JPS5957193A - Automatic operation device for control rod - Google Patents
Automatic operation device for control rodInfo
- Publication number
- JPS5957193A JPS5957193A JP57167878A JP16787882A JPS5957193A JP S5957193 A JPS5957193 A JP S5957193A JP 57167878 A JP57167878 A JP 57167878A JP 16787882 A JP16787882 A JP 16787882A JP S5957193 A JPS5957193 A JP S5957193A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- control
- reactor
- output
- operator
- 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
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
- Transplanting Machines (AREA)
- Load-Engaging Elements For Cranes (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】
〔発明の技術分野１
本発明は、制御棒操作を自動的に行なうことのできる制
御棒自動操作装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention 1] The present invention relates to an automatic control rod operation device that can automatically operate control rods.
［発明の技術的背碩］
一般に、制御棒操作時には、操作シーケンスの記載され
たノートを所持したオペレータと制御棒操作用のオペレ
ータとがペアとなり、制御棒操作シーケンスの記載され
たノートを持ったＡ−ペレータが操作制御棒を指示し、
これに基づい（他／ｊのオペレータが操作盤より制御棒
を操作することが、行われている。[Technical background of the invention] Generally, when operating a control rod, an operator who has a notebook in which the operation sequence is written and an operator for controlling the control rod are paired, A-Perator directs the operating control rod,
Based on this, the operator of (other/j) operates the control rod from the operation panel.
制御棒操作値が特に多いのは原子炉を起動あるいは停止
Ｊる場合Ｃあり、原子炉を起動する場合には原子炉臨界
までに約２５％、また鎚電機併入までに約５０％以上の
制御棒が引抜かれる。そして一般に制御棒操作にあたつ
℃は種々の制限条件が課Ｕられ°Ｃいる。The control rod operation value is especially large when starting or stopping a nuclear reactor.When starting a reactor, the control rod operation value is about 25% until the reactor reaches criticality, and about 50% or more before the addition of Tsui Electric. The control rod is pulled out. In general, various limiting conditions are imposed on the temperature at which control rods are operated.
すな４つら臨界前ぐあれば中性子束レベルの上昇率を表
わすペリオドがある一定ｔｉｎを越えないことが必要で
あり、臨界後には炉水温度上昇率が予め定められたｌｉ
、ｉ以下であること、中性子束に合せて１８Ｍレンジの
切換えを実施すること等が必要である。In other words, before criticality, it is necessary that the period, which represents the rate of increase in the neutron flux level, does not exceed a certain level, and after criticality, the rate of increase in reactor water temperature must be li, which is determined in advance.
, i or less, and it is necessary to switch the 18M range according to the neutron flux.
従って、一般に起動時には、オペレータはこれらのｍを
監視しながら順次制御棒を引き抜いＣいくことが必要ぐ
あり、またこの間に種々の補機を原子炉の状態に沿つ【
起動していく必要があり、原子炉起動時のオペレータの
作業量は非常に多く、現在は最小３人程度のオペレータ
が必要である。Therefore, during startup, it is generally necessary for the operator to sequentially withdraw the control rods while monitoring these m, and during this time, adjust various auxiliary equipment according to the reactor status.
The amount of work required by operators during reactor startup is extremely large, and currently a minimum of three operators are required.
同様のことは原子炉停止１時にもいうことができる。The same thing can be said about the first hour of reactor shutdown.
なお発電機俳人が完了し、炉出力が２０％稈度まＣ゛上
貸ツるど、原子炉プラントまわりの種々の捕１爽の操作
はなくなるが、制御棒引抜きによりざｔ生づる局所的な
出力上昇偵が増大するので、制御棒引抜き自身にオペレ
ータは神経を使う必要が生じＣくる。Furthermore, once the generator output is completed and the reactor output is increased to 20% culm C, there will be no need for various recovery operations around the reactor plant, but there will be local disruptions caused by the withdrawal of the control rods. As the power output increases, the operator will have to be careful when withdrawing the control rods.
このように、制御棒操作にあたって考慮すべき制限条件
は原子炉出力レベルにより大ぎく異なっている。As described above, the limiting conditions that should be considered in control rod operation vary greatly depending on the reactor power level.
′？ｊなわち、原子炉起動１１７や停止時等の原子炉出
ノコレベルの低い時点では、炉水温度変化率等のポイン
１〜量の制限値を満足すればよく、この制限が満足され
ない場合には制御棒操作の速度を減少することによりこ
の制限を解決することができる。′? In other words, at times when the reactor outlet level is low, such as during reactor startup 117 and shutdown, it is sufficient to satisfy the limit values of point 1 to amount such as the rate of change in reactor water temperature, and if this limit is not satisfied, This limitation can be overcome by reducing the speed of control rod operations.
−ｈ１原子炉出力レベルが高い場合には、制御棒操作に
よる局所的な出力分布変化や炉心安定性といった出力分
布に依存する要素に注薫する必要があるが、これらが決
められた制限条件を満足しないとしても単に操作時間を
理らぜるだけでこれらの制限を緩和りることは困難であ
る。-h1 When the reactor power level is high, it is necessary to pay attention to factors that depend on the power distribution, such as local power distribution changes due to control rod operation and core stability, but these must meet the predetermined limiting conditions. Even if these limitations are not satisfied, it is difficult to alleviate these limitations simply by adjusting the operation time.
すなわちこのような場合には、オペレータは問題となる
制限条件に対応して予め定められた制御棒操作シーケン
スを実行した後、改め′（所定の制御棒操作を実行する
ことになる。従っンオペレータは予定どうり制御棒を操
作°リベきか、このまま制御棒操作をしばらく中！ｇｉ
ずべきか、変更用制御棒シーケンスを実行Ｊべさか等を
常に選択し、この選択に阜づきそれを実行する必要があ
る。In other words, in such a case, the operator executes a predetermined control rod operation sequence corresponding to the limiting conditions in question, and then performs the predetermined control rod operation again. I will operate the control rod as planned.I will continue to operate the control rod for a while!gi
It is necessary to always select whether to change the control rod sequence or execute the change control rod sequence, etc., and execute it based on this selection.
「費用技術の問題点」
以上述べたように、一般に制御棒操作にあたっては、低
出力領域と高出力領域においＣ２つの問題点が存在する
。"Problems with cost technology" As mentioned above, there are generally two problems in control rod operation, one in the low-power region and the other in the high-power region.
りなわち低出力領域においては、制御棒操作量が非７１
−に多く、他の補機の操作ｍ等も多いため、この時点に
オペレータの操作が集中りるｔｃめオペレータとして多
数の人間が必要であり、また高出力領域においては、制
御棒操作による局所的な出力変化が大きく炉心状態の変
化が人ぎいためオペレータが制御棒操作に非常に神経を
使うという問題がある。In other words, in the low power region, the control rod operation amount is
-, and there are many operations of other auxiliary equipment, etc., so a large number of people are required as tc operators, where operator operations are concentrated at this point.In addition, in high power areas, local control rod operations are required. The problem is that operators have to be very careful when operating the control rods because the power output changes are large and the reactor core conditions change easily.
［発明の目的］
本発明はかかる従来の事情に対処しＣなされたしのぐ、
例えば低出力時にはオペレータの操作量を軽減し、高出
力時にはオペレータの操作量と精神的な負担を軽減づる
ことのできる制御棒自動操作装置を捉供しようとするも
のである。[Object of the invention] The present invention addresses and overcomes the conventional circumstances,
For example, an attempt is made to provide an automatic control rod operating device that can reduce the amount of operator operation when the output is low, and reduce the amount of operation and mental burden on the operator when the output is high.
［発明の概要］
す“なわち本発明は、オペレータから入力された運転６
１画に阜づき制御棒を操作した場合の炉心状態を予測ム
１樟し、この予測計算結果が運転上の制限条件を満たし
くいる場合に制御棒を自動操作することを特徴とする制
御棒自動操作装置である。[Summary of the Invention] In other words, the present invention
A control rod that predicts the state of the reactor core when the control rod is operated in one stroke, and automatically operates the control rod if the predicted calculation result satisfies operational constraints. It is an automatic operating device.
［発明の実施例］
以下木Ｒ明の詳細を図面に示す一実施例につい（説明す
る。[Embodiment of the Invention] An embodiment of the invention will be described below in detail with reference to the drawings.
図においＣ一点鎖線で囲まれた部分は現行の制御棒操作
モジュールを示ずもので、この制御棒操作モジ１−ルで
は、オペレータは制御棒監視操作装置１に制御棒の引抜
きあるいは挿入の要求信号を人力する。In the figure, the part surrounded by the dashed line C does not show the current control rod operation module. Human-powered signals.
この４５１号はプラント状態に関３１１！−する種々の
情報を収集しＣなる制御棒操作補助装置２に出力され、
この制御棒操作補助装置２により制御棒の挿入あるいは
引抜きが許１Ｉｌｌされるものであるがが判Ｗｉされる
。そして、この制御棒操作補助装置２は制御棒の挿入あ
るいは引抜きがｉす能であると判断した時には、オペレ
ータの入力に対応した制御棒駆動信号を制御棒駆動補助
装置３に出ツノし、−まｊこ制御棒操作を許容Ｃぎない
と判断した場合には、制御棒監視操作装置１にその旨を
出力する。制御棒駆動信号を人力した制御棒駆動補助装
置３【よ選択された制御棒に対応する水圧駆動ユニット
の弁制御信号を制御ｌｌ棒駆動装置４に出力し、この結
果、原子炉５の該当する水１１駆動二ｌニットの弁が変
化し、制御棒駆動水が流れ制御棒位置が変更される。This issue 451 is about 311! - collects various information and outputs it to the control rod operation auxiliary device 2 called C,
It is determined that the control rod operation assisting device 2 allows insertion or withdrawal of the control rod. When the control rod operation auxiliary device 2 determines that the control rod can be inserted or withdrawn, it outputs a control rod drive signal corresponding to the operator's input to the control rod drive auxiliary device 3, and - If it is determined that the control rod operation is not permissible, a notification to that effect is output to the control rod monitoring and operation device 1. The control rod drive auxiliary device 3 which manually outputs the control rod drive signal outputs the valve control signal of the hydraulic drive unit corresponding to the selected control rod to the control rod drive device 4, and as a result, the valve control signal of the hydraulic drive unit corresponding to the selected control rod is outputted to the control rod drive device 4. The valve of the water 11 drive unit changes, and the control rod drive water flows and the control rod position is changed.
この制御棒位置の変化は制御棒位１１り検出′ＪＡｉ！
（６内に配設される位置指示プローブ内のリードスイッ
チにより検出され、この制御棒位置検出装置６から各制
御棒に対応する位置指示プローブ信号が制御棒位置伝送
補助装聞７に出力され、この制御棒位置伝送補助袋ａ７
により制御棒パターンが求められる。This change in control rod position is detected by control rod position 11'JAi!
(Detected by a reed switch in the position indicating probe disposed in the control rod position detecting device 6, a position indicating probe signal corresponding to each control rod is output from the control rod position detecting device 6 to the control rod position transmission auxiliary equipment 7, This control rod position transmission auxiliary bag A7
The control rod pattern is determined by
この制御棒パターンを示’Ｊ’ （ｉｔｉ号【よ制御棒
位置指示装置Ｅ３に出力され、この制御棒位置相承装置
８Ｃ表小用信号に変換された後、制御棒監視操作装置１
に出力され、制御棒パターンが制御棒ＩＬｉ視操作装置
１に表示される。This control rod pattern is output to the control rod position indicating device E3, and after being converted into a signal for the control rod position indicating device 8C, the control rod monitoring and operating device 1
The control rod pattern is displayed on the control rod ILi visual operation device 1.
図の一点鎖線で囲まれた部分の左側は本発明の一実施例
の制御棒自動操作装置を示してａ３す、この制御棒自動
操作装置は入力装置９、総合判断装置百１０、長期予測
装置１１、短期予測装置１２、出力装置１３、制御棒選
択操作確認装置１４、炉心状態監祝装圓１５およびデー
タフアイル１６とから主体部分が構成されている。The left side of the part surrounded by the dashed line in the figure shows an automatic control rod operating device according to an embodiment of the present invention. 11, a short-term prediction device 12, an output device 13, a control rod selection operation confirmation device 14, a core state monitoring device 15, and a data file 16.
’Ｊ ／ｃ、’Ｃわら人力装置９はＡペレータから運転
４画、自動運転要求、ブレークポイン１〜設定値、出力
Ｊ＞よび炉心流量変化、中１１ｉ要求、再開要求、予測
要求等をへカタる。'J/c, 'C straw human power equipment 9 sends 4 operation strokes, automatic operation request, break point 1 to set value, output J> and core flow rate change, intermediate 11i request, restart request, prediction request, etc. from A pelleter. Kataru.
総合判断装置１ツ１０は人ツノ装置６９に入力された運
転計画を入力し、まずこの運転計画に基づいて長期ｒ測
装櫛１′１にブレークポイントまでの長期予測を実行さ
け°る。The comprehensive judgment device 1 10 inputs the driving plan inputted into the human horn device 69, and first, based on this driving plan, causes the long-term measurement comb 1'1 to execute long-term prediction up to a break point.
長期予測装置６１１は総合判断装置１０がら運転６１画
を人力し炉心内の出力分布あ゛るい（、ｌＬ出力レベル
の長期的な変化を、物３．１１！ ［デルに基づく核熱
水力ｈ１算プ１」グラム、例えばＪ１Δ、Ｗｏｏｌｅｙ
１Ｔｂｒｅｃ ［） ｉ ｍｃｎｓｉｏｎａｌ
Ｂ Ｗ ＲＣｏｒｅ Ｓ ｉｍｕｌａｔｏｒ、 Ｇ
ｅｎｅｒａｌ Ｅ １ｅｃｔｒｉｃ Ｃｏ
、 ｌｌ−１ｃｃｎｓｉｎ丁ｏｐｉｃａｌ Ｒｅ
ｐｏｒｔ 、 ｆｖｌａｙ １９７６ （Ｎ Ｅ Ｄ
Ｏ−２０９５３）にゼノン変動を考慮したモデルで実施
りる。このどき、炉心内の燃料の核特性を評価するため
に燃料の燃焼亀分布などの変数、あるいはこれに基づく
核特性ｉｒｌ ｔ’、１に必要な燃料の特性から定まる
定数が必要となるが、これらのデータはデータ７ノ・イ
ル１６から人力される。The long-term prediction device 611 manually performs the operation 61 steps from the comprehensive judgment device 10 and predicts the long-term changes in the output level of the power distribution within the reactor core. Arithmetic 1'gram, e.g. J1Δ, Wooley
1Tbrec [) i mcnsional
B W RCore Simulator, G
eneral E 1 electric Co
, ll-1ccnsinchopical Re
port, fvlay 1976 (NED
O-20953) using a model that takes into account Zeno fluctuations. Nowadays, in order to evaluate the nuclear characteristics of the fuel in the reactor core, variables such as the combustion curve distribution of the fuel, or constants determined from the fuel characteristics necessary for the nuclear characteristics irl t',1 based on this, are required. These data are manually input from Data 7 No. 16.
長期予測装置１１ぐ計障された長期予測は出力装置１３
に出力され、Ａベレータはこの出力装置１３に出力され
た長期予測に基づき自動運転が可能であると判断した場
合には、人力装置９に自動運転を要求する。The long-term prediction that has been detected by the long-term prediction device 11 is sent to the output device 13.
If the A-bellator determines that automatic operation is possible based on the long-term prediction output to the output device 13, it requests the human-powered device 9 to perform automatic operation.
この自動運転要求信ぢは人力装置９から総合判１１１ｉ
’）ムｉｉ’ｉ １０に出力され、総合判断装置１０
は制御捧位１６指示装置ε３から現状の制御棒パターン
を入力し、この制御棒パターンと運転翳１画に基づく制
御棒操作シーケンスとを比較し、現状の制御棒パターン
のシーケンス上での位置を定め、シーケンス上で操作予
定制御棒を見出し、これを操作した場合の炉心状態変化
を短期予測装置１２に予測計１ンさける。This automatic driving request signal is sent from the human power device 9 to the general format 111i.
') muii'i 10, and is output to the comprehensive judgment device 10.
inputs the current control rod pattern from the control orientation 16 indicating device ε3, compares this control rod pattern with the control rod operation sequence based on one stroke of the driving picture, and determines the position of the current control rod pattern on the sequence. Then, the control rods scheduled to be operated are found on the sequence, and the short-term prediction device 12 is used to predict changes in the core state when the control rods are operated.
短期予測装置１２は、この予測閉枠に必要な情報をデー
タフＩイル１６から入力（データの内容は、長期予測装
置１１で必要どされるものと本質的に同一である。）し
、短期予測を行なう。なお、このり、０期予測内容は起
動時、出力運転１１．１、炉心状態等によりそれぞれ異
なっている。The short-term prediction device 12 inputs the information necessary for this prediction frame from the data file 16 (the content of the data is essentially the same as that required by the long-term prediction device 11), and makes the short-term prediction. Do the following. Note that the contents of the 0-period prediction differ depending on the startup, power operation 11.1, core state, etc.
すなわら、未臨界１１ｆｆにはペリオド、未臨界庶等が
、運転モードスイッチが「起動」である出力上背１１）
には、炉水温度上胃率等が、運転−し−ドスイッヂが「
運転」である通常運転時には安定性、１〕Ｃ１ンベＬ１
−ブ余裕、Ｍ ＣＰ Ｒマージン等がそれぞれ予■り計
綽される。In other words, the subcritical 11ff has period, subcritical, etc., and the output upper back 11) whose operation mode switch is set to "start"
In this case, the reactor water temperature, upper gas rate, etc. are determined by the operating switch.
Stability during normal operation, 1) C1 engine L1
- B margin, MCPR margin, etc. are calculated in advance.
短期予測装置１２は、この短期予測８１綽結果にＪニド
つき、予定制御棒が操作−り能と判断した場合には、制
御棒操作確認信号を制御棒選択操作確認装置１４に出力
Ｊる。また短期予測装置１２は短期予測結果が運転上の
制限を渦妃しＣいないと判Ｗ１した場合には、下記のよ
うな操作をｔｊなう。The short-term prediction device 12 outputs a control rod operation confirmation signal to the control rod selection operation confirmation device 14 when it determines that the scheduled control rod is operable. Further, when the short-term prediction device 12 determines that the short-term prediction result does not exceed the driving restrictions, it performs the following operations.
ず入わち、未臨界時および出力上賃時には、制御棒操作
を中［θｉあるいは操作間隔をあ番）ることでこれに対
応する。In other words, during sub-criticality and output increase, this is handled by controlling the control rods in the middle (θi or the operation interval).
−ｈ、通常運転時には、制御棒操作の中断あるいは操作
間隔をあけることでは容易にこの制限条件を逃れること
ができない。従って、この短期予測装置１２は安定性、
ＰＣＣエンペ−ブ余裕、ＭＣＩ） Ｒマージン等にそれ
ぞれ対応して予め定められたｑ！ｒ ＩＡ制制御操作シ
ーケンスにＪ、り制υ１１棒の操作を行なう。-h. During normal operation, this limiting condition cannot be easily escaped by interrupting control rod operations or increasing the interval between control rod operations. Therefore, this short-term prediction device 12 has stability,
PCC empa- margin, MCI) q! predetermined corresponding to R margin, etc. r In the IA control control operation sequence, perform the operation of J, control υ11 rod.
ＩＪ Ｊ３、この特殊制御棒操作シーケンスのステップ
は最小限に保たれ、できるだけ速い段階ｒ元に戻される
。IJ J3, the steps of this special control rod operation sequence are kept to a minimum and reversed as quickly as possible.
制御棒選択操作確認装置１／Ｉは短期予測装置１２から
制御棒操作（ｉｆｃ詐信列信号力し、制御棒操作補助装
置２に制御棒操作信号を出力する。口の制御４仝操作（
ｅζ２」の制御棒操作補助装置２への人力により、前述
したＪ、うにしく１京子炉５の制御棒が操作され、制御
棒位置指示袋間８の制御棒位ｊ（が変化Ｊるが、制御棒
選択操作確認装置１４は制御棒誤操作］Ｊ（装置ε３か
ら制御Ｉ棒位置化号を人力し、制御棒が実際に操作され
たことを確認する。The control rod selection operation confirmation device 1/I inputs a control rod operation (ifc false train signal) from the short-term prediction device 12 and outputs a control rod operation signal to the control rod operation auxiliary device 2.
The control rods of the above-mentioned J, 1 Kyoko reactor 5 are operated by human power to the control rod operation auxiliary device 2 of ``eζ2'', and the control rod position j (between the control rod position indicating bags 8 changes). The control rod selection operation confirmation device 14 confirms that the control rod was actually operated by manually inputting the control I rod positioning signal from the device ε3.
炉心状態監視装置１５は原子炉Ｅ３から炉心状態を示す
各種（Ａ号を入力し、制御棒操作が完了した炉心状態を
監視し、この炉心状態が所定の制限条件を満たしＣいる
かどうかを監視づ”る。この監視結果は総合判Ｉｌ？′
ｉ装置１０に出力される。The core condition monitoring device 15 receives various inputs (A) indicating the core condition from the reactor E3, monitors the core condition after control rod operation is completed, and monitors whether the core condition satisfies predetermined limiting conditions. ``Is this monitoring result a comprehensive judgment?''
It is output to the i-device 10.
なお、この炉心状態監視装置１５で監視された炉心状態
が制限条件を満たしでいない場合には、未臨界時ｄ）よ
び出力上４時には制御棒操作の中断あるいは操作間隔を
あ【プることＣ対応が可能であり、また通畠゛運転時に
は前述した特殊制御棒操作シークンスに従い操作される
。Note that if the core condition monitored by this core condition monitoring device 15 does not satisfy the limiting conditions, control rod operations may be interrupted or the operation interval may be shortened at subcritical times d) and when the output level is 4. The control rod can be operated according to the above-mentioned special control rod operation sequence during continuous operation.
［発明の効果１
以上述べたＪ、うに本発明の制御棒自動操作装置によれ
ば、運転６１画に従い制御棒が自動操作されるため、特
に原子炉起動時ａ３よび停止時におけるオペレータの制
御棒操作を大幅に減少することができる。[Effects of the Invention 1] According to the automatic control rod operation device of the present invention described above, the control rods are automatically operated according to the 61 operation strokes, so that the operator's control rods are not affected particularly during reactor startup a3 and shutdown. Operations can be significantly reduced.
また通常運転１１、冒こは制御棒操作に伴うオペレータ
の精神的な負担を大幅に軽減することができる。In addition, during normal operation 11, the mental burden on the operator associated with control rod operation can be significantly reduced.
従ってオペレータの制御棒誤操作は低減し、スクラム、
燃料破損等の可能性を大幅に低減り゛ることができる。Therefore, the operator's control rod misoperation is reduced, scram,
The possibility of fuel damage etc. can be significantly reduced.
図は本発明の一実施例の制御棒自動操作装置を示（ブロ
ック図である。
９・・・・・・・・・・・・人力装置
１０・・・・・・・・・・・・総合判断装置１１・・・
・・・・・・・・・長期予測装置１２・・・・・・・・
・・・・短期予測装置１３・・・・・・・・・・・・出
力装置４１４・・・・・・・・・・・・制御棒選択操作
確認装置１５・・・・・・・・・・・・炉心状態監視装
置占１６・・・・・・・・・・・・〕〕゛−タノアイル
ー５The figure shows an automatic control rod operating device according to an embodiment of the present invention (it is a block diagram). 9......Manual power device 10... Comprehensive judgment device 11...
......Long-term prediction device 12...
... Short-term prediction device 13 ...... Output device 414 ...... Control rod selection operation confirmation device 15 ......・・・・Core condition monitoring device 16・・・・・・・・・・・・〕゛-Tano Airu 5
Claims (1)
棒を操作した場合の炉心状態を予測上１棹し、この予測
８１紳結果が運転上の制限条件を満たしている場合に制
御棒を自動操作りることを特徴どりる制御棒自動操作装
置。(1) Predict the core state when the control rods are operated based on the operation plan input by the operator, and automatically operate the control rods if the predicted result satisfies the operational constraints. A control rod automatic operating device characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57167878A JPS5957193A (en) | 1982-09-27 | 1982-09-27 | Automatic operation device for control rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57167878A JPS5957193A (en) | 1982-09-27 | 1982-09-27 | Automatic operation device for control rod |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5957193A true JPS5957193A (en) | 1984-04-02 |
Family
ID=15857750
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57167878A Pending JPS5957193A (en) | 1982-09-27 | 1982-09-27 | Automatic operation device for control rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5957193A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62180293A (en) * | 1986-02-04 | 1987-08-07 | 株式会社東芝 | Method and device for automatically operating control rod ofnuclear power plant |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4935791A (en) * | 1972-08-09 | 1974-04-02 | ||
| JPS49104093A (en) * | 1973-02-12 | 1974-10-02 | ||
| JPS53123793A (en) * | 1977-04-04 | 1978-10-28 | Hitachi Ltd | Input reaction degree restricting apparatus |
-
1982
- 1982-09-27 JP JP57167878A patent/JPS5957193A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4935791A (en) * | 1972-08-09 | 1974-04-02 | ||
| JPS49104093A (en) * | 1973-02-12 | 1974-10-02 | ||
| JPS53123793A (en) * | 1977-04-04 | 1978-10-28 | Hitachi Ltd | Input reaction degree restricting apparatus |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62180293A (en) * | 1986-02-04 | 1987-08-07 | 株式会社東芝 | Method and device for automatically operating control rod ofnuclear power plant |
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