JPS6138828B2 - - Google Patents
Info
- Publication number
- JPS6138828B2 JPS6138828B2 JP10360980A JP10360980A JPS6138828B2 JP S6138828 B2 JPS6138828 B2 JP S6138828B2 JP 10360980 A JP10360980 A JP 10360980A JP 10360980 A JP10360980 A JP 10360980A JP S6138828 B2 JPS6138828 B2 JP S6138828B2
- Authority
- JP
- Japan
- Prior art keywords
- water
- water discharge
- discharge nozzle
- radioactive
- cylindrical body
- 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
Links
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
- G01T7/02—Collecting means for receiving or storing samples to be investigated and possibly directly transporting the samples to the measuring arrangement; particularly for investigating radioactive fluids
Landscapes
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Description
本発明は、原子力プラント等から出される放射
性排水の放射能濃度を測定するための排水モニタ
に関するものである。
排水モニタにおいては、配管内壁に付着する放
射性物質からの放射線の影響をなくすため、放射
線計測を行なう配管では、排水をその配管内壁に
非接触で通水するようにしている。しかし、配管
内壁に非接触で通水する排水モニタは、排水流量
に応じて放射線計測の有効体積が変化するため、
正確な測定が困難である。この対策としては排水
流量を一定に保つか、ある一定の流量範囲内で変
化すること想定して誤差として取扱うことなどが
ある。
前者は一定流量に保つ制御機構が必要であり、
装置が複雑になる。また、後者はモニタとしての
精度が悪くなる欠点があつた。
本発明の目的は、上記従来技術の欠点を除去
し、流量の変動に無関係に、排水中の放射能濃度
を精度良く測定できる排水モニタを提供すること
にある。
以下本発明の実施例について図面を参照して説
明する。
第1図は、本発明の一実施例の全体構成図であ
り、第2図は、本実施例の効果を説明するための
図である。
第1図において、排水は送水ポンプ1で送水さ
れ、流量計2、整流管3、放水ノズル4を通過し
て、計測部の配管5の内壁に非接触で通水され
る。計測部を通過した排水6は矢印7方向に排水
する。洗浄水は常時一定流量で供給管8と案内板
9で放射線計測部の配管5の内壁に沿つて通水さ
れる。放水ノズル4から放水される排水の放射能
はしやへい体10に囲まれた放射線検出器11と
計数装置12で測定される。放水ノズル4から放
水される排水の放水形状は排水の流量に依存して
変化する。これは放射線計測される排水の有効体
積の変化となり、計測値の補正が必要となる。こ
の補正は計数装置12に補正演算部14を設けて
おき、流量計2の出力を信号回線13で送信し、
その信号に基づき補正演算を実行する。この補正
した値が計数装置の出力、すなわち排水モニタの
出力となる。
放水ノズル部に整流管などを設けて、送水ポン
プの吐出圧をほぼ大気圧に等しくすると、放水ノ
ズル部とその下流側ではベルヌーイの式が成立す
る。すなわち、放水ノズル部から放水される排水
の速度と放水形状は、放水ノズル部との位置水頭
で決定できる。
このことから、放水ノズル部とその下流におけ
る流速と放水形状の関係は以下のようになる。
R:放射線測定位置における放水形状の半径
R0:放水ノズルの半径
v0:放水ノズル部の排水流速
g:重力の加速度
h:放水ノズルの先端から放射線測定位置までの
水頭
ここで、R0とhは排水モニタの設計で一定値
となり、放水形状の半径Rは流量で決まる流速v0
の関数として求められる。この関係は実験的にも
証明できている。第2図に放水半径Rの計算値と
実測値の関係を示す。実際の補正値としてはv0が
2m/secのときのRを1とすると、v0が1m/sec
のときのRは0.78となる(但し、hは30cmであ
る)。この値に基づいて、有効体積の補正を実施
する。
放水している排水の放射線を十分コリメートし
て側面から測定する場合、計測される排水の有効
体積は放射線検出器が見込む放水形の中心軸の長
さと放射線検出器の中心位置における放水形の半
径からなる円柱状体積で近似できる。放射線検出
器が見込む放水形の中心軸の長さHは放水形の半
径Rが変化しても変わらない。
このことから有効体積の補正は、基準とする放
水形の半径をR、測定時の放水形の半径をR′と
した場合(R/R′)2を測定値に乗ずることにより
近似的に実施できる。
基準の放水形のノズル部流速をv0とし、測定時
のノズル部流速をv0′とすると、補正係数Fは
The present invention relates to a wastewater monitor for measuring the radioactivity concentration of radioactive wastewater discharged from a nuclear power plant or the like. In the drainage monitor, in order to eliminate the influence of radiation from radioactive substances adhering to the inner wall of the pipe, the waste water is passed through the inner wall of the pipe in a non-contact manner in the pipe where radiation measurement is performed. However, with drainage monitors that pass water through the inner wall of the pipe without contact, the effective volume for radiation measurement changes depending on the drainage flow rate.
Accurate measurement is difficult. Countermeasures include keeping the drainage flow rate constant, or assuming that it will change within a certain flow rate range and treating it as an error. The former requires a control mechanism to maintain a constant flow rate;
The equipment becomes complicated. Additionally, the latter had the disadvantage of poor accuracy as a monitor. SUMMARY OF THE INVENTION An object of the present invention is to eliminate the drawbacks of the conventional techniques described above and to provide a wastewater monitor that can accurately measure the radioactivity concentration in wastewater regardless of fluctuations in flow rate. Embodiments of the present invention will be described below with reference to the drawings. FIG. 1 is an overall configuration diagram of an embodiment of the present invention, and FIG. 2 is a diagram for explaining the effects of this embodiment. In FIG. 1, waste water is sent by a water pump 1, passes through a flow meter 2, a rectifier pipe 3, and a water discharge nozzle 4, and is passed through the inner wall of a pipe 5 of a measuring section without contacting it. The waste water 6 that has passed through the measuring section is drained in the direction of the arrow 7. Cleaning water is always passed at a constant flow rate along the inner wall of the pipe 5 of the radiation measurement section through the supply pipe 8 and the guide plate 9. The radioactivity of the waste water discharged from the water discharge nozzle 4 is measured by a radiation detector 11 surrounded by a shield body 10 and a counting device 12. The shape of the drainage water discharged from the water discharge nozzle 4 changes depending on the flow rate of the drainage water. This results in a change in the effective volume of wastewater that is measured by radiation, and requires correction of the measured value. For this correction, a correction calculation section 14 is provided in the counting device 12, and the output of the flowmeter 2 is transmitted through the signal line 13.
A correction calculation is performed based on the signal. This corrected value becomes the output of the counting device, that is, the output of the drainage monitor. If a rectifier pipe or the like is provided in the water discharge nozzle section to make the discharge pressure of the water pump approximately equal to atmospheric pressure, Bernoulli's equation will hold in the water discharge nozzle section and its downstream side. That is, the speed and shape of the water discharged from the water discharge nozzle can be determined by the head position relative to the water discharge nozzle. From this, the relationship between the flow velocity and the water discharge shape in the water discharge nozzle section and its downstream is as follows. R: Radius of the water discharge shape at the radiation measurement position R 0 : Radius of the water discharge nozzle v 0 : Drainage flow velocity at the water discharge nozzle g: Acceleration of gravity h: Water head from the tip of the water discharge nozzle to the radiation measurement position Here, R 0 and h is a constant value due to the design of the drainage monitor, and the radius R of the water discharge shape is determined by the flow rate v 0
It is found as a function of This relationship has also been experimentally proven. Figure 2 shows the relationship between the calculated value and the actually measured value of the water discharge radius R. As an actual correction value, if R is 1 when v 0 is 2 m/sec, then v 0 is 1 m/sec
In this case, R is 0.78 (however, h is 30 cm). Based on this value, the effective volume is corrected. When measuring from the side with sufficient collimation of the radiation from the discharged wastewater, the effective volume of the measured wastewater is determined by the length of the central axis of the discharge shape as expected by the radiation detector and the radius of the discharge shape at the center position of the radiation detector. It can be approximated by a cylindrical volume consisting of . The length H of the central axis of the water discharge shape that the radiation detector can see does not change even if the radius R of the water discharge shape changes. Therefore, the effective volume can be corrected approximately by multiplying the measured value by 2 (R/R'), where R is the radius of the reference water discharge shape and R' is the radius of the water discharge shape at the time of measurement. can. If the nozzle flow velocity of the standard water discharge type is v 0 and the nozzle flow velocity at the time of measurement is v 0 ', then the correction coefficient F is
【式】となる。ここで[Formula] becomes. here
【式】C2=2ghでいずれも一定値
である。
流量計2の出力信号をもとにしてv0′、Fを演
算して有効体積の補正を実施する。
第1図に示した補正演算部14の具体例は排水
の実測流量値から放水ノズル部の流速v0′を演算
し、上述した補正係数Fを演算し、放射能の測定
値へ乗ずることになる。
上述した例では、v0が2m/secの基準に対して
測定時の流速v0′が1m/secの場合、この補正は
計数値の1.64倍となる。
第2図に本実施例の装置によると実測値と理論
的計算値との関係を示す。図で、二重丸は実測値
を、実線は計算値を示している。
本発明によれば、放水ノズル部における放射性
排水の流速V0、放水ノズルの半径R0、重力加速
度g及び放水ノズルの下端から放射線検出器の設
定位置までの水頭hに基づいて放射線検出器の設
置位置における放射性排水の有効体積を補正する
とともに補正された放射性排水の有効体積を用い
て放射線検出器の出力信号を補正しているので、
放水ノズルに供給する放射性排水の流量を常時所
定範囲に保つ流量制御装置が不要であるために排
水モニタが単純な構造となり、しかも放射能の検
出精度を著しく向上することができる。[Formula] C 2 = 2gh, both of which are constant values. Based on the output signal of the flowmeter 2, v 0 ' and F are calculated to correct the effective volume. A specific example of the correction calculation section 14 shown in FIG. 1 calculates the flow velocity v 0 ' of the water discharge nozzle section from the measured flow rate value of wastewater, calculates the above-mentioned correction coefficient F, and multiplies it to the measured value of radioactivity. Become. In the above example, if the flow velocity v 0 ' at the time of measurement is 1 m/sec with respect to the standard v 0 of 2 m/sec, this correction will be 1.64 times the count value. FIG. 2 shows the relationship between actually measured values and theoretically calculated values according to the apparatus of this embodiment. In the figure, double circles indicate actual measured values, and solid lines indicate calculated values. According to the present invention, the radiation detector is adjusted based on the flow velocity V 0 of radioactive wastewater in the water discharge nozzle portion, the radius R 0 of the water discharge nozzle, the gravitational acceleration g, and the water head h from the lower end of the water discharge nozzle to the set position of the radiation detector. Since the effective volume of radioactive wastewater at the installation location is corrected and the corrected effective volume of radioactive wastewater is used to correct the output signal of the radiation detector,
Since there is no need for a flow rate control device that constantly maintains the flow rate of radioactive wastewater supplied to the water discharge nozzle within a predetermined range, the wastewater monitor has a simple structure, and radioactivity detection accuracy can be significantly improved.
第1図は、本発明の一実施例の全体構成図、第
2図は、本発明の効果を説明するための図であ
る。
第1図において、1……送水ポンプ、2……流量
計、3……整流管、4……放水ノズル、5……配
管、6……排水、7……矢印、8……供給管、9
……案内板、10……しやへい体、11……放射
線検出器、12……計数装置、13……信号回
線、14……補正演算部。
FIG. 1 is an overall configuration diagram of an embodiment of the present invention, and FIG. 2 is a diagram for explaining the effects of the present invention. In Fig. 1, 1... Water pump, 2... Flow meter, 3... Rectifier pipe, 4... Water discharge nozzle, 5... Piping, 6... Drainage, 7... Arrow, 8... Supply pipe, 9
. . . Guide plate, 10 . . . Shape body, 11 .
Claims (1)
状体の中央部に配置されて前記筒状体の軸方向に
延び、しかも下方に向かつて開口する放水ノズル
と、前記放水ノズルに放射性排水を導く放射性排
水導管と、前記放水ノズルの下端より上方で前記
筒状体と前記放水ノズルとの間にある空間に洗浄
水を供給して前記筒状体の内壁に沿う洗浄水流を
形成する手段と、前記放水ノズルから流出した放
射性排水流と前記洗浄水流とが存在する部分でし
かも前記筒状体の外側に配置された放射線検出器
とを有する排水モニタにおいて、前記放射性排水
導管に設けられた流量計と、前記流量計の出力信
号に基づいて前記放水ノズル部における放射性排
水の流速V0を求め、次式により前記放射線検出
器の設置位置における放水された前記放射性排水
の半径Rを求め、この放射性排水の半径Rに基 ここで、R0は放水ノズルの半径、gは重力加
速度及びhは放水ノズルの下端から放射線検出器
の設置位置までの水頭。 づいて前記放射線検出器の設置位置における放射
性排水の有効体積を補正するとともに補正された
放射性排水の有効体積を用いて前記放射線検出器
の出力信号を補正する手段とを備えたことを特徴
とする排水モニタ。[Claims] 1. A cylindrical body disposed substantially vertically, and a water discharge nozzle disposed in the center of the cylindrical body, extending in the axial direction of the cylindrical body, and opening downward. a radioactive drainage conduit that guides radioactive wastewater to the water discharge nozzle; and a radioactive drainage conduit that supplies cleaning water to a space between the cylindrical body and the water discharge nozzle above the lower end of the water discharge nozzle to drain the inner wall of the cylindrical body. A drainage monitor comprising means for forming a cleaning water flow along the water discharge nozzle, and a radiation detector disposed outside the cylindrical body in a portion where the radioactive wastewater flow flowing out from the water discharge nozzle and the cleaning water flow exist, The flow velocity V 0 of the radioactive waste water at the water discharge nozzle part is determined based on the flow meter provided in the radioactive waste water conduit and the output signal of the flow meter, and the flow velocity V 0 of the radioactive waste water at the installation position of the radiation detector is determined by the following formula. Find the radius R of the radioactive wastewater, and use the radius R of the radioactive wastewater as a base. Here, R 0 is the radius of the water nozzle, g is the gravitational acceleration, and h is the water head from the bottom of the water nozzle to the installation position of the radiation detector. and means for correcting the effective volume of radioactive wastewater at the installation position of the radiation detector and correcting the output signal of the radiation detector using the corrected effective volume of the radioactive wastewater. Drainage monitor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10360980A JPS5729981A (en) | 1980-07-30 | 1980-07-30 | Drainage monitor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10360980A JPS5729981A (en) | 1980-07-30 | 1980-07-30 | Drainage monitor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5729981A JPS5729981A (en) | 1982-02-18 |
| JPS6138828B2 true JPS6138828B2 (en) | 1986-09-01 |
Family
ID=14358509
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP10360980A Granted JPS5729981A (en) | 1980-07-30 | 1980-07-30 | Drainage monitor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5729981A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2617983B1 (en) * | 1987-07-08 | 1991-10-25 | Electricite De France | DEVICE FOR MEASURING THE GAMMA ACTIVITY OF A RADIOACTIVE LIQUID |
| JP2549155B2 (en) * | 1988-08-25 | 1996-10-30 | 株式会社東芝 | Radioactive waste liquid treatment equipment |
-
1980
- 1980-07-30 JP JP10360980A patent/JPS5729981A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5729981A (en) | 1982-02-18 |
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