JPS61240121A - Apparatus for measuring water level of nuclear reactor - Google Patents

Apparatus for measuring water level of nuclear reactor

Info

Publication number
JPS61240121A
JPS61240121A JP60081292A JP8129285A JPS61240121A JP S61240121 A JPS61240121 A JP S61240121A JP 60081292 A JP60081292 A JP 60081292A JP 8129285 A JP8129285 A JP 8129285A JP S61240121 A JPS61240121 A JP S61240121A
Authority
JP
Japan
Prior art keywords
measuring device
water level
level
output signal
reactor water
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
JP60081292A
Other languages
Japanese (ja)
Inventor
Kiyohide Miura
三浦 清秀
Kiyoshi Daimon
清 大門
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.)
Toshiba Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
Toshiba Corp
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 Toshiba Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP60081292A priority Critical patent/JPS61240121A/en
Publication of JPS61240121A publication Critical patent/JPS61240121A/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

Abstract

PURPOSE:To make it possible to accurately measure the water level of a nuclear reactor, by correcting the output signal of a level measuring device, which measures pressure difference between a reference water head and the pressure take-out point below a reactor water level, by the output signal of a density measuring device for measuring the pressure difference between two places below the reactor water level. CONSTITUTION:The same level measuring device 6 as a conventional one is provided below a reactor water level 2 and pressures are guided from two pressure take-out points 8a, 8b separated by a certain distance in an up-and- down direction through pressure guide pipings 9a, 9b and pressure difference is measured by a density measuring device 10. The output signal D of this density measuring device 10 comes to the value proportional to the water density of a nuclear reactor. A level correcting device 11 performs the correction of the output signal DELTAP of the level measuring device 6 by the output signal D of the density measuring device 10 to output a nuclear reactor water level signal L receiving no effect of the change in the water density of the nuclear reactor.

Description

【発明の詳細な説明】 [発明の技術分野] 本発明は発電用沸騰水型原子炉の原子炉水位計測装置設
備において、原子炉水密度の変化の影響をうけない原子
炉水位計測装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a reactor water level measuring device that is not affected by changes in reactor water density in reactor water level measuring device equipment for a boiling water nuclear reactor for power generation.

[発明の技術的背景] 一般に原子力発電所においては、原子炉水位を測定して
その結果を通常運転時の水位監視のばか配管破断事故時
のスクラムや工学的安全設備の起動信号等に利用してい
る。
[Technical Background of the Invention] Generally, in nuclear power plants, the reactor water level is measured and the results are used for water level monitoring during normal operation, scram in the event of a pipe rupture accident, and as a start signal for engineering safety equipment. ing.

第2図は従来の原子炉水位計測装置の構成例を示すもの
で、圧力容器1の炉水レベル2の上方の蒸気層に開口す
る圧力取出点3aに昇り勾配の導圧配管4を介して凝縮
槽5を接続し、この凝縮槽5の下端は導圧配管7bで差
圧式のレベル測定器6の圧力検出口の一つに接続されて
おり、レベル測定器6のもう一つの圧力検出出口は、導
圧配管7aで炉水レベル2の下方に開口する圧力取出点
3bに接続されている。
FIG. 2 shows an example of the configuration of a conventional reactor water level measuring device. A condensing tank 5 is connected, and the lower end of this condensing tank 5 is connected to one of the pressure detection ports of a differential pressure type level measuring device 6 through a pressure guiding pipe 7b, and the other pressure detecting port of the level measuring device 6 is connected to the condensing tank 5. is connected to a pressure take-off point 3b that opens below the reactor water level 2 by a pressure piping 7a.

このような構成の原子炉水位計測装置において、凝縮槽
5内は圧力容器1内の蒸気層部に連通しており、凝縮槽
5内に流入した炉水蒸気はそこで冷却液化し、その余剰
の凝縮水は下り勾配の導圧配置14を通して圧力容器1
内に戻るので、凝縮槽5内の液面は常時一定となって基
準水頭を形成する。
In the reactor water level measuring device having such a configuration, the inside of the condensing tank 5 is connected to the steam layer inside the pressure vessel 1, and the reactor steam that flows into the condensing tank 5 is cooled and liquefied there, and the excess condensation is carried out. The water is passed through the pressure vessel 1 through the downhill conduction arrangement 14.
Therefore, the liquid level in the condensing tank 5 is always constant and forms a reference water head.

従って導圧配管7a、7b内の流体圧の差圧信号、原子
炉水位に比例した信号となる。
Therefore, the signal is a differential pressure signal between the fluid pressures in the pressure guiding pipes 7a and 7b, and is a signal proportional to the reactor water level.

[背景技術の問題点] 前述の様な原子炉水位測定装置において、レベル測定器
6の出力信号が原子炉水位に比例した信号になる為には
、原子炉水密度が一定でなくてはいけない。しかしなが
ら、原子炉水密度は原子炉の圧力及び温度によって決定
されるものであるが、原子炉の圧力及び温度は、常にあ
る範囲内に制御されているとはいえ、冷却材喪失事故(
LOCA)時等で原子炉に過渡的変化が生じた場合は、
制御範囲から免税して原子炉水密度が変動する場合があ
り、こ様な場合、原子炉水位信号に誤差が生ずることに
なる。また原子炉に過渡的変化を生じた様な場合は、こ
れに対処する為にも、特に正確な原子炉水位情報を運転
員に知らしめることが望ましい。
[Problems with the Background Art] In the reactor water level measuring device as described above, in order for the output signal of the level measuring device 6 to be a signal proportional to the reactor water level, the reactor water density must be constant. . However, the reactor water density is determined by the reactor pressure and temperature, and although the reactor pressure and temperature are always controlled within a certain range, loss of coolant accidents (
If a transient change occurs in the reactor such as during LOCA),
There are cases where the reactor water density fluctuates outside the control range, and in such a case, an error will occur in the reactor water level signal. Furthermore, in the event that a transient change occurs in the reactor, it is desirable to provide operators with particularly accurate reactor water level information in order to deal with this.

[発明の目的] 本発明の目的は、原子炉の過渡的変化により、原子炉水
密度が変化しても水位信号に影響のない正確な原子炉水
位信号を得ることのできる原子炉水位計測装置を提供す
ることにある。
[Object of the Invention] The object of the present invention is to provide a reactor water level measuring device that can obtain an accurate reactor water level signal that does not affect the water level signal even if the reactor water density changes due to transient changes in the reactor. Our goal is to provide the following.

[発明の概要] 本発明の原子炉水位計測装置は、圧力容器の蒸気層に連
通している凝縮槽により形成される基準水頭と、炉水レ
ベルの下方の圧力取出点との圧力差を測定しているレベ
ル測定器と、炉水レベルの下方2ケ所の圧力取出点の圧
力差を測定している密度測定器と、前記レベルの測定器
の出力信号と密度測定器の出力信号とを入力してレベル
測定器の出力信号を密度測定器の出力信号で補正するレ
ベル補正器とから構成したことを特徴とするものである
[Summary of the invention] The reactor water level measuring device of the present invention measures the pressure difference between a reference water head formed by a condensing tank communicating with a steam layer of a pressure vessel and a pressure take-off point below the reactor water level. Input the level measuring device used to measure the level, the density measuring device measuring the pressure difference between two pressure take-off points below the reactor water level, the output signal of the level measuring device, and the output signal of the density measuring device. and a level corrector for correcting the output signal of the level measuring device with the output signal of the density measuring device.

[発明の実施例] 以下本発明を第1図を参照して説明するが、第1図にお
いて、第2図と同一符号は同一部分を示すものであるか
らその説明を省略する。本発明においては、レベル測定
器6は従来と同じものであるが、さらに炉水レベル2よ
り下方にあり、かつ上下方向にある距離だけ離れた2つ
の圧力取出点8a、8bより導圧配管9a 、9bで圧
力を導き、密度測定器10で圧力差を測定する。この密
度測定器10の出力信号りは、原子炉水密度に比例した
値となる。またレベル補正器11は、レベル測定器6の
出力信号ΔPを密度測定器10の出力信号りで補正を行
い、原子炉水密度の変化の影響のない原子炉水位信号り
を出力するよう構成されている。
[Embodiments of the Invention] The present invention will be described below with reference to FIG. 1. In FIG. 1, the same reference numerals as in FIG. 2 indicate the same parts, so the explanation thereof will be omitted. In the present invention, the level measuring device 6 is the same as the conventional one, but furthermore, the pressure piping 9a is connected to two pressure take-off points 8a and 8b located below the reactor water level 2 and separated by a certain distance in the vertical direction. , 9b, and the density measuring device 10 measures the pressure difference. The output signal of this density measuring device 10 has a value proportional to the reactor water density. Further, the level corrector 11 is configured to correct the output signal ΔP of the level measuring device 6 using the output signal of the density measuring device 10 and output a reactor water level signal that is not affected by changes in the reactor water density. ing.

このように構成した本発明の原子炉水位計測装置におい
て、レベル測定器6の出力信号ΔPは(1)式の様に表
わされる。
In the reactor water level measuring device of the present invention configured as described above, the output signal ΔP of the level measuring device 6 is expressed as in equation (1).

ΔP=ρ+ H+ +R+        ・・・(1
)ここでρ1は原子炉水密度、Hlは圧力取出点3bと
原子炉水レベル2の垂直方向距離、つまり原子炉水レベ
ルを表すaR+ は定数である。又密度測定器10の出
力信号りは(2)式の様に表わされる。
ΔP=ρ+ H+ +R+ ...(1
) Here, ρ1 is the reactor water density, Hl is the vertical distance between the pressure take-off point 3b and the reactor water level 2, and aR+ representing the reactor water level is a constant. Further, the output signal of the density measuring device 10 is expressed as in equation (2).

D−ρ+ H2・・・(2) ここでH2は圧力取出点8aと8bの垂直方向距離を表
わす。レベル補正器11の出力信号しは、ΔPとDを用
いて(3)式の様に表わされる。
D-ρ+H2...(2) Here, H2 represents the vertical distance between the pressure take-off points 8a and 8b. The output signal of the level corrector 11 is expressed as in equation (3) using ΔP and D.

従ってレベル補正器11の出力信号りは原子炉レベルH
1と等しい値となり、原子炉水密度ρ1とは無関係にな
る。
Therefore, the output signal of the level corrector 11 is at the reactor level H.
It becomes a value equal to 1, and becomes unrelated to the reactor water density ρ1.

[発明の効果] 以上説明した様に本発明によれば、基準水頭と炉水レベ
ルの下方の圧力取出点との圧力差を測定しているレベル
測定器の出力信号を、炉水レベルの下方の2ケ所の圧力
取出点の圧力差を測定している密度測定器の出力信号で
補正するよう構成したことにより、原子炉水密度の変化
による影響を受けず、より正確な原子炉水位が測定でき
るので、原子炉に過渡的変化が生じて原子炉水密度が変
動しても正確な原子炉水位信号を発し、安全で信頼性の
高い原子炉の運転を行うことができる効果がある。
[Effects of the Invention] As explained above, according to the present invention, the output signal of the level measuring device that measures the pressure difference between the reference water head and the pressure take-off point below the reactor water level is By configuring the system to correct the pressure difference between the two pressure take-off points using the output signal of the density measuring device, it is possible to measure the reactor water level more accurately without being affected by changes in the reactor water density. As a result, even if a transient change occurs in the reactor and the reactor water density fluctuates, an accurate reactor water level signal can be generated and the reactor can be operated safely and reliably.

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

第1図は本発明の原子炉水位計測装置を示す構成図、第
2図は従来の原子炉水位計測装置を示す構成図である。 1・・・圧力容器 2・・・炉水レベル 3a、3b、8a、8b・・・圧力取出点4.7a 、
’7b 、9a 、9b −・・導圧配管5・・・凝縮
槽 6・・・レベル測定器 10・・・密度測定器 11・・・レベル補正器 (8733)代理人 弁理士 猪 股 祥 晃(ほか1
名) 第  2  図      3
FIG. 1 is a block diagram showing a reactor water level measuring device of the present invention, and FIG. 2 is a block diagram showing a conventional reactor water level measuring device. 1... Pressure vessel 2... Reactor water level 3a, 3b, 8a, 8b... Pressure take-off point 4.7a,
'7b, 9a, 9b - Pressure piping 5... Condensation tank 6... Level measuring device 10... Density measuring device 11... Level corrector (8733) Agent Patent attorney Yoshiaki Inomata (and 1 more
Figure 2 3

Claims (2)

【特許請求の範囲】[Claims] (1)圧力容器の蒸気層に連通している凝縮槽により形
成される基準水頭と炉水レベルの下方の圧力取出点との
圧力差を測定しているレベル測定器と、炉水レベルの下
方2ケ所の圧力取出点の圧力差を測定している密度測定
器と、前記レベル測定器の出力信号と密度測定器の出力
信号とを入力してレベル測定器の出力信号を密度測定器
の出力信号で補正するレベル補正器とから構成したこと
を特徴とする原子炉水位計測装置。
(1) A level measuring device that measures the pressure difference between the reference head formed by the condensing tank communicating with the steam layer of the pressure vessel and the pressure take-off point below the reactor water level, and a level measuring device below the reactor water level. A density measuring device that measures the pressure difference between two pressure take-off points is input, and the output signal of the level measuring device and the output signal of the density measuring device are input, and the output signal of the level measuring device is outputted from the density measuring device. A nuclear reactor water level measuring device comprising a level corrector that corrects using a signal.
(2)凝縮槽は降り勾配の導圧配管を介して圧力容器内
の蒸気層に連通していることを特徴とする特許請求の範
囲第1項記載の原子炉水位計測装置。
(2) The reactor water level measuring device according to claim 1, characterized in that the condensing tank communicates with a steam layer in the pressure vessel via a descending pressure impulse piping.
JP60081292A 1985-04-18 1985-04-18 Apparatus for measuring water level of nuclear reactor Pending JPS61240121A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60081292A JPS61240121A (en) 1985-04-18 1985-04-18 Apparatus for measuring water level of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60081292A JPS61240121A (en) 1985-04-18 1985-04-18 Apparatus for measuring water level of nuclear reactor

Publications (1)

Publication Number Publication Date
JPS61240121A true JPS61240121A (en) 1986-10-25

Family

ID=13742303

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60081292A Pending JPS61240121A (en) 1985-04-18 1985-04-18 Apparatus for measuring water level of nuclear reactor

Country Status (1)

Country Link
JP (1) JPS61240121A (en)

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