JPH05288590A - Nuclear reactor water level measuring device - Google Patents
Nuclear reactor water level measuring deviceInfo
- Publication number
- JPH05288590A JPH05288590A JP4092868A JP9286892A JPH05288590A JP H05288590 A JPH05288590 A JP H05288590A JP 4092868 A JP4092868 A JP 4092868A JP 9286892 A JP9286892 A JP 9286892A JP H05288590 A JPH05288590 A JP H05288590A
- Authority
- JP
- Japan
- Prior art keywords
- temperature
- water level
- reactor
- instrumentation
- measuring
- 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
- Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、例えば原子力発電プラ
ントにおける原子炉の水位を原子炉水位計を用いて測定
する装置に係り、特に原子炉の水位を正確に測定できる
と共に、原子炉水位計の校正作業を容易に行ない得るよ
うにした原子炉水位測定装置に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an apparatus for measuring the water level of a nuclear reactor, for example, in a nuclear power plant using a reactor water level gauge. The present invention relates to a reactor water level measuring device capable of easily performing the calibration work of.
【０００２】[0002]
【従来の技術】従来から、例えば原子力発電プラントに
おいては、原子炉の水位を原子炉水位計を用いて測定す
ることが行なわれてきている。この場合、原子炉水位の
測定に当たっては、原子炉水位計のドライウェル（Ｄ／
Ｗ）内の計装配管（導圧管）の水柱密度を、一定温度
（原子炉格納容器常温 摂氏約５７度）として校正を行
なっている。そして、ドライウェル内の温度分布のばら
つきにより、校正結果が基準値以内に収まらない場合に
は、ドライウェルの点検時に現場で雰囲気温度を測定し
たり、あるいは仮設温度計を設置することにより、各ラ
インの雰囲気温度による影響を調査し、補正を加えるよ
うにしている。2. Description of the Related Art Conventionally, for example, in a nuclear power plant, the water level of a nuclear reactor has been measured using a reactor water level gauge. In this case, when measuring the reactor water level, the dry well (D /
Calibration is performed by setting the water column density of the instrumentation pipe (pressure pipe) in W) to a constant temperature (reactor containment vessel room temperature about 57 degrees Celsius). If the calibration result does not fall within the standard value due to the variation in the temperature distribution in the dry well, measure the ambient temperature at the site when inspecting the dry well, or install a temporary thermometer. The influence of the ambient temperature of the line is investigated and corrections are made.
【０００３】すなわち、原子炉の水位は、例えば図３に
示すような構成において、以下のような基本計算式によ
り求めている。なお、図３中、１は原子炉格納容器（Ｒ
ＰＶ）、２は原子炉水位計（ＬＴ）をそれぞれ示してい
る。That is, the water level of the nuclear reactor is calculated by the following basic calculation formula in the configuration shown in FIG. 3, for example. In FIG. 3, reference numeral 1 is a reactor containment vessel (R
PV) and 2 are reactor water level gauges (LT), respectively.
【０００４】[0004]
【数１】 [Equation 1]
【０００５】ＷC ：発生差圧（摂氏２０度換算水柱） ＶA ：摂氏２０度大気圧における水の比容積 ＶG ：炉内蒸気の比容積 ＶF ：炉水の比容積 ＶC ：原子炉圧力容器（ＰＣＶ）内計装配管の水の比容
積 ＶT ：原子炉圧力容器（ＰＣＶ）外計装配管の水の比容
積 Ｌ1 ：炉水面から凝縮槽基準水面までの距離 Ｌ2 ：下部取出しノズルから炉水面までの距離 Ｌ3 ：高圧側計装ペネレベルから下部取出しノズルまで
の距離 Ｌ4 ：低圧側計装ペネレベルから凝縮槽基準水面までの
距離 Ｌ5 ：低圧側計装ペネレベルから高圧側計装ペネレベル
までの距離[0005] W C: generating a differential pressure (20 ° in terms of water column C) V A: specific volume V G of water in Celsius 20 degrees atmospheric pressure: specific volume V F of the furnace the vapor ratio of the reactor water volume V C: atom Specific volume of water in instrumentation piping inside reactor pressure vessel (PCV) V T : Specific volume of water in instrumentation piping outside reactor pressure vessel (PCV) L 1 : Distance from reactor water surface to condensation tank reference water surface L 2 : distance from the lower extraction nozzle to the furnace water surface L 3: distance from the high pressure side instrumentation Penereberu to lower take-out nozzle L 4: distance from the low pressure side instrumentation Penereberu to the condensing tank reference water level L 5: high from the low pressure side instrumentation Penereberu Distance to the side instrumentation pen level
【０００６】これは、ドライウェル内常温が平均摂氏約
５７度で設計されているが、個々のエリアやドライウェ
ル冷却ファン等の運転モードによって、実際にはばらつ
きが生じているためである。This is because the room temperature in the dry well is designed to have an average temperature of about 57 degrees Celsius, but it actually varies depending on the operation mode of each area or the dry well cooling fan.
【０００７】そのため、原子炉水位計は、定常運転時の
環境条件（ドライウェル 摂氏５７度 圧力容器 摂氏
２８５度，７０．７ｋｇｍ／ｃｍ2 ）下において、正確
な指示を示すように校正されている。For this reason, the reactor water level gauge is designed so that the environmental conditions at the time of steady operation (dry well: 57 degrees Celsius, pressure vessel: 285 degrees Celsius, 70.7 kgm / cm 2 ) Below, it is calibrated to give accurate instructions.
【０００８】しかしながら、万一、ドライウェル内で計
装配管の破断事故等が発生すると、ドライウェル内の雰
囲気温度が大幅に上昇して、計装配管内の水柱密度が変
化し、原子炉水位計の誤差が生じる。これらの誤差は、
プラント運転の安全上問題はない値であるが、原子炉の
水位をより正確に把握することが運転管理上望まれると
共に、現場での温度測定作業をなくすることが、被曝低
減化の上から望まれてきている。However, if a breakage of the instrumentation pipe occurs in the drywell, the atmospheric temperature in the drywell rises significantly, the water column density in the instrumentation pipe changes, and the reactor water level meter Error occurs. These errors are
Although it is a value that does not cause a safety problem in plant operation, more accurate grasp of the water level of the reactor is desired in operation management, and eliminating temperature measurement work at the site is to reduce radiation exposure. It has been desired.
【０００９】[0009]
【発明が解決しようとする課題】以上のように、従来の
原子炉水位測定方法においては、原子炉水位計のドライ
ウェル内の計装配管の水柱密度を一定温度として校正を
行なっていることから、ドライウェル内の雰囲気温度の
ばらつき、ドライウェル内の計装配管破断事故等による
ドライウェル内の温度上昇が生じた場合に、測定誤差が
大きくなって原子炉の水位を正確に測定できないという
問題があった。As described above, in the conventional reactor water level measuring method, calibration is performed by setting the water column density of the instrumentation pipe in the dry well of the reactor water level meter to a constant temperature. When the temperature of the dry well rises due to variations in the atmospheric temperature in the dry well or due to an instrument pipe breakage accident in the dry well, the measurement error increases and the water level in the reactor cannot be measured accurately. was there.
【００１０】本発明の目的は、原子炉の水位を正確に測
定できると共に、原子炉水位計の校正作業を容易に行な
うことが可能な極めて信頼性の高い原子炉水位測定装置
を提供することにある。An object of the present invention is to provide an extremely reliable reactor water level measuring device capable of accurately measuring the water level of the reactor and facilitating the calibration work of the reactor water level gauge. is there.
【００１１】[0011]
【課題を解決するための手段】上記の目的を達成するた
めに、In order to achieve the above object,
【００１２】まず、請求項１に記載の発明では、原子炉
水位計のドライウェル内の計装配管の水柱密度を校正す
ることにより、原子炉の水位を測定する装置において、
計装配管の垂直方向に設けられ、当該計装配管の表面温
度を測定する複数の温度測定手段と、各温度測定手段に
よりそれぞれ測定された温度を記録する温度記録手段と
を備えて構成し、温度記録手段による記録結果に基づい
て計装配管の水柱密度を温度補正するようにしている。First, according to the invention described in claim 1, in the apparatus for measuring the water level of the reactor by calibrating the water column density of the instrumentation pipe in the dry well of the reactor water level meter,
Provided in the vertical direction of the instrumentation pipe, comprising a plurality of temperature measuring means for measuring the surface temperature of the instrumentation pipe, and a temperature recording means for recording the temperature measured by each temperature measuring means, respectively, The water column density of the instrumentation pipe is temperature-corrected based on the recording result of the temperature recording means.
【００１３】また、請求項２に記載の発明では、原子炉
水位計のドライウェル内の計装配管の水柱密度を校正す
ることにより、原子炉の水位を測定する装置において、
計装配管の垂直方向に設けられ、当該計装配管の表面温
度を測定する複数の温度測定手段と、各温度測定手段に
よりそれぞれ測定された温度に基づいて、計装配管の水
柱密度を自動的に温度補正する補正演算手段とを備えて
構成している。ここで、特に上記各温度測定手段として
は、高圧側または低圧側の計装配管のうち少なくとも低
圧側の計装配管に設けるようにしている。また、上記温
度測定手段としては、光ファイバー温度分布センサを用
いるようにしている。さらに、上記温度記録手段として
は、各温度測定手段から離間した部所に設けるようにし
ている。According to the second aspect of the invention, in the apparatus for measuring the water level of the reactor by calibrating the water column density of the instrumentation pipe in the dry well of the reactor water level meter,
The water column density of the instrumentation pipe is automatically determined based on the temperature measured by each of the temperature measurement units and the temperature measurement units that are provided in the vertical direction of the instrumentation pipe and measure the surface temperature of the instrumentation pipe. In addition, the correction calculation means for temperature correction is provided. Here, in particular, as each of the temperature measuring means, at least the low-pressure side instrumentation pipe of the high-pressure side or low-pressure side instrumentation pipe is provided. An optical fiber temperature distribution sensor is used as the temperature measuring means. Further, the temperature recording means is provided at a portion separated from each temperature measuring means.
【００１４】[0014]
【作用】従って、請求項１に記載の発明の原子炉水位測
定装置においては、計装配管の垂直方向の雰囲気温度が
測定され、その温度分布が記録されることにより、この
記録結果を基に測定員が計算で、計装配管の水柱密度を
温度補正計算して、原子炉の水位を正確に求めることが
できる。Therefore, in the reactor water level measuring apparatus according to the first aspect of the present invention, the atmospheric temperature in the vertical direction of the instrumentation pipe is measured and the temperature distribution is recorded, and the recorded result is used as a basis. The operator can calculate the temperature of the water column density of the instrumentation pipe by temperature correction and accurately determine the water level of the reactor.
【００１５】また、請求項２に記載の発明の原子炉水位
測定装置においては、計装配管の垂直方向の雰囲気温度
が測定され、その温度分布を基に、計装配管の水柱密度
を自動的に温度補正することにより、原子炉の水位を正
確にかつ自動的に求めることができる。In the reactor water level measuring apparatus according to the second aspect of the invention, the atmospheric temperature in the vertical direction of the instrumentation pipe is measured, and the water column density of the instrumentation pipe is automatically determined based on the temperature distribution. By correcting the temperature to 1, the water level of the reactor can be accurately and automatically obtained.
【００１６】さらに、温度測定手段から離間した部所に
て温度分布記録を常時指示することにより、現場での温
度測定作業が不要となり、被曝低減化の面からも効果を
得ることができる。Further, by always instructing the temperature distribution recording at a place distant from the temperature measuring means, the temperature measuring work in the field becomes unnecessary, and the effect of reducing the radiation exposure can be obtained.
【００１７】[0017]
【実施例】以下、本発明の一実施例について図面を参照
して詳細に説明する。図１は、本発明による原子炉水位
測定装置の構成例を示すブロック図であり、図３と同一
要素には同一符号を付して示している。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described in detail below with reference to the drawings. FIG. 1 is a block diagram showing a configuration example of a reactor water level measuring device according to the present invention, and the same elements as those in FIG. 3 are designated by the same reference numerals.
【００１８】すなわち、本実施例の原子炉水位測定装置
は、原子炉水位計のドライウェル内の低圧側および高圧
側の計装配管の垂直方向に設けられ、当該計装配管の表
面温度を測定する複数（本例では、各々の側について３
個ずつの合計６個）の温度計３Ａ，３Ｂ，３Ｃおよび３
Ｄ，３Ｅ，３Ｆと、各温度計３Ａ，３Ｂ，３Ｃ，３Ｄ，
３Ｅ，３Ｆから離間した中央操作所に設けられ、各温度
計３Ａ，３Ｂ，３Ｃ，３Ｄ，３Ｅ，３Ｆによりそれぞれ
測定された温度を記録する温度記録計４とから構成して
いる。That is, the reactor water level measuring device of this embodiment is provided in the dry well of the reactor water level meter in the vertical direction of the low pressure side and high pressure side instrumentation pipes and measures the surface temperature of the instrumentation pipes. Multiple (3 on each side in this example)
6 thermometers 3A, 3B, 3C and 3 each
D, 3E, 3F and each thermometer 3A, 3B, 3C, 3D,
It is provided at a central operation place apart from 3E and 3F, and is composed of a temperature recorder 4 for recording the temperature measured by each of the thermometers 3A, 3B, 3C, 3D, 3E and 3F.
【００１９】ここで、各温度計３Ａ，３Ｂ，３Ｃ，３
Ｄ，３Ｅ，３Ｆとしては、例えば熱電対を用いることが
できる。なお、図１中、５は原子炉圧力容器（ＰＣＶ）
を示している。次に、以上のように構成した本実施例の
原子炉水位測定装置の作用について説明する。Here, each thermometer 3A, 3B, 3C, 3
As D, 3E, 3F, for example, a thermocouple can be used. In FIG. 1, 5 is a reactor pressure vessel (PCV)
Is shown. Next, the operation of the reactor water level measuring device of the present embodiment configured as described above will be described.
【００２０】図１において、低圧側および高圧側の計装
配管に設けた各温度計３Ａ，３Ｂ，３Ｃおよび３Ｄ，３
Ｅ，３Ｆにより、計装配管の表面温度ＴA ，ＴB ，ＴC
およびＴD ，ＴE ，ＴF が測定される。そして、これら
の各温度計３Ａ，３Ｂ，３Ｃ，３Ｄ，３Ｅ，３Ｆにより
それぞれ測定された温度ＴA ，ＴB ，ＴC ，ＴD ，
ＴE ，ＴF は、中央操作所に設けた温度記録計４に記録
される。In FIG. 1, thermometers 3A, 3B, 3C and 3D, 3 provided on the low-pressure side and high-pressure side instrumentation pipes, respectively.
E, 3F, the surface temperature T A , T B , T C of the instrumentation pipe
And T D , T E , T F are measured. The temperatures T A , T B , T C , T D , respectively measured by these thermometers 3A, 3B, 3C, 3D, 3E, 3F,
The T E and T F are recorded on the temperature recorder 4 provided at the central operating station.
【００２１】従って、測定員は、この温度記録計４に記
録された各温度ＴA ，ＴB ，ＴC ，ＴD ，ＴE ，ＴF 、
すなわち計装配管の垂直方向の温度分布を確認した上
で、これらの温度を用いて計装配管の水柱密度を温度補
正計算することにより、原子炉の水位が正確に求められ
る。Therefore, the measurer can measure the temperatures T A , T B , T C , T D , T E , and T F recorded on the temperature recorder 4.
That is, after confirming the temperature distribution in the vertical direction of the instrumentation pipe, by using these temperatures to perform temperature correction calculation of the water column density of the instrumentation pipe, the water level of the reactor can be accurately obtained.
【００２２】すなわち、この場合、原子炉の水位は、例
えば以下のような温度補正計算式（６個の温度計３Ａ，
３Ｂ，３Ｃ，３Ｄ，３Ｅ，３Ｆを設けた場合）により求
められる。That is, in this case, the water level of the nuclear reactor is calculated by, for example, the following temperature correction calculation formula (six thermometers 3A,
3B, 3C, 3D, 3E, 3F are provided).
【００２３】[0023]
【数２】 [Equation 2]
【００２４】ＶCA：温度ＴA の時、７０．７ｋｇ〜ｃｍ
2 時の水の比容積 ＶCB：温度ＴB の時、７０．７ｋｇ〜ｃｍ2 時の水の比
容積 ＶCC：温度ＴC の時、７０．７ｋｇ〜ｃｍ2 時の水の比
容積 ＶCD：温度ＴD の時、７０．７ｋｇ〜ｃｍ2 時の水の比
容積 ＶCE：温度ＴE の時、７０．７ｋｇ〜ｃｍ2 時の水の比
容積 ＶCF：温度ＴF の時、７０．７ｋｇ〜ｃｍ2 時の水の比
容積 なお、ＷC 、ＶG 、ＶF 、ＶT 、Ｌ1 、Ｌ2 、Ｌ5 は、
それぞれ図３と同様である。V CA : 70.7 kg-cm at temperature T A
2 Specific volume of water at time V CB : At temperature T B , 70.7 kg to cm 2 Specific volume of water at time V CC : 70.7 kg to cm 2 at temperature T C Specific volume of water at time V CD : 70.7 kg to cm 2 at temperature T D Specific volume of water at time V CE : 70.7 kg to cm 2 at temperature T E Specific volume of water at time V CF : 70.7 kg to cm 2 at temperature T F Specific volume of water at time W C , V G , V F , V T , L 1 , L 2 , L 5 are
Each is similar to FIG.
【００２５】以上より、ドライウェル内の雰囲気温度の
ばらつきによって、本来であれば測定水位に相対誤差が
生じるが、本実施例では、計装配管に設けた各温度計に
よって計装配管の表面温度を測定し、その温度値を用い
て計装配管の水柱密度が温度補正されることにより、原
子炉の水位測定を精度よく行なうことができる。From the above, although the relative error in the measured water level would normally occur due to the variation of the atmospheric temperature in the dry well, in the present embodiment, the surface temperature of the instrumentation pipe is adjusted by each thermometer provided in the instrumentation pipe. Is measured, and the water column density of the instrumentation pipe is temperature-corrected using the temperature value, so that the water level in the reactor can be accurately measured.
【００２６】また、ドライウェル内での計装配管の破断
事故等の発生によって、原子炉格納容器内温度が大幅に
上昇した場合（ドライウェル最高温度 摂氏１７１度、
安全解析上の大破断事故時 摂氏１４０度）にも、本来
であれば測定誤差（例えば、燃料域水位計の事故時の標
準状態（摂氏１００度飽和）からの指示誤差は、約２９
０ｍｍ低めの指示となる：フルスケール５１００ｍｍに
対して、約６％の指示誤差）が生じるが、本実施例で
は、上記と同様にして測定誤差を吸収することができ
る。Further, when the temperature inside the reactor containment vessel rises significantly due to the occurrence of a breakage of the instrumentation piping in the drywell (the maximum temperature of the drywell is 171 degrees Celsius,
Even in the case of a major failure accident in safety analysis at 140 degrees Celsius, the measurement error (for example, the indication error from the standard state (100 degrees Celsius saturation) of the fuel level gauge at the time of the accident) is about 29.
The instruction becomes 0 mm lower: an instruction error of about 6% with respect to the full scale of 5100 mm) occurs, but in this embodiment, the measurement error can be absorbed in the same manner as described above.
【００２７】上述したように、本実施例では、原子炉水
位計のドライウェル内の計装配管の水柱密度を校正する
ことにより、原子炉の水位を測定する装置において、低
圧側および高圧側の計装配管の垂直方向に設けられ、当
該計装配管の表面温度を測定する６個の温度計３Ａ，３
Ｂ，３Ｃ，３Ｄ，３Ｅ，３Ｆと、各温度計３Ａ，３Ｂ，
３Ｃ，３Ｄ，３Ｅ，３Ｆによりそれぞれ測定された温度
を記録する温度記録計４とから構成し、温度記録計４に
よる記録結果に基づいて計装配管の水柱密度を温度補正
するようにしたものである。As described above, in the present embodiment, in the apparatus for measuring the water level of the reactor by calibrating the water column density of the instrumentation pipe in the dry well of the reactor water level gauge, Six thermometers 3A, 3 provided in the vertical direction of the instrumentation pipe to measure the surface temperature of the instrumentation pipe
B, 3C, 3D, 3E, 3F, and thermometers 3A, 3B,
3C, 3D, 3E, and 3F, each of which is composed of a temperature recorder 4 for recording the temperature measured, and the water column density of the instrumentation pipe is temperature-corrected based on the recording result by the temperature recorder 4. is there.
【００２８】従って、計装配管の表面温度を常時測定
し、計装配管の水柱密度の補正を中央操作所にて行なう
ことにより、通常運転時および事故時に、正確な原子炉
パラメータの把握（誤差の把握）を行なうことができ、
原子炉の水位を正確に測定することができると共に、原
子炉水位計の校正作業を容易に行なうことが可能とな
る。また、温度分布記録を中央操作所にて常時指示する
ことにより、現場での温度測定作業が不要となり、被曝
低減化の面からも効果を得ることが可能となる。尚、本
発明は上記実施例に限定されるものではなく、次のよう
にしても同様に実施できるものである。Therefore, by constantly measuring the surface temperature of the instrumentation pipe and correcting the water column density of the instrumentation pipe at the central operation site, it is possible to accurately grasp the reactor parameters (errors) during normal operation and during an accident. Can be carried out)
The reactor water level can be accurately measured, and the reactor water level gauge can be easily calibrated. Further, by constantly instructing the temperature distribution record at the central operation place, the temperature measurement work at the site becomes unnecessary, and it is possible to obtain an effect from the viewpoint of radiation exposure reduction. The present invention is not limited to the above embodiment, but can be implemented in the same manner as described below.
【００２９】（ａ）上記実施例においては、計装配管の
垂直方向の雰囲気温度を測定して温度記録計４に記録さ
せ、その温度分布を基に測定員が計算で、計装配管の水
柱密度を温度補正計算して、原子炉の水位を求める場合
について説明したが、これに限られるものではない。(A) In the above embodiment, the atmospheric temperature of the instrumentation pipe in the vertical direction is measured and recorded in the temperature recorder 4, and the water temperature of the instrumentation pipe is calculated by the measurer based on the temperature distribution. The case where the density of the reactor is calculated by temperature correction to obtain the water level of the reactor has been described, but the present invention is not limited to this.
【００３０】例えば、図２にその構成例を示すように、
前記温度記録計４に代えて補正演算回路６を設け、前記
各温度計３Ａ，３Ｂ，３Ｃ，３Ｄ，３Ｅ，３Ｆによりそ
れぞれ測定された温度に基づいて、補正演算回路６にて
計装配管の水柱密度を自動的に温度補正することによ
り、原子炉の水位を自動的に求めるようにしてもよい。
これにより、原子炉水位計の自動温度補正を行なうこと
が可能となる。For example, as shown in FIG.
A correction calculation circuit 6 is provided in place of the temperature recorder 4, and the correction calculation circuit 6 adjusts the instrumentation piping based on the temperature measured by each of the thermometers 3A, 3B, 3C, 3D, 3E, 3F. The water level of the reactor may be automatically obtained by automatically correcting the temperature of the water column density.
This makes it possible to perform automatic temperature correction of the reactor water level gauge.
【００３１】（ｂ）上記実施例においては、温度計を高
圧側および低圧側の計装配管にそれぞれ設ける場合につ
いて説明したが、これに限らず高圧側または低圧側の計
装配管のうち低圧側の計装配管にのみ温度計を設けるよ
うにしてもよい。(B) In the above embodiment, the case where the thermometers are provided on the high-pressure side and low-pressure side instrumentation pipes has been described, but the present invention is not limited to this, and the low-pressure side of the high-pressure side or low-pressure side instrumentation pipes is not limited to this. You may make it provide a thermometer only to the instrumentation piping of.
【００３２】（ｃ）上記実施例においては、各温度計３
Ａ，３Ｂ，３Ｃ，３Ｄ，３Ｅ，３Ｆとして、熱電対を用
いる場合について説明したが、これに限らず温度測定手
段として例えば光ファイバー温度分布センサ（ＯＴＤ
Ｒ：Ｏｐｔｉｃａｌ ＴｉｍｅＤｒａｉｎ Ｒｅｆｌｅ
ｃｔｍｅｔｒｙ）を用いるようにしてもよい。これによ
り、計装配管全体の平均温度を測定することができ、原
子炉の水位をより一層精度よく測定することが可能とな
る。(C) In the above embodiment, each thermometer 3
The case where a thermocouple is used as A, 3B, 3C, 3D, 3E, and 3F has been described, but the present invention is not limited to this, and as the temperature measuring means, for example, an optical fiber temperature distribution sensor (OTD).
R: Optical TimeDrain Reflect
ctmetry) may be used. As a result, the average temperature of the entire instrumentation pipe can be measured, and the water level of the reactor can be measured more accurately.
【００３３】[0033]
【発明の効果】以上説明したように本発明によれば、原
子炉水位計のドライウェル内の計装配管の水柱密度を校
正することにより、原子炉の水位を測定する装置におい
て、計装配管の垂直方向に設けられ、当該計装配管の表
面温度を測定する複数の温度測定手段と、各温度測定手
段によりそれぞれ測定された温度を記録する温度記録手
段とを備え、温度記録手段による記録結果に基づいて計
装配管の水柱密度を温度補正するか、または計装配管の
垂直方向に設けられ、当該計装配管の表面温度を測定す
る複数の温度測定手段と、各温度測定手段によりそれぞ
れ測定された温度に基づいて、計装配管の水柱密度を自
動的に温度補正する補正演算手段とを備えて構成したの
で、原子炉の水位を正確に測定できると共に、原子炉水
位計の校正作業を容易に行なうことが可能な極めて信頼
性の高い原子炉水位測定装置が提供できる。As described above, according to the present invention, in the device for measuring the water level of the reactor by calibrating the water column density of the instrumentation pipe in the dry well of the reactor water level gauge, , Which is provided in the vertical direction and has a plurality of temperature measuring means for measuring the surface temperature of the instrumentation pipe, and a temperature recording means for recording the temperature measured by each temperature measuring means. The temperature of the water column density of the instrumentation pipe is corrected based on the above, or it is provided in the vertical direction of the instrumentation pipe and measured by a plurality of temperature measurement means for measuring the surface temperature of the instrumentation pipe and each temperature measurement means. Based on the measured temperature, it is equipped with correction calculation means that automatically corrects the temperature of the water column density of the instrumentation pipe, so the water level of the reactor can be measured accurately and the calibration work of the reactor water level gauge can be performed. Very capable of performing the easy reliable reactor water level measuring device can be provided.
【図１】本発明による原子炉水位測定装置の一実施例を
示すブロック図。FIG. 1 is a block diagram showing an embodiment of a reactor water level measuring device according to the present invention.
【図２】本発明による原子炉水位測定装置の他の実施例
を示すブロック図。FIG. 2 is a block diagram showing another embodiment of the reactor water level measuring device according to the present invention.
【図３】従来の方法による原子炉水位測定の概要を説明
するためのブロック図。FIG. 3 is a block diagram for explaining an outline of reactor water level measurement by a conventional method.
１…原子炉格納容器（ＲＰＶ）、２…原子炉水位計（Ｌ
Ｔ）、３Ａ，３Ｂ，３Ｃ，３Ｄ，３Ｅ，３Ｆ…温度計、
４…温度記録計、５…原子炉圧力容器（ＰＣＶ）、６…
補正演算回路。1 ... Reactor containment vessel (RPV), 2 ... Reactor water gauge (L
T) 3A, 3B, 3C, 3D, 3E, 3F ... thermometer,
4 ... Temperature recorder, 5 ... Reactor pressure vessel (PCV), 6 ...
Correction arithmetic circuit.
Claims (5)
管の水柱密度を校正することにより、原子炉の水位を測
定する装置において、 前記計装配管の垂直方向に設けられ、当該計装配管の表
面温度を測定する複数の温度測定手段と、 前記各温度測定手段によりそれぞれ測定された温度を記
録する温度記録手段とを備えて成り、 前記温度記録手段による記録結果に基づいて前記計装配
管の水柱密度を温度補正するようにしたことを特徴とす
る原子炉水位測定装置。1. An apparatus for measuring the water level of a reactor by calibrating the water column density of the instrumentation pipe in a dry well of a reactor water level gauge, which is provided in the vertical direction of the instrumentation pipe. It comprises a plurality of temperature measuring means for measuring the surface temperature of the pipe, and a temperature recording means for recording the temperature measured by each of the temperature measuring means, and the instrumentation based on the recording result by the temperature recording means. A reactor water level measuring device characterized in that the water column density of piping is temperature-corrected.
管の水柱密度を校正することにより、原子炉の水位を測
定する装置において、 前記計装配管の垂直方向に設けられ、当該計装配管の表
面温度を測定する複数の温度測定手段と、 前記各温度測定手段によりそれぞれ測定された温度に基
づいて、前記計装配管の水柱密度を自動的に温度補正す
る補正演算手段と、 を備えて成ることを特徴とする原子炉水位測定装置。2. An apparatus for measuring the water level of a reactor by calibrating the water column density of the instrumentation piping in a dry well of a reactor water level gauge, which is provided in the vertical direction of the instrumentation piping, A plurality of temperature measuring means for measuring the surface temperature of the pipe, and a correction calculating means for automatically temperature-correcting the water column density of the instrumentation pipe based on the temperature measured by each of the temperature measuring means. A reactor water level measuring device characterized by comprising:
たは低圧側の計装配管のうち少なくとも低圧側の計装配
管に設けるようにしたことを特徴とする請求項１または
２に記載の原子炉水位測定装置。3. The atom according to claim 1 or 2, wherein each of the temperature measuring means is provided in at least a low-pressure side instrumentation pipe among high-pressure side or low-pressure side instrumentation pipes. Reactor water level measuring device.
ー温度分布センサを用いるようにしたことを特徴とする
請求項１または２に記載の原子炉水位測定装置。4. The reactor water level measuring device according to claim 1, wherein an optical fiber temperature distribution sensor is used as the temperature measuring means.
測定手段から離間した部所に設けるようにしたことを特
徴とする請求項１に記載の原子炉水位測定装置。5. The reactor water level measuring device according to claim 1, wherein the temperature recording means is provided at a position separated from each of the temperature measuring means.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4092868A JPH05288590A (en) | 1992-04-13 | 1992-04-13 | Nuclear reactor water level measuring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4092868A JPH05288590A (en) | 1992-04-13 | 1992-04-13 | Nuclear reactor water level measuring device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH05288590A true JPH05288590A (en) | 1993-11-02 |
Family
ID=14066414
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4092868A Pending JPH05288590A (en) | 1992-04-13 | 1992-04-13 | Nuclear reactor water level measuring device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH05288590A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009271056A (en) * | 2008-04-09 | 2009-11-19 | Toshiba Corp | Device for measuring water level of nuclear reactor and method for measuring water level of nuclear reactor |
| JP2014041023A (en) * | 2012-08-21 | 2014-03-06 | Hitachi Ltd | Reactor water-level meter |
| KR101395103B1 (en) * | 2012-09-03 | 2014-05-19 | 동국대학교 경주캠퍼스 산학협력단 | An auxiliary monitoring system for spent fuel pool at nuclear power plant and the monitoring method using the same |
-
1992
- 1992-04-13 JP JP4092868A patent/JPH05288590A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009271056A (en) * | 2008-04-09 | 2009-11-19 | Toshiba Corp | Device for measuring water level of nuclear reactor and method for measuring water level of nuclear reactor |
| JP2014041023A (en) * | 2012-08-21 | 2014-03-06 | Hitachi Ltd | Reactor water-level meter |
| KR101395103B1 (en) * | 2012-09-03 | 2014-05-19 | 동국대학교 경주캠퍼스 산학협력단 | An auxiliary monitoring system for spent fuel pool at nuclear power plant and the monitoring method using the same |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| KR101158459B1 (en) | Method and installation for monitoring the core of a nuclear reactor | |
| CN103903661B (en) | A kind of manostat water level measurement system and method after accident | |
| CN112129415B (en) | Transformer substation infrared temperature measurement device and method based on temperature dynamic calibration | |
| KR100199383B1 (en) | Improved method for steam generator water level measurement background of the invention | |
| US5533074A (en) | Nuclear reactor coolant level monitoring system | |
| JPH05288590A (en) | Nuclear reactor water level measuring device | |
| US5214957A (en) | Integrity and leak rate testing of a hermetic building | |
| JP4918345B2 (en) | Subcriticality measuring method, subcriticality measuring program, and subcriticality measuring apparatus | |
| McKee et al. | Calibration stability of oxygen meters for LMFBR sodium systems | |
| CN115050496A (en) | Single-point calibration method for external detector of pressurized water reactor | |
| CN114334197A (en) | Primary loop water charge monitoring method and system in low operation mode | |
| CN112629707A (en) | Heating furnace system precision testing method | |
| JPS59137823A (en) | Measuring device for water level in container | |
| JP2001324590A (en) | System for measuring water level of nuclear reactor | |
| JPH04232497A (en) | Apparatus for monitoring output distribution of core, reactor protecting apparatus, detector apparatus for core of reactor and method for monitoring coreof reactor | |
| JPS59193398A (en) | Reactor power distribution monitoring device | |
| JP3442598B2 (en) | Fixed in-core instrumentation system | |
| JPH0554917B2 (en) | ||
| CN115388986A (en) | Transmitter data processing method and system based on linear function | |
| US4652251A (en) | Determining the difference between the temperature of a liquid flowing in a closed system and its saturation temperature | |
| JP2521683B2 (en) | Reactor power distribution monitor | |
| JP3579024B2 (en) | Reactor power monitoring device | |
| JPS63275995A (en) | Apparatus for measuring concentration of hydrogen in reactor container | |
| JPS60228911A (en) | Automatic hardness corrector for thickness gauge | |
| JPH0551117B2 (en) |