数の測定を可能にてきろ。処理結果は、測定開始後数点
のデータを採取すると逐次、′ｇ速速記温度係数表示装
置１２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。In addition, if the control rod position changes during the measurement (,'!I
(for neutron flux adjustment during 1st control), make it possible to measure the moderator temperature coefficient at the same control rod position by deleting the data during this period. The processing results are displayed on the shorthand temperature coefficient display device 12 as data is collected from several points after the start of the measurement, and when the specified measurement is completed, the measurement results as shown in Table 1 are printed out as before. Output to device 13. The processing procedure is shown in FIG. This figure shows a case where the control rod position indicator 2 emits pulses.
先ず、初期化２１の部分で、初期制御棒位置の更新を行
う。ステップ２２で微小温度が変化したかを判断し、Ｙ
ｅｓの場合、ステップ２３で制御棒位置が変わったこと
を判断する。ＮＯの場合ステップ２４で作図（第３図で
示せばジグザグの各測定点１４ａ）及び回帰計算（作図
は作図装置１４て、回帰計算はＣＰＵ８で行う）をし、
ステップ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。次にステップ２７で測定終
了かを判断し、ＹｅＳの場合ステップ２８て測定結果の
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１４ａを結
ぶ直線１４ｂ）を行う。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 Y
In the case of es, it is determined in step 23 that the control rod position has changed. In the case of NO, in step 24, plotting (each zigzag measurement point 14a shown in FIG. 3) and regression calculation (plotting is performed by the plotting device 14, and regression calculation is performed by the CPU 8),
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 drawn (printing is done by the printing device 13, drawing is done by the drawing device 14, and if the drawing is shown in FIG. 3, each measurement A straight line 14b) connecting the points 14a is performed.
ステ・ンプ２２でＮＯ又はステップ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（よ作図及び回帰計算処理を行わない。ステ
ップ２７で測定終了していない（Ｎｏ）場合、引き続き
ステップ２２に戻り繰り返す。If NO in step 22 or Yes in step 23, that is, if the moderator temperature does not change or the control rod position is changing (no plotting or regression calculation processing is performed.The measurement is not completed in step 27). If not (No), the process continues to return to step 22 and repeat.
〈発明の効果〉
思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。<Effects of the Invention> The nuclear reactor moderator temperature coefficient measuring device described in detail has the following effects.
■ 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。■ Real-time processing is performed, and design values and measured values can be compared immediately after the test is completed, which not only greatly reduces processing time, but also saves labor and improves the operating rate of the reactor.
■ 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。■ 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. I can do it.
■ 測定装置が小型化できろため、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。■ Since the measuring device can be made smaller, it can be used in test locations such as central control rooms. Therefore, it is possible to reduce the number of testers and data organizers.
第１図は本発明の減速材温度係数測定装置によろ機能実
現手段を示すブロック図、第２図は本発明測定装置の一
実施例の構造を示すブロック図、第３図は本発明測定装
置による処理ステップを示すフローチャー１・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ェース、
６ 、、、 Ａ ／ Ｄコンバーター又はパルスカウン
ター、７．１１ ・Ｉ１０ポート、８ ＣＰ Ｕ 。
９ 、、、 ＲＡ Ｍ、１０ 外部記憶装置、１２ 表
示装置、１３ 印字装置、
１４ 作図装置
特許出願人 三菱原子カニ業株式会社代理人 弁理士
佐 藤 英 昭
１４回
−Ａ逮右温度Fig. 1 is a block diagram showing the means for realizing the functions of the moderator temperature coefficient measuring device of the present invention, Fig. 2 is a block diagram showing the structure of an embodiment of the measuring device of the present invention, and Fig. 3 is the measuring device of the present invention. Flowchart 1/Figure 4 showing the processing steps according to
The figure is a graph of reactivity versus moderator temperature drawn with a plotter. 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 ・I10 port, 8 CPU. 9, RAM, 10 External storage device, 12 Display device, 13 Printing device, 14 Plotting device Patent applicant Mitsubishi Atomic Crab Industry Co., Ltd. Representative Patent attorney Hide Sato 1979-A arrest temperature
Claims (1)
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、 （ィ）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
ると共にドッ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って等温 度係数を算出し、この等温度係数とドップ ラ温度係数より減速材温度係数を算出する 手段。 （へ）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] A reactor reactivity meter, a moderator average temperature meter, and a control rod position indicator that convert the current obtained from a neutron flux detector installed in or near the reactor core into voltage to solve a dynamic characteristic equation. In the installed nuclear reactor, (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, (d) the position of the control rods mentioned above. , a means for storing the reactivity and moderator temperature as well as the design value of the Doppler temperature coefficient; Means for performing regression calculation to calculate an isotemperature coefficient, and calculating a moderator temperature coefficient from this isotemperature coefficient and the Doppler temperature coefficient. (f) Means for continuously plotting the relationship between reactivity and moderator temperature on an XY recorder; (g) Means for sequentially displaying the memorized values and calculation results; (h) Measurement within a scheduled temperature range. 1. A moderator temperature coefficient measuring device for a nuclear reactor, comprising means for printing the result upon completion of the measurement.
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 true JPS6259899A (en) | 1987-03-16 |
| JPH0458913B2 JPH0458913B2 (en) | 1992-09-18 |
Family
ID=16417112
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) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06207997A (en) * | 1990-11-23 | 1994-07-26 | Korea Atomic Power Safety & Technol | Reactor-core physical testing device of nuclear reactor using digital reactivity computer system |
| JP2007064946A (en) * | 2005-09-02 | 2007-03-15 | Hitachi Ltd | Method and device for determining positive/negative of moderator temperature coefficient |
| JP2012093140A (en) * | 2010-10-25 | 2012-05-17 | Mitsubishi Heavy Ind Ltd | Temperature coefficient measuring apparatus and temperature coefficient measuring method for moderator |
| JP2014163803A (en) * | 2013-02-25 | 2014-09-08 | Mitsubishi Heavy Ind Ltd | Reactivity temperature coefficient estimation device and method |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56120988A (en) * | 1980-02-29 | 1981-09-22 | Sumitomo Electric Industries | Nuclear reactor signal processing device |
-
1985
- 1985-09-10 JP JP60199999A patent/JPS6259899A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56120988A (en) * | 1980-02-29 | 1981-09-22 | Sumitomo Electric Industries | Nuclear reactor signal processing device |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06207997A (en) * | 1990-11-23 | 1994-07-26 | Korea Atomic Power Safety & Technol | Reactor-core physical testing device of nuclear reactor using digital reactivity computer system |
| JP2007064946A (en) * | 2005-09-02 | 2007-03-15 | Hitachi Ltd | Method and device for determining positive/negative of moderator temperature coefficient |
| JP2012093140A (en) * | 2010-10-25 | 2012-05-17 | Mitsubishi Heavy Ind Ltd | Temperature coefficient measuring apparatus and temperature coefficient measuring method for moderator |
| JP2014163803A (en) * | 2013-02-25 | 2014-09-08 | Mitsubishi Heavy Ind Ltd | Reactivity temperature coefficient estimation device and method |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0458913B2 (en) | 1992-09-18 |
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