JPH0644061B2 - Abnormal flow detector for reactor cooling system - Google Patents
Abnormal flow detector for reactor cooling systemInfo
- Publication number
- JPH0644061B2 JPH0644061B2 JP57018781A JP1878182A JPH0644061B2 JP H0644061 B2 JPH0644061 B2 JP H0644061B2 JP 57018781 A JP57018781 A JP 57018781A JP 1878182 A JP1878182 A JP 1878182A JP H0644061 B2 JPH0644061 B2 JP H0644061B2
- Authority
- JP
- Japan
- Prior art keywords
- cooling system
- flow rate
- reactor
- rate
- reactor cooling
- 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
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)
Description
【発明の詳細な説明】 本発明は、原子炉冷却系の異常流量検出方法に係わり、
特に液体金属ナトリウムを使用する高速増殖炉冷却系の
流量異常を早期に検出するのに好適な異常流量検出装置
に関する。The present invention relates to a method for detecting abnormal flow rate in a reactor cooling system,
Particularly, the present invention relates to an abnormal flow rate detection device suitable for early detection of an abnormal flow rate in a fast breeder reactor cooling system using liquid metal sodium.
液体金属ナトリウムを使用する高速増殖炉1次冷却系の
典型例を図1に示す。循環ポンプ3で冷却材を原子炉1
と熱交換器2の間で循環させて、原子炉1で発生する熱
を熱交換器2で除去させる。循環経路には、循環系の流
量を測定する流量検出器4を、ポンプにはその延長軸に
ポンプ回転計を設置するのが通例である。従来、上記原
子炉冷却系の異常流量検出は流量計の信号がプラント運
用上規定される流量、たとえば一定流量で運転される場
合にはその一定流量値を、原子炉出力と比例して流量を
変化させて運転する場合には原子炉出力に応じて定まる
流量値を基準流量として、その基準流量と実流量との比
較を行ない、その偏差が規定値以上変化したことをもつ
て原子炉冷却系の異常とする方法がとられている。この
様な流量異常検出方法は簡単であるため、有効な異常検
出手段であるが、その流量計の測定精度が余りよくない
場合あるいは流量計信号にゆらぎ成分がある場合など
は、基準流量との許容偏差を大きくせざるを得ず、その
異常検出感度を低下させる欠点がある。A typical example of a fast cooling reactor primary cooling system using liquid metal sodium is shown in FIG. Circulating pump 3 supplies coolant to reactor 1
And the heat exchanger 2 are circulated so that the heat generated in the reactor 1 is removed by the heat exchanger 2. It is customary to install a flow rate detector 4 for measuring the flow rate of the circulation system in the circulation path and a pump tachometer on the extension shaft of the pump. Conventionally, the abnormal flow rate detection of the reactor cooling system is performed by the flow rate signal in which the signal of the flow meter is regulated in plant operation, for example, when the flow rate is operated at a constant flow rate, the constant flow rate value is proportional to the reactor output. When changing the operation, the flow rate value determined according to the reactor output is used as a reference flow rate, and the reference flow rate is compared with the actual flow rate. The method of making it abnormal is taken. Since such a flow rate abnormality detection method is simple, it is an effective abnormality detection means.However, if the measurement accuracy of the flow meter is not very good or there is a fluctuation component in the flow meter signal, the There is a drawback that the allowable deviation must be increased and the abnormality detection sensitivity is reduced.
本発明の目的は、流量の変化を与えるポンプ回転数と実
流量との変化率を比較して早期に原子炉冷却系の流路異
常を検出する手段を提供することにある。An object of the present invention is to provide a means for detecting a flow path abnormality in a reactor cooling system at an early stage by comparing the rate of change between the pump rotational speed that gives a change in flow rate and the actual flow rate.
本発明は、前記した従来技術による異常流量検出手段を
補完して、より確実かつ早期の異常検出手段を提供する
ことである。前記した如く、流量計の測定精度が余りよ
くない場合あるいは流量計信号にゆらぎ成分がある場合
などは基準流量との許容偏差を大きくせざるを得ないた
め、その許容偏差内で生ずる流路の異常には、前記従来
の異常検出方法は動作しないことになる。この様な僅か
な流量の異常が生じても通常原子炉の安全性は損なわれ
ることのない様に設計されるが、この様な異常でも早期
に検出できる手段が装備されることが望ましい。The present invention is intended to provide a more reliable and early abnormality detecting means by complementing the above-mentioned abnormal flow detecting means according to the prior art. As described above, when the measurement accuracy of the flowmeter is not very good, or when the flowmeter signal has a fluctuation component, the allowable deviation from the reference flow rate must be increased. In the case of abnormality, the conventional abnormality detection method does not operate. It is designed so that the safety of the nuclear reactor is not normally impaired even if such a slight flow rate abnormality occurs, but it is desirable to equip a means for early detection of such abnormality.
従来技術は、流量計信号単独で異常を検出しようとする
ものであるが、本発明は冷却系流量に変化を与えるポン
プ回転数と実流量との変化率を比較して相対的に異常を
検出しようとするものである。The prior art attempts to detect an abnormality using the flowmeter signal alone, but the present invention compares the rate of change of the pump rotational speed that changes the cooling system flow rate with the actual flow rate to detect an abnormality relatively. Is what you are trying to do.
以下、本発明の一実施例を第2図により説明する。流量
センサ6は第1図に示す流量計4の位置に設置される流
量センサで通常電磁流量計が使用される。電磁流量計は
原子炉冷却材である液体ナトリウムの流速に比例した電
圧信号を発生する。回転計センサ7は第1図に示す回転
計5の位置に設置される回転センサで回転発電機あるい
は電磁ピツクアツプなどによる計測手段がとられる。本
図では回転発電機を使用した場合の図示で、回転発電機
はポンプ回転数に比例した電圧信号を発生する。信号変
換器8−1,8−2は、上記流量センサおよび回転計セ
ンサの電圧信号を電流信号に変換するものである。係数
器9は回転数信号を流量信号と比較するために、所定の
係数を入力信号に乗算する回路である。変化率演算器1
0−1,10−2は、上記流量センサおよび回転計サン
セの信号変換された信号の変化率を求めるものである。
比較器11は、上記流量および回転の変化率信号を比較
し、両者の偏差が予め定められたしきい値以上になつた
かを判定するものである。An embodiment of the present invention will be described below with reference to FIG. The flow sensor 6 is a flow sensor installed at the position of the flow meter 4 shown in FIG. 1, and an electromagnetic flow meter is normally used. The electromagnetic flowmeter generates a voltage signal proportional to the flow rate of liquid sodium, which is the reactor coolant. The tachometer sensor 7 is a rotation sensor installed at the position of the tachometer 5 shown in FIG. 1, and a measuring means such as a rotary generator or an electromagnetic pickup is used. In this figure, a rotary generator is used, and the rotary generator generates a voltage signal proportional to the pump rotation speed. The signal converters 8-1, 8-2 convert the voltage signals of the flow rate sensor and the tachometer sensor into current signals. The coefficient unit 9 is a circuit for multiplying the input signal by a predetermined coefficient in order to compare the rotation speed signal with the flow rate signal. Change rate calculator 1
0-1 and 10-2 are for obtaining the rate of change of the signal converted by the flow sensor and the tachometer sensor.
The comparator 11 compares the flow rate and the rotation rate change signals to determine whether the deviation between the two signals exceeds a predetermined threshold value.
冷却系の流路が形成され、その流路に変化がない場合は
ポンプ回転数と冷却系流量は比例する。すなわち、 F=α×N ……… F:冷却系流量(定格値に対する比率) N:ポンプ回転数(定格値に対する比率) α:換算定数 の関係がある。When a cooling system flow path is formed and there is no change in the flow path, the pump rotation speed is proportional to the cooling system flow rate. That is, F = α × N ... F: cooling system flow rate (ratio to rated value) N: pump speed (ratio to rated value) α: conversion constant
したがつて第2図に示す回路において、係数器9の係数
を上記式のαに相当する値に選定すれば、流路に変化
がない限り、理論的には信号21と22は等しくなる。
しかし、実際には計測精度および計測信号に含まれるゆ
らぎなどによりその差は現われる。この計測誤差および
ゆらぎなどを取り除くために、その信号の変化率を求め
両者の比較を行なうことが本発明の特徴である。Therefore, in the circuit shown in FIG. 2, if the coefficient of the coefficient multiplier 9 is selected to a value corresponding to α in the above equation, the signals 21 and 22 are theoretically equal to each other unless the flow path changes.
However, in reality, the difference appears due to the measurement accuracy and fluctuation included in the measurement signal. In order to remove the measurement error and fluctuation, it is a feature of the present invention that the rate of change of the signal is obtained and the two are compared.
冷却系流量を変動させる要因としては、ポンプ駆動源の
変動と流路の変動がある。ポンプ駆動源の変動ではポン
プ回転数と冷却系流量共に変動するが、流路変動ではポ
ンプ回転数は変動せず冷却系流量のみが変動する。した
がつて両者の変化率を常時監視し、両者の変化率の偏差
が許容値以上に変動する場合は冷却系流路の圧損変化あ
るいは流路の破損などによる流路の異常であることを検
知できる。本発明では、回転数と流量の変化率を比較し
ているため、流量および回転数の測定精度には影響を受
けず、また、流量信号に加わるゆらぎなどの変動成分
は、その変化率を演算する係数を大きくすることで、そ
のゆらぎ成分の影響を受けない様にすることが可能であ
る。Factors that change the cooling system flow rate include fluctuations in the pump drive source and fluctuations in the flow path. When the pump drive source fluctuates, both the pump rotation speed and the cooling system flow rate fluctuate, but when the flow path changes, the pump rotation speed does not fluctuate but only the cooling system flow rate fluctuates. Therefore, the change rate of both is constantly monitored, and if the deviation of the change rate of both changes more than the permissible value, it is detected that the flow path is abnormal due to pressure loss change of the cooling system flow path or breakage of the flow path. it can. In the present invention, since the rotational speed and the change rate of the flow rate are compared, the measurement accuracy of the flow rate and the rotational speed is not affected, and the fluctuation component such as fluctuations added to the flow rate signal is calculated by the change rate. It is possible to prevent the fluctuation component from being affected by increasing the coefficient.
本発明によれば、原子炉冷却系の流量計の測定軽度が余
りよくない場合あるいは流量計信号にゆらぎ成分がある
場合でも、確実かつ早期に流路の異常を検出できる。According to the present invention, even when the measurement lightness of the flowmeter of the reactor cooling system is not so good or the flowmeter signal has a fluctuation component, it is possible to reliably and early detect the abnormality of the flow path.
第1図は、液体金属ナトリウムを使用する高速増殖炉1
次冷却系の典型例を示す概念図、第2図は本発明になる
原子炉冷却系の異常流量検出装置の実施例説明図であ
る。 1…原子炉、2…熱交換器、3…冷却材循環ポンプ、4
…流量検出器、5…ポンプ回転計、6…流量センサ、7
…回転計センサ、8−1,2…信号変換器、9…係数
器、10−1,2…変化率演算器、11…比較器。FIG. 1 shows a fast breeder reactor 1 using liquid metal sodium.
FIG. 2 is a conceptual diagram showing a typical example of the next cooling system, and FIG. 2 is an explanatory diagram of an embodiment of the abnormal flow rate detection device of the reactor cooling system according to the present invention. 1 ... Reactor, 2 ... Heat exchanger, 3 ... Coolant circulation pump, 4
... Flow rate detector, 5 ... Pump tachometer, 6 ... Flow rate sensor, 7
... Tachometer sensor, 8-1, 2 ... Signal converter, 9 ... Coefficient device, 10-1, 2 ... Change rate calculator, 11 ... Comparator.
Claims (1)
などより構成される原子炉冷却系において、冷却系流路
配管に流量計を、循環ポンプに回転計を設置し、当該流
量計と回転計信号の変化率を比較しその偏差が規定値以
上になつたことをもつて原子炉冷却系の異常を検出する
ことを特徴とする原子炉冷却系の異常流量検出装置。1. A reactor cooling system comprising a reactor coolant circulation pump, piping, a heat exchanger, etc., wherein a flow meter is installed in the cooling system flow passage piping and a tachometer is installed in the circulation pump. And a rate of change of the tachometer signal are compared with each other, and an abnormality in the reactor cooling system is detected when the deviation exceeds a specified value, thereby detecting an abnormal flow rate in the reactor cooling system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57018781A JPH0644061B2 (en) | 1982-02-10 | 1982-02-10 | Abnormal flow detector for reactor cooling system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57018781A JPH0644061B2 (en) | 1982-02-10 | 1982-02-10 | Abnormal flow detector for reactor cooling system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58137794A JPS58137794A (en) | 1983-08-16 |
| JPH0644061B2 true JPH0644061B2 (en) | 1994-06-08 |
Family
ID=11981166
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57018781A Expired - Lifetime JPH0644061B2 (en) | 1982-02-10 | 1982-02-10 | Abnormal flow detector for reactor cooling system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0644061B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105741893A (en) * | 2016-05-06 | 2016-07-06 | 上海核工程研究设计院 | Reactor coolant pump flow monitoring system of nuclear power plant |
-
1982
- 1982-02-10 JP JP57018781A patent/JPH0644061B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS58137794A (en) | 1983-08-16 |
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