JP2557885B2 - Differential pressure reactor water level measuring device - Google Patents

Differential pressure reactor water level measuring device

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Publication number
JP2557885B2
JP2557885B2 JP62118993A JP11899387A JP2557885B2 JP 2557885 B2 JP2557885 B2 JP 2557885B2 JP 62118993 A JP62118993 A JP 62118993A JP 11899387 A JP11899387 A JP 11899387A JP 2557885 B2 JP2557885 B2 JP 2557885B2
Authority
JP
Japan
Prior art keywords
reactor
water level
water column
containment vessel
differential pressure
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 - Fee Related
Application number
JP62118993A
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Japanese (ja)
Other versions
JPS63285492A (en
Inventor
貞男 黒沢
幸雄 村田
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 Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
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Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP62118993A priority Critical patent/JP2557885B2/en
Publication of JPS63285492A publication Critical patent/JPS63285492A/en
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Publication of JP2557885B2 publication Critical patent/JP2557885B2/en
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Expired - Fee Related legal-status Critical Current

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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

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  • Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は原子炉圧力容器の炉水位を測定するのに好適
な差圧式原子炉水位測定装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Industrial Application] The present invention relates to a differential pressure type reactor water level measuring apparatus suitable for measuring the reactor water level of a reactor pressure vessel.

(従来の技術) 炉水位の測定には各種方式があるが、原子炉発電プラ
ントにおいては、運転中原子炉格納容器内での保守点検
作業の必要のない差圧式原子炉水位測定装置が使用され
る。
(Prior Art) There are various methods for measuring the reactor water level, but in the reactor power plant, a differential pressure type reactor water level measuring device that does not require maintenance and inspection work in the reactor containment vessel during operation is used. It

第4図はそのような差圧式原子炉水位測定装置の従来
例を示したもので、原子炉格納容器1内に収納される原
子炉圧力容器2には、内部に連通して、炉水位が取り得
る上限位置に基準水柱配管3,下限位置に変動水柱配管4
が取り付けられている。これら水柱配管3,4は原子炉格
納容器1を貫通して原子炉水位測定装置5の差圧伝送器
6に接続され、そこで上下限位置の炉水位差圧ΔPが検
出される。検出された差圧ΔPは水位演算装置7に取り
込まれて炉水位Lが算出され、インジケータ8に表示さ
れる。この構成により原子炉格納容器1内での保守点検
作業が一切不要にして原子炉格納容器1外部で原子炉圧
力容器2の水位が測定できる。
FIG. 4 shows a conventional example of such a differential pressure type reactor water level measuring device. The reactor pressure vessel 2 housed in the reactor containment vessel 1 communicates with the inside and the reactor water level is Standard water column piping 3 at the upper limit position and variable water column piping 4 at the lower limit position
Is attached. These water column pipes 3 and 4 penetrate the reactor containment vessel 1 and are connected to the differential pressure transmitter 6 of the reactor water level measuring device 5, where the reactor water level differential pressure ΔP at the upper and lower limit positions is detected. The detected differential pressure ΔP is taken into the water level calculator 7 to calculate the reactor water level L and displayed on the indicator 8. With this configuration, the maintenance and inspection work inside the reactor containment vessel 1 is not necessary at all, and the water level of the reactor pressure vessel 2 can be measured outside the reactor containment vessel 1.

(発明が解決しようとする問題点) しかしながら、上記従来装置においては、炉水位差圧
ΔPから炉水位Lを算出するのに、両者が線形関係にあ
るものとして、 L=S×ΔP+β ……(1) とおき、比例定数δと定数項βを定格運転時の実測値を
基に一義的に決定して炉水位を測定していた。
(Problems to be Solved by the Invention) However, in the above-described conventional apparatus, in calculating the reactor water level L from the reactor water level differential pressure ΔP, it is assumed that the two have a linear relationship, and L = S × ΔP + β. 1), the proportional constant δ and the constant term β were uniquely determined based on the measured values during rated operation to measure the reactor water level.

このため、上記従来装置においては、原子炉の運転が
定格運転から外れると、炉内の温度,圧力が大きく変動
することから、測定誤差が非常に大きくなる。例えば、
圧力が定格運転状態から変化した場合、第5図に示すよ
うに、大きな測定誤差が生じる。この測定誤差は、炉水
位の下限位置を0、上限位置1500mmとしたときに、上限
位置に近くなる程大きくなり、測定装置としての使用に
耐えなくなる問題点があった。
Therefore, in the above-described conventional apparatus, when the operation of the nuclear reactor deviates from the rated operation, the temperature and pressure inside the reactor fluctuate greatly, resulting in a very large measurement error. For example,
When the pressure changes from the rated operating state, a large measurement error occurs as shown in FIG. When the lower limit position of the reactor water level is set to 0 and the upper limit position is set to 1500 mm, this measurement error becomes larger as it approaches the upper limit position, and there is a problem that it cannot be used as a measuring device.

そこで本発明は、上記問題点を解決した原子炉運転状
態の如何によらず炉水位を精度良く測定できる差圧式原
子炉水位測定装置を提供することを目的とする。
Therefore, an object of the present invention is to provide a differential pressure type reactor water level measuring device which can solve the above problems and accurately measure the reactor water level regardless of the operating state of the reactor.

[発明の構成] (問題点を解決するための手段) 本発明は、そのときの温度,圧力に応じた炉水位上限
時の炉水位差圧WC(U)と炉水位下限時の炉水位差圧WC
(L)を計算により求め、これら炉水位差圧WC(U),W
c(L)と、炉水位上下限位置間の距離lと、差圧伝送
器で実測した炉水位差圧ΔPとを基に、上下限位置間の
炉水位 を算出する水位補正演算装置を設けるようにしたもので
ある。
[Structure of the Invention] (Means for Solving Problems) The present invention is directed to a reactor water level differential pressure W C (U) at the time of the reactor water level upper limit and a reactor water level at the time of the reactor water level lower limit according to the temperature and pressure at that time. Differential pressure W C
(L) is calculated and the reactor water level differential pressure W C (U), W
Based on c (L), the distance l between the reactor water level upper and lower limit positions, and the reactor water level differential pressure ΔP measured by the differential pressure transmitter, the reactor water level between the upper and lower limit positions A water level correction calculation device for calculating is calculated.

(作用) この構成により、原子炉の運転状態が定格を外れて炉
内の温度,圧力が大きく変動しても、この温度,圧力を
考慮した炉水位Lが算出され、誤差の少ない炉水位Lが
測定できる。
(Operation) With this configuration, even if the operating state of the nuclear reactor deviates from the rated value and the temperature and pressure inside the reactor fluctuate significantly, the reactor water level L considering this temperature and pressure is calculated, and the reactor water level L with less error is calculated. Can be measured.

(実施例) 第1図は、本発明の一実施例による差圧式原子炉水位
測定装置のブロツク図を示したものである。図中、第4
図と同一符号は同一または相当部分を示し、第4図と異
なる点は水位演算装置7の代りに温度と圧力に応じて補
正した炉水位を算出する水位補正演算装置9を設けた点
である。
(Embodiment) FIG. 1 is a block diagram of a differential pressure reactor water level measuring device according to an embodiment of the present invention. 4th in the figure
The same reference numerals as those in the figure indicate the same or corresponding portions, and the difference from FIG. 4 is that a water level correction calculation device 9 for calculating the reactor water level corrected according to temperature and pressure is provided instead of the water level calculation device 7. .

この水位補正演算装置9は、第2図に示すように、原
子炉格納容器外における基準水柱配管の温度を検出する
原子炉格納容器外基準水柱配管温度検出器11と、原子炉
格納容器外における前記変動水柱配管の温度を検出する
原子炉格納容器外変動水柱配管温度検出器12と、原子炉
格納容器内における前記基準水柱配管の温度を検出する
原子炉格納容器内基準水柱配管温度検出器13と、原子炉
格納容器内における前記変動水柱配管の温度を検出する
原子炉格納容器内変動水柱配管温度検出器14と、原子炉
圧力容器内の炉水温度を検出する炉水温度検出器15と、
原子炉圧力容器内の蒸気圧を検出する原子炉圧力容器内
蒸気圧検出器16と、原子炉格納容器外基準水柱配管温度
検出器及び原子炉格納容器外変動水柱配管温度検出器が
検出した温度の平均を取る原子炉格納容器外水柱配管温
度平均装置17と、原子炉格納容器内基準水柱配管温度検
出器及び原子炉格納容器内変動水柱配管温度検出器が検
出した温度の平均を取る原子炉格納容器内水柱配管温度
平均装置18と、前記原子炉圧力容器内蒸気圧検出器、前
記原子炉格納容器外水柱配管温度平均装置及び原子炉格
納容器内水柱配管温度平均装置から得られる、そのとき
の圧力及び温度における炉水位上限時の炉水位差圧W
C(U)及び炉水位下限時の炉水位差圧WC(L)を計算
により求める炉水位差圧WC(U)計算手段19及炉水位差
圧WC(L)計算手段20とを備えた炉水位上下限差圧補正
計算手段21と、メモリ22と、炉水位算出手段23とから構
成される。
As shown in FIG. 2, the water level correction computing device 9 includes a reference water column piping temperature detector 11 outside the reactor containment vessel for detecting the temperature of the reference water column piping outside the reactor containment vessel, and a reactor outside the reactor containment vessel. Fluctuating water column piping temperature detector 12 outside the reactor containment vessel for detecting the temperature of the fluctuating water column piping, and reference water column piping temperature detector 13 inside the reactor containment vessel for detecting the temperature of the reference water column piping inside the reactor containment vessel And a variable water column piping temperature detector 14 in the reactor containment vessel that detects the temperature of the variable water column piping in the reactor containment vessel, and a reactor water temperature detector 15 that detects the reactor water temperature in the reactor pressure vessel. ,
Temperature detected by the vapor pressure detector 16 inside the reactor pressure vessel that detects the vapor pressure inside the reactor pressure vessel, the reference water column piping temperature detector outside the reactor containment vessel, and the variable water column piping temperature detector outside the reactor containment vessel Of the temperature of the water column piping outside the reactor containment vessel and the reference temperature of the water column piping inside the reactor containment vessel and the temperature of the fluctuation water column piping inside the reactor containment vessel Obtained from the water column piping temperature averaging device 18 in the containment vessel, the vapor pressure detector in the reactor pressure vessel, the water column piping temperature averaging device outside the reactor containment vessel and the water column piping temperature averaging device in the reactor containment vessel, at that time Water level differential pressure W at the upper limit of reactor water level at various pressures and temperatures
C (U) and reactor water level differential pressure W C (L) at the lower limit of reactor water level are calculated by calculating reactor water level differential pressure W C (U) calculating means 19 and reactor water level differential pressure W C (L) calculating means 20. The reactor water level upper / lower limit differential pressure correction calculation means 21 is provided, a memory 22, and a reactor water level calculation means 23.

以上の構成で、第1図に示すように、今、原子炉圧力
容器2の炉水位Lと炉水位上限位置に取り付けられる基
準水柱配管3のA部間の距離をl1、炉水位Lと変動水柱
配管4のA′部間の距離をl2、変動水柱配管4のA′部
とB′部間の距離をl3、基準水柱配管3のA部とB部間
の距離をl4、基準水柱配管3のB部と変動水柱配管4の
B′部間の距離をl5、基準水柱配管3のA部と変動水柱
配管4のA′部間の距離をlとする。
With the above configuration, as shown in FIG. 1 , the distance between the reactor water level L of the reactor pressure vessel 2 and the A portion of the reference water column pipe 3 attached to the reactor water level upper limit position is now l 1 , and the reactor water level L is The distance between the A'part of the variable water column pipe 4 is l 2 , the distance between the A'part and the B'part of the variable water column pipe 4 is l 3 , and the distance between the A and B parts of the reference water column pipe 3 is l 4 The distance between the B part of the standard water column pipe 3 and the B'part of the variable water column pipe 4 is l 5 , and the distance between the A part of the standard water column pipe 3 and the A'part of the variable water column pipe 4 is l.

また、 Va:基準温度における水比容積(定数) Vg:そのときの原子炉圧力容器内蒸気圧に応じた原子炉
圧力容器内飽和蒸気容積 Vf1:そのときの炉水温度に応じた原子炉圧力容器内飽和
水比容積 Vc:そのときの原子炉格納容器内水柱配管平均温度に応
じた原子炉格納容器内水柱配管中の加圧水比容積 Vt:そのときの原子炉格納容器外水柱配管平均温度に応
じた原子炉格納容器外水柱配管中の加圧水比容積 l(1,L):原子炉水位測定装置下限におけるl1(定
数) l(2,L):原子炉水位測定装置下限におけるl2(定
数) l(1,U):原子炉水位測定装置上限におけるl1(定
数) l(2,U):原子炉水位測定装置上限におけるl2(定
数) と定義すると、基準水性ラインA,B,C,Dにおける圧力PA,
PB,PC,PDは、 PA=P∞−l1/Vg ……(2) PB=PA+l4/Vc ……(3) PC=PB+(l4−l4)/Vt=PB ……(4) PD=PC+l5/Vt ……(5) と表わされる。また、変動水柱ラインA′,B′,C′にお
ける圧力AA′,PB′,PC′は、 PA′=P∞+l2/Vf1 ……(6) PB′=PA′+l3/Vc ……(7) PC′=PB′+(l3−l3)/Vt=PB′ ……(8) となる。これにより、差圧伝送器6に得られる理論上の
差圧DPは、 DP=PC′−PD =(l1/Vg+l2/Vf1+l3/Vc)−(l4/Vc+l5/Vt ……
(9) と表わすことができる。従って、この(9)式と前記定
義を用いて、炉水位が上限位置LUにあるときの炉水位差
圧WC(U)を計算により求めると、 WC(U)=Va[(l(1,U)/Vg+l(2,U)/Vf1 +l3/Vc)−(l4/Vc+l5/Vt)] ……(10) となる。同様にして炉水位が下限位置LLにあるときの炉
水位差圧WC(L)は、 WC(L) =Va[(l(1,L)/Vg+l(2,L)/Vf1 +l3/Vc)−(l4/Vc+l5/Vt)] ……(11) と求まる。
Va: Specific water volume (constant) at the reference temperature Vg: Saturated steam volume in the reactor pressure vessel according to the steam pressure in the reactor pressure vessel at that time Vf 1 : Reactor according to the reactor water temperature at that time Specific volume of saturated water in the pressure vessel Vc: Specific volume of pressurized water in the water column piping in the reactor containment vessel according to the average temperature of the water column piping in the reactor containment vessel at that time Vt: Average temperature of the water column piping outside the reactor containment vessel at that time Specific volume of pressurized water in the water column piping outside the reactor containment vessel according to the following: l ( 1 , L ): l 1 (constant) at the lower limit of the reactor water level measurement device l ( 2 , L ): l 2 at the lower limit of the reactor water level measurement device (Constant) l ( 1 , U ): l 1 at the upper limit of the reactor water level measuring device l (Constant) l ( 2 , U ): l 2 at the upper limit of the reactor water level measuring device If defined as the (constant), the reference aqueous line A, Pressure at B, C, D P A ,
P B , P C , P D is P A = P ∞ −l 1 / Vg …… (2) P B = P A + l 4 / Vc …… (3) P C = P B + (l 4 −l 4 ) / Vt = P B …… (4) P D = P C + l 5 / Vt …… (5) The pressure A A ′, P B ′, P C ′ in the fluctuating water column lines A ′, B ′, C ′ is P A ′ = P ∞ + l 2 / Vf 1 (6) P B ′ = P A ′ + l 3 / Vc …… (7) PC C ′ = P B ′ + (l 3 −l 3 ) / Vt = P B ′ …… (8). Thus, the differential pressure DP of the theoretical obtained differential pressure transmitter 6, DP = P C '-P D = (l 1 / Vg + l 2 / Vf 1 + l 3 / Vc) - (l 4 / Vc + l 5 / Vt ……
It can be expressed as (9). Therefore, when the reactor water level differential pressure W C (U) when the reactor water level is at the upper limit position L U is calculated by using this equation (9) and the above definition, W C (U) = V a [( l ( 1 , U ) / V g +1 ( 2 , U ) / Vf 1 + l 3 / Vc) − (l 4 / Vc + l 5 / Vt)] ... (10). Similarly, when the reactor water level is at the lower limit position L L , the reactor water level differential pressure W C (L) is W C (L) = Va [(l ( 1 , L ) / Vg + l ( 2 , L ) / Vf 1 + l 3 / Vc) - ( l 4 / Vc + l 5 / Vt)] obtained with the ... (11).

一方、炉水位差圧と炉水位が線形関係にあるものとし
て、上記(10),(11)式で計算により求めた炉水位上
下限位置における差圧WC(U),WC(L)を用いて実測
した炉水位差圧ΔPからそのときの炉水位Lを求める
と、 となり、そのときの温度,圧力を考慮した誤差の小さい
炉水位Lが得られる。
On the other hand, assuming that there is a linear relationship between the reactor water level differential pressure and the reactor water level, the differential pressure W C (U), W C (L) at the reactor water level upper and lower limit positions calculated by the equations (10) and (11) above. When the reactor water level L at that time is obtained from the reactor water level differential pressure ΔP measured using And the reactor water level L with a small error in consideration of the temperature and pressure at that time is obtained.

これを実現する具体的ブロック構成図が第2図で、炉
水位上下限差圧補正計算手段21にはl1〜l5,l,Va等の固
定情報が予め記憶されている。
A concrete block diagram for realizing this is shown in FIG. 2, and fixed information such as l 1 to l 5 , l, Va is stored in advance in the reactor water level upper and lower limit differential pressure correction calculation means 21.

一方、各検出器11〜16および平均装置17,18を介し
て、そのときの水性配管温度平均値,炉水温度,炉内蒸
気圧力が炉水位上下限差圧補正計算手段21に取り込ま
れ、これら温度,圧力に応じたVg,Vf1,Vc,Vtが計算され
る。
On the other hand, through each of the detectors 11 to 16 and the averaging devices 17 and 18, the aqueous pipe temperature average value at that time, the reactor water temperature, and the in-reactor steam pressure are taken into the reactor water level upper and lower limit differential pressure correction calculation means 21, Vg, Vf 1 , Vc, and Vt corresponding to these temperatures and pressures are calculated.

次いで、これらの計算値とメモリ22からの記憶データ
を基に炉水位上限時の炉水位差圧WC(U)計算手段19,
炉水位下限時の炉水位差圧WC(L)計算手段20にて前記
(10),(11)式に従った炉水位上下限差圧WC(U),W
C(L)が算出される。
Next, based on these calculated values and the stored data from the memory 22, the reactor water level differential pressure W C (U) calculating means 19, when the reactor water level is at the upper limit,
Reactor water level differential pressure W C (L) at the reactor water level lower limit The reactor water level upper and lower limit differential pressure W C (U), W according to the equations (10) and (11) calculated by the calculating means 20.
C (L) is calculated.

これにより、炉水位算出手段23では、炉水位上下限差
圧補正計算手段21からWC(U),WC(L)、メモリ22か
らl、差圧伝送器6からΔPを取り込み、前記(12)式
を計算することにより、炉水位Lを求めることができ
る。
As a result, the reactor water level calculation means 23 fetches W C (U) and W C (L) from the reactor water level upper and lower limit differential pressure correction calculation means 21, the memory 22 from l, and ΔP from the differential pressure transmitter 6, and The reactor water level L can be obtained by calculating the equation (12).

このようにして水位補正演算装置9で補正計算した炉
水位Lをインジケータ8に表示することにより、原子炉
の運転状態によらず炉水位Lを精度良く測定表示するこ
とができる。
In this way, by displaying the reactor water level L corrected and calculated by the water level correction arithmetic unit 9 on the indicator 8, the reactor water level L can be accurately measured and displayed regardless of the operating state of the reactor.

第3図は、このときの測定誤差を示したもので、第5
図に示した従来の場合と比較して、定格運転状態を大き
く外れた場合でも測定誤差が非常に小さくなっているこ
とが判る。
FIG. 3 shows the measurement error at this time.
It can be seen that the measurement error is much smaller than the conventional case shown in the figure even when the rated operating state is greatly deviated.

なお、水位補正演算装置9内の演算処理は、アナログ
演算装置により実現してもよく、あるいは、マイクロコ
ンピュータや電子計算機を用いて実現してもよい。
The arithmetic processing in the water level correction arithmetic device 9 may be realized by an analog arithmetic device, or may be realized by using a microcomputer or an electronic calculator.

[発明の効果] 以上説明したように本発明によれば、原子炉の運転状
態の如何によらず、炉水位を精度良く測定することので
きる差圧式原子炉水位測定装置が得られる。
[Effect of the Invention] As described above, according to the present invention, a differential pressure type reactor water level measuring device capable of accurately measuring the reactor water level regardless of the operating state of the reactor can be obtained.

【図面の簡単な説明】 第1図は本発明の一実施例を示す差圧式原子炉水位測定
装置のブロック構成図、第2図は第1図の水位補正演算
装置の詳細ブロック図、第3図は第1図の装置による測
定誤差の実測図、第4図は従来の差圧式原子炉水位測定
装置のブロック構成図、第5図は第4図の装置による測
定誤差実測図である。 6……差圧伝送器、9……水位補正演算装置、15……炉
水温度検出器、16……原子炉圧力容器内蒸気圧検出器、
17……原子炉格納容器外水柱配管温度平均装置、18……
原子炉格納容器内水柱配管温度平均装置18、19……水位
上限時の炉水位差圧WC(U)計算手段、20……炉水位下
限時の炉水位差圧WC(L)計算手段、21……炉水位上下
限差圧補正計算手段、22……メモリ、23……炉水位算出
手段。
BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a block configuration diagram of a differential pressure reactor water level measuring device showing an embodiment of the present invention, FIG. 2 is a detailed block diagram of a water level correction computing device of FIG. 1, and FIG. FIG. 4 is an actual measurement diagram of measurement error by the apparatus of FIG. 1, FIG. 4 is a block diagram of a conventional differential pressure type reactor water level measurement apparatus, and FIG. 5 is an actual measurement figure of measurement error by the apparatus of FIG. 6 ... Differential pressure transmitter, 9 ... Water level correction calculation device, 15 ... Reactor water temperature detector, 16 ... Reactor pressure vessel vapor pressure detector,
17 …… Temperature averaging device for the water column outside the reactor containment vessel, 18 ……
Water column piping temperature averaging device in the reactor containment vessel 18, 19 …… Reactor water level differential pressure W C (U) calculation means at water level upper limit, 20 …… Reactor water level differential pressure W C (L) calculation means at reactor water level lower limit , 21 …… Reactor water level upper / lower limit differential pressure correction calculation means, 22 …… Memory, 23 …… Reactor water level calculation means.

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】原子炉圧力容器の炉水位上限位置に取り付
けられた基準水柱配管と該基準水柱配管と距離lの位置
であって、炉水位下限位置に取り付けられた変動水柱配
管とを差圧伝送器に接続して炉水位差圧ΔPを検出し、
検出した炉水位差圧ΔPに基づいて炉水位Lを算出し、
インジケータに表示する差圧式原子炉水位測定装置にお
いて、 原子炉圧力容器内の炉水温度を検出する炉水温度検出器
と、 原子炉圧力容器内の蒸気圧を検出する原子炉圧力容器内
蒸気圧検出器と、 原子炉格納容器内における前記基準水柱配管の温度を検
出する原子炉格納容器内基準水柱配管温度検出器と、 原子炉格納容器外における前記基準水柱配管の温度を検
出する原子炉格納容器外基準水柱配管温度検出器と、 原子炉格納容器内における前記変動水柱配管の温度を検
出する原子炉格納容器内変動水柱配管温度検出器と、 原子炉格納容器外における前記変動水柱配管の温度を検
出する原子炉格納容器外変動水柱配管温度検出器と、 原子炉格納容器外基準水柱配管温度検出器及び原子炉格
納容器外変動水柱配管温度検出器が検出した温度の平均
を取る原子炉格納容器外水柱配管温度平均装置と、 原子炉格納容器内基準水柱配管温度検出器及び原子炉格
納容器内変動水柱配管温度検出器が検出した温度の平均
を取る原子炉格納容器内水柱配管温度平均装置と、 前記原子炉圧力容器内蒸気圧検出器、前記原子炉格納容
器外水柱配管温度平均装置及び原子炉格納容器内水柱配
管温度平均装置から得られる、そのときの圧力及び温度
における炉水位上限時の炉水位差圧WC(U)及び炉水位
下限時の炉水位差圧WC(L)を計算により求める炉水位
上下限差圧補正計算手段と、 前記炉水位差圧WC(U),WC(L)、前記距離l及び前
記炉水位差圧ΔPを基に炉水位Lを L=(ΔP−WC(L))×l/(WC(U)−WC(L)) として算出する炉水位算出手段と、 を備える水位補正演算装置を設けたことを特徴とする差
圧式原子炉水位測定装置。
1. A differential pressure between a reference water column pipe attached to a reactor water level upper limit position of a reactor pressure vessel and a variable water column pipe attached at a distance l from the reference water column lower limit position at a reactor water level lower limit position. Connect to the transmitter to detect the reactor water level differential pressure ΔP,
The reactor water level L is calculated based on the detected reactor water level differential pressure ΔP,
In the differential pressure type reactor water level measuring device displayed on the indicator, the reactor water temperature detector that detects the reactor water temperature in the reactor pressure vessel and the reactor pressure vessel vapor pressure that detects the vapor pressure in the reactor pressure vessel Detector and reference water column piping temperature detector inside the reactor containment vessel that detects the temperature of the reference water column piping inside the reactor containment vessel, and reactor containment that detects the temperature of the reference water column piping outside the reactor containment vessel Reference water column piping temperature detector outside the vessel, fluctuation water column piping temperature detector inside the reactor containment vessel that detects the temperature of the fluctuation water column piping inside the reactor containment vessel, and temperature of the fluctuation water column piping outside the reactor containment vessel The temperature detected by the fluctuation water column piping temperature detector outside the reactor containment vessel, the reference water column piping temperature detector outside the reactor containment vessel, and the fluctuation water column piping temperature detector outside the reactor containment vessel The average temperature of the water column piping outside the reactor containment vessel, the reference water column piping temperature detector inside the reactor containment vessel, and the fluctuation water column piping temperature detector inside the reactor containment vessel Water column piping temperature averaging device in the vessel, the reactor pressure vessel vapor pressure detector, the water column piping temperature averaging device outside the reactor containment vessel and the water column piping temperature averaging device in the reactor containment vessel, the pressure at that time And the reactor water level upper and lower limit differential pressure correction calculation means for calculating the reactor water level differential pressure W C (U) at the time of the reactor water level upper limit and the reactor water level differential pressure W C (L) at the time of the reactor water level lower limit, and the reactor water level Based on the differential pressures W C (U), W C (L), the distance 1 and the reactor water level differential pressure ΔP, the reactor water level L is L = (ΔP−W C (L)) × l / (W C (U ) -W C (L)) as a reactor water level calculation means, and A differential pressure type reactor water level measuring device characterized by being provided.
JP62118993A 1987-05-18 1987-05-18 Differential pressure reactor water level measuring device Expired - Fee Related JP2557885B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62118993A JP2557885B2 (en) 1987-05-18 1987-05-18 Differential pressure reactor water level measuring device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62118993A JP2557885B2 (en) 1987-05-18 1987-05-18 Differential pressure reactor water level measuring device

Publications (2)

Publication Number Publication Date
JPS63285492A JPS63285492A (en) 1988-11-22
JP2557885B2 true JP2557885B2 (en) 1996-11-27

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ID=14750347

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Country Link
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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5742875B2 (en) * 2012-05-16 2015-07-01 アイシー測器株式会社 Liquid transport vehicles such as vacuum cars and liquid collection and metering methods using the same
CN103854713B (en) * 2012-12-07 2016-08-31 中国核动力研究设计院 A kind of method determining disengagement surface

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61223693A (en) * 1985-03-29 1986-10-04 株式会社東芝 Instrumentation device for water level in nuclear reactor

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