JPS59116086A - Automatic power control device for reactor - Google Patents

Automatic power control device for reactor

Info

Publication number
JPS59116086A
JPS59116086A JP57225842A JP22584282A JPS59116086A JP S59116086 A JPS59116086 A JP S59116086A JP 57225842 A JP57225842 A JP 57225842A JP 22584282 A JP22584282 A JP 22584282A JP S59116086 A JPS59116086 A JP S59116086A
Authority
JP
Japan
Prior art keywords
reactor
neutron
output
detector
power control
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
JP57225842A
Other languages
Japanese (ja)
Inventor
中根 雅彦
岩崎 敏夫
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 JP57225842A priority Critical patent/JPS59116086A/en
Publication of JPS59116086A publication Critical patent/JPS59116086A/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

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】 〔発明の利用分野〕 本発明は、中性子束を計測して自動的に原子炉出力を制
御する原子炉自動出力制御方式に係シ、特に、中性子束
検出器の単一故障による原子炉出力変動を防止するに好
適な原子炉自動出力制御装置に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to an automatic reactor power control system that measures neutron flux and automatically controls the reactor output, and in particular, relates to a method for automatically controlling the reactor output by measuring neutron flux, and in particular, to a method for automatically controlling the reactor output by measuring neutron flux. The present invention relates to an automatic reactor power control device suitable for preventing fluctuations in reactor power due to a single failure.

〔従来技術〕[Prior art]

原子炉の出力制御は、原子炉固有の特性を利用して行な
われている。軽水沸騰型原子炉では、炉心内の制御棒位
置の調整と原子炉へ冷却材を強制循環させる再循環系の
流量調整により、′また軽水加圧型原子炉では炉心内の
制御棒位置の調整と原子炉冷却材中リボロン濃度調整に
より、また重水減速軽水沸騰型原子炉では炉心内の制御
棒位置の調整と重水中のボロン濃度調整により行われる
Nuclear reactor output control is performed by utilizing the unique characteristics of a nuclear reactor. In light water boiling reactors, the control rod position within the reactor core is adjusted and the flow rate of the recirculation system that forcibly circulates coolant to the reactor is adjusted. This is done by adjusting the concentration of riboron in the reactor coolant, and in heavy water-moderated light water boiling reactors, by adjusting the position of control rods in the reactor core and adjusting the boron concentration in heavy water.

上記の原子炉出力制御を自動的に行う場合には、原子炉
出力を測定する手段が必要であシ、通常、複数個の中性
子検出器が便用されている。中性子検出器は、その測定
精度を向上させるために、軽水沸騰m原子炉あるいは重
水減速型原子炉では、炉心内に配置され、複数個の中性
子検出器の信号を平均することで原子炉出力モニタとし
ている。
In order to automatically perform the above-mentioned reactor power control, a means for measuring the reactor power is required, and a plurality of neutron detectors are usually used. In order to improve measurement accuracy, neutron detectors are placed inside the reactor core in light water boiling m reactors or heavy water moderation reactors, and are used to monitor reactor output by averaging the signals of multiple neutron detectors. It is said that

上記の原子炉出力モニタを原子炉自動出力制御装置に使
用する場合の代表構成例を第1図に示す。
FIG. 1 shows a typical configuration example when the above reactor output monitor is used in an automatic reactor output control system.

炉内に設置された複数個の中性子検出器1、中性子増幅
器2の出力信号は、平均回路3に入力し、平均して原子
炉出力を測定する。A系、B系と2つの出力モニタを独
立に設置するのは、原子炉出力モニタの信頼性を向上さ
せるためである。平均回路の出力は、入力バッファ4、
高値優先回路5全通して、制御棒駆動制御回路6に入力
される。
Output signals from a plurality of neutron detectors 1 and neutron amplifiers 2 installed in the reactor are input to an averaging circuit 3 and averaged to measure the reactor output. The reason why two output monitors, A system and B system, are installed independently is to improve the reliability of the reactor output monitor. The output of the averaging circuit is input to the input buffer 4,
The entire high value priority circuit 5 is inputted to the control rod drive control circuit 6.

上記の原子炉自動出力制御装置においては、単一の中性
子検出器が故障で信号が低側へ変動する場合は、高値優
先回路5によ多原子炉出力変動に継がることはないが、
高側に変動する場合には、制御棒を自動挿入して原子炉
出力を変動させることとなっている。
In the automatic reactor power control system described above, if a single neutron detector fails and the signal fluctuates to the low side, the high value priority circuit 5 prevents the signal from fluctuating to the multiple reactor power fluctuation.
If the power fluctuates to the high side, control rods are automatically inserted to vary the reactor output.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、中性子束検出器で原子炉出力をモニタ
することによ多原子炉出力を制御する原子炉自動出力制
御方式に関して、中性子束検出器の単一故障による中性
子束信号の変化を検知して原子炉出力制御を自動から手
動に切換え、原子炉出力変動を未然に防止する手段を提
供することにある。
The present invention relates to an automatic reactor power control system that controls multiple reactor power by monitoring the reactor power with a neutron flux detector, and the purpose of the present invention is to prevent changes in the neutron flux signal due to a single failure of the neutron flux detector. The object of the present invention is to provide a means to detect and switch reactor output control from automatic to manual, thereby preventing fluctuations in reactor output.

〔発明の概要〕 原子炉出力変動に継がる中性子束検出器の単一故障にお
いては、当該の検出器からの出力信号のみが高を示すの
で、他の正常な検出器の出力信号との比較監視がなされ
るならば、故障を検知することが可能であシ、特に中性
子移動面積が炉心に比して大きい重水炉等では、通常時
検出信号が相互に追随して変化する隣接の検出器間で比
較監視紫行なうことによシ確実に検知できるとの考え方
に基づき、各検出器の出力信号の変化前の・1ハ号値に
対する変化時の変化の割合を監視し、比較することによ
り、検出器の故障を検知し、原子炉出力変動を未然に防
止するものである。
[Summary of the invention] In the case of a single failure of a neutron flux detector following fluctuations in the reactor output, only the output signal from the relevant detector shows a high level, so comparison with the output signals of other normal detectors is required. If monitoring is performed, it is possible to detect failures. Especially in heavy water reactors, etc., where the neutron movement area is large compared to the reactor core, detection signals of adjacent detectors whose detection signals normally change following each other can be detected. Based on the idea that detection can be achieved reliably by performing comparative monitoring between , which detects detector failures and prevents fluctuations in reactor output.

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

以下、本発明の一実施例を第2図によシ説明する。中性
子束信号変化を比奴する中性子束検出器は、検出信号が
可能な限9同様の変化を示す様な検出器相互間で比較が
なされるよう選定して、中性子束検出器故障による検出
信号の変化と、故障によるのではない真の原子炉出力変
化による検出信号の変化とkg別する。第2図は、近接
する2個の中性子束検出器ごとVC1比較監視する場合
であシ各中性子束検出器に対し、−次遅れ回路11゜1
2、偏差計算回路13,14、演算回路15゜16が全
く同様に設置され、選定された2個の検出器間で、中性
子束信号変化率が比較回路によシ比較される。
An embodiment of the present invention will be explained below with reference to FIG. Neutron flux detectors that compare changes in neutron flux signals are selected in such a way that comparisons are made between detectors whose detection signals show similar changes to the extent possible, and detection signals due to neutron flux detector failures are selected. kg is distinguished from the change in the detection signal due to a true change in reactor output that is not due to a failure. Figure 2 shows a case where VC1 is compared and monitored for each of two adjacent neutron flux detectors.
2. The deviation calculation circuits 13, 14 and calculation circuits 15 and 16 are installed in exactly the same way, and the comparison circuit compares the rate of change of the neutron flux signal between the two selected detectors.

一方の中性子束検出器1の単一故障によシ異常高信号X
′が出力されるとこの異常高信号は一次遅れ回路11を
介して遅れ時間の期間だけ出力される故障直前の信号X
との偏差(変化幅)(X′−x)が偏差計算回路13で
計算される。この変ば、原子炉出力制御装置内のA/M
ステーション7へ指令を発し、自動制御を手#J割@1
に切換える。
Abnormally high signal X due to a single failure of one neutron flux detector 1
' is output, this abnormally high signal becomes the signal X just before the failure, which is output for the delay time period via the first-order delay circuit 11.
The deviation (change width) (X'-x) from the above is calculated by the deviation calculation circuit 13. If this change occurs, the A/M in the reactor power control device
Issue command to station 7 and start automatic control #Jwari@1
Switch to

〔発明の効果〕〔Effect of the invention〕

本発明によれば、中性子検出器の単一故障を監視して、
これによる原子炉出力変動を防止することができ、原子
炉出力制御の安定化、信頼性向上に大きくを与すること
ができる。
According to the invention, by monitoring a single failure of a neutron detector,
Fluctuations in the reactor output due to this can be prevented, and this can greatly contribute to stabilizing reactor output control and improving reliability.

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

第1図は従来の原子炉自動出力制御回路の構成図、第2
図は選定された各2個の中性子検出器に対して設けられ
る、中性子信号の変化幅を比較するための回路の構成図
である。
Figure 1 is a configuration diagram of a conventional automatic reactor output control circuit;
The figure is a configuration diagram of a circuit provided for each of the two selected neutron detectors for comparing the variation range of neutron signals.

Claims (1)

【特許請求の範囲】[Claims] 1、 中性子束検出器、信号処理回路、原子炉出方制御
装置から成る原子炉自動出方制御装置において各中性子
検出器の出力信号の変化幅′ft監視し、これを各検出
器間で比較する中性子束信号比較監視回路を設けたこと
を特徴とする原子炉自動出方制御装置。
1. In the reactor automatic output control system, which consists of a neutron flux detector, a signal processing circuit, and a reactor output control system, the change width 'ft of the output signal of each neutron detector is monitored, and this is compared between each detector. 1. A nuclear reactor automatic output control device characterized by being provided with a neutron flux signal comparison and monitoring circuit.
JP57225842A 1982-12-24 1982-12-24 Automatic power control device for reactor Pending JPS59116086A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57225842A JPS59116086A (en) 1982-12-24 1982-12-24 Automatic power control device for reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57225842A JPS59116086A (en) 1982-12-24 1982-12-24 Automatic power control device for reactor

Publications (1)

Publication Number Publication Date
JPS59116086A true JPS59116086A (en) 1984-07-04

Family

ID=16835673

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57225842A Pending JPS59116086A (en) 1982-12-24 1982-12-24 Automatic power control device for reactor

Country Status (1)

Country Link
JP (1) JPS59116086A (en)

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