JPH037275B2 - - Google Patents

Info

Publication number
JPH037275B2
JPH037275B2 JP58166140A JP16614083A JPH037275B2 JP H037275 B2 JPH037275 B2 JP H037275B2 JP 58166140 A JP58166140 A JP 58166140A JP 16614083 A JP16614083 A JP 16614083A JP H037275 B2 JPH037275 B2 JP H037275B2
Authority
JP
Japan
Prior art keywords
water level
reactor water
steam drum
reactor
flow rate
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
Application number
JP58166140A
Other languages
Japanese (ja)
Other versions
JPS6057292A (en
Inventor
Kenji Tonomoto
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP58166140A priority Critical patent/JPS6057292A/en
Publication of JPS6057292A publication Critical patent/JPS6057292A/en
Publication of JPH037275B2 publication Critical patent/JPH037275B2/ja
Granted 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

Landscapes

  • Details Of Flowmeters (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は圧力管型原子炉の原子炉水位及び再循
環流量計測装置に関するものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor water level and recirculation flow rate measuring device for a pressure tube nuclear reactor.

第1図は、従来の圧力管型原子炉の原子炉水位
計測装置及び再循環流量計測装置の系統図を示す
ものであるが、通常時、原子炉冷却材は蒸気ドラ
ム3より下降管8及びマニホルド4を経て、再循
環ポンプ5により昇圧されウオータドラム7及び
入口管11を経て原子炉1内の圧力管2に送られ
る。圧力管2に供給された冷却材は、燃料集合体
10の核反応熱により加熱されて二層流(水と蒸
気の混合流)となつて出口管12を経て蒸気ドラ
ム3に戻り、水と蒸気に分離される。更に、蒸気
は主蒸気管13を経てタービン系15へ送られ
る。また、蒸気ドラム3において分離された水は
給水管14からの給水と混合された後圧力管2へ
再循環される。尚、下降管8には配管破損時の冷
却材流出を制限する絞り機構24が設けられてい
る。
FIG. 1 shows a system diagram of a reactor water level measuring device and a recirculation flow rate measuring device of a conventional pressure tube reactor. Under normal conditions, reactor coolant flows from the steam drum 3 to the downcomer pipe 8 and the recirculation flow rate measuring device. It passes through the manifold 4, is pressurized by the recirculation pump 5, and is sent to the pressure pipe 2 in the reactor 1 via the water drum 7 and the inlet pipe 11. The coolant supplied to the pressure pipe 2 is heated by the nuclear reaction heat of the fuel assembly 10, becomes a two-layer flow (a mixed flow of water and steam), returns to the steam drum 3 via the outlet pipe 12, and is mixed with water. Separated into steam. Furthermore, the steam is sent to the turbine system 15 via the main steam pipe 13. Further, the water separated in the steam drum 3 is mixed with water supplied from the water supply pipe 14 and then recycled to the pressure pipe 2. Note that the downcomer pipe 8 is provided with a throttle mechanism 24 that restricts the flow of coolant in the event of pipe breakage.

このような圧力管型原子炉の冷却系統におい
て、原子炉水位計測装置は、蒸気ドラム3の気相
部に器準面器16を介して配管9及び基準配管1
9により接続された蒸気ドラム圧力計17と、一
端がマニホルド4に連通し他の一端が前記基準配
管19に連通する原子炉水位計22と、下降管8
の流量圧力損失及び冷却材密度補正を行なう原子
炉水位演算器18により構成されている。
In the cooling system of such a pressure tube reactor, the reactor water level measuring device connects the piping 9 and the reference piping 1 to the gas phase part of the steam drum 3 via the leveling device 16.
9, a reactor water level gauge 22 whose one end communicates with the manifold 4 and whose other end communicates with the reference pipe 19, and the downcomer pipe 8.
The reactor water level calculator 18 corrects flow rate pressure loss and coolant density.

一方、再循環流量計測装置は、再循環ポンプ5
の冷却材出口側に設けられている流量計絞り機構
6及び流量計検出配管23により接続された再循
環流量計20により構成されている。
On the other hand, the recirculation flow rate measuring device is the recirculation pump 5
The recirculation flowmeter 20 is connected to a flowmeter throttle mechanism 6 provided on the coolant outlet side of the flowmeter and a flowmeter detection pipe 23.

蒸気ドラムの水位計測は、蒸気ドラム3の液相
部と基準配管9間に配設された蒸気ドラム水位計
21によつて行なわれる。
The water level in the steam drum is measured by a steam drum water level gauge 21 disposed between the liquid phase portion of the steam drum 3 and the reference pipe 9.

しかるに、このように構成された従来の計測装
置においては、原子炉水位計測装置と再循環流量
計測装置との2つの計測装置を必要とし、システ
ムの複雑化の問題があつた。
However, the conventional measuring device configured in this manner requires two measuring devices, a reactor water level measuring device and a recirculation flow rate measuring device, resulting in a problem of system complexity.

この発明は上記の如き事情に鑑みてなされたも
のであつて、計測用配管の接続を変えることによ
つて、従来の原子炉水位計測装置に再循環流量の
計測機能を付与することができ、したがつて、絞
り機構型の再循環流量計を削除することができ、
しかもシステムの簡素化及び設備の合理化を図り
得る原子炉水位・再循環流量計測装置を提供する
ことを目的とするものである。
This invention was made in view of the above circumstances, and by changing the connection of the measurement piping, a recirculation flow rate measurement function can be added to a conventional reactor water level measurement device. Therefore, the throttling mechanism type recirculation flowmeter can be removed,
Moreover, it is an object of the present invention to provide a reactor water level/recirculation flow rate measuring device that can simplify the system and rationalize the equipment.

この目的に対応して、この発明の原子炉水位・
再循環流量計測装置は、少なくとも、順次、圧力
管、蒸気ドラム、マニホルド、再循環ポンプ、ウ
オータドラムを経て前記圧力管に戻る閉ループを
備えた圧力管型原子炉において、一端が配管を介
して前記マニホルドに連通し他の一端が配管を介
して蒸気ドラム圧力計及び前記蒸気ドラムの液相
部に連通する原子炉水位流量計と、前記蒸気ドラ
ム圧力計及び前記原子炉水位流量計の信号を入力
し再循環流量を出力する流量計密度補正演算器
と、前記蒸気ドラム圧力計及び原子炉水位流量計
の信号ならびに流量計密度補正演算器の出力を入
力し原子炉水位を出力する原子炉水位演算器とを
備えたことを特徴としている。
Corresponding to this purpose, the reactor water level and
The recirculation flow rate measuring device is used in a pressure tube nuclear reactor having at least a closed loop that sequentially returns to the pressure tube via a pressure tube, a steam drum, a manifold, a recirculation pump, and a water drum, one end of which connects the A reactor water level flow meter that communicates with the manifold and whose other end communicates with a steam drum pressure gauge and a liquid phase portion of the steam drum via piping, and inputs signals from the steam drum pressure gauge and the reactor water level flow meter. a flowmeter density correction calculator that outputs the recirculation flow rate; and a reactor water level calculator that inputs the signals from the steam drum pressure gauge and the reactor water level flowmeter and the output of the flowmeter density correction calculator and outputs the reactor water level. It is characterized by having a container.

以下、この発明の詳細を一実施例を示す図面に
ついて説明する。
Hereinafter, details of the present invention will be explained with reference to the drawings showing one embodiment.

第2図において、30は原子炉水位流量計であ
る。原子炉水位流量計30は、一端が配管31を
介してマニホルド4に、他の一端が配管32を介
して蒸気ドラム圧力計17及び蒸気ドラム3の液
相部に連通接続されている。ここで注目されなけ
ればならないことは、従来の検出器(すなわち原
子炉水位計22)が配管9及び基準配管19を介
して蒸気ドラム3の気相部に連通していたのに対
し、本発明における検出器(すなわち原子炉水位
流量計30)は配管32を介し蒸気ドラム3の液
相部に連通していることである。このように、従
来の原子炉水位計の差圧検出位置の一方の側の接
続配管を蒸気ドラム気相部から蒸気ドラム液相部
に変更することにより、蒸気ドラム3とマニホル
ド4間の正確な差圧の測定が可能となり、したが
つて、従来の原子炉水位計22は、原子炉水位計
測と再循環流量計測の二つの機能を備えた原子炉
水位流量計30として用いることができる。
In FIG. 2, 30 is a reactor water level flow meter. The reactor water level flow meter 30 is connected at one end to the manifold 4 via a pipe 31 and at the other end to the steam drum pressure gauge 17 and the liquid phase portion of the steam drum 3 via a pipe 32. What must be noted here is that whereas the conventional detector (i.e., the reactor water level gauge 22) communicates with the gas phase portion of the steam drum 3 via the piping 9 and the reference piping 19, the present invention The detector (namely, the reactor water level flowmeter 30) in is connected to the liquid phase portion of the steam drum 3 via a pipe 32. In this way, by changing the connection piping on one side of the differential pressure detection position of the conventional reactor water level gauge from the steam drum gas phase part to the steam drum liquid phase part, accurate control between the steam drum 3 and the manifold 4 can be achieved. Differential pressure can be measured, and therefore, the conventional reactor water level gauge 22 can be used as a reactor water level flow meter 30 having two functions: reactor water level measurement and recirculation flow rate measurement.

次に、原子炉水位流量計30及び蒸気ドラム圧
力計17の信号を用いて原子炉水位及び再循環流
量を求める場合について説明する。
Next, a case will be described in which the reactor water level and recirculation flow rate are determined using the signals from the reactor water level flow meter 30 and the steam drum pressure gauge 17.

図中、符号33は、流量密度補正演算器、符号
35は、原子炉水位演算器である。原子炉水位流
量計30の信号は、再循環流量に対し位置水頭に
相当する差圧が誤差として発生するが、この誤差
は、蒸気ドラム圧力計17の信号を用いた前記流
量計密度補正演算器33により補正されて再循環
流量が求められる。
In the figure, numeral 33 is a flow rate density correction calculator, and numeral 35 is a reactor water level calculator. The signal from the reactor water level flow meter 30 has an error in the differential pressure corresponding to the position head with respect to the recirculation flow rate. 33 to determine the recirculation flow rate.

また、原子炉水位における下降管8の圧力損失
の補正は、原子炉水位演算器への入力を蒸気ドラ
ム圧力計及び原子炉水位流量計30の信号と共に
前記流量計密度補正演算器33の出力を入力する
ことによつて行なわれる。
In addition, to correct the pressure loss of the downcomer pipe 8 at the reactor water level, the input to the reactor water level calculator is combined with the signals from the steam drum pressure gauge and the reactor water level flowmeter 30, as well as the output of the flowmeter density correction calculator 33. This is done by inputting the information.

尚、従来の原子炉水位計測装置においても、蒸
気ドラム3とマニホルド4間に再循環流量による
差圧は発生するが、前記差圧は蒸気ドラム気相部
から得ることになるため、蒸気ドラム水位変動の
影響を受け易く、再循環流量を求める場合不正確
となる問題がある。
In the conventional reactor water level measurement device, a pressure difference occurs between the steam drum 3 and the manifold 4 due to the recirculation flow rate, but since the pressure difference is obtained from the steam drum gas phase, the steam drum water level It is susceptible to fluctuations and has the problem of being inaccurate when determining the recirculation flow rate.

このように構成された本発明の原子炉水位・再
循環流量計測装置においては、原子炉水位流量計
の差圧検出位置の一方の側の接続配管が蒸気ドラ
ム液相部に接続されているので、蒸気ドラムの水
位変動の影響を受けない再循環流量による差圧を
得ることができ、したがつて、正確な再循環流量
計測が可能となると共に絞り機構を備えた再循環
流量計を不用とすることができ、しかも同一検出
器の信号により原子炉水位の計測ができるのでシ
ステムの簡素化及び設備の合理化を図ることがで
きる。
In the reactor water level/recirculation flow measuring device of the present invention configured as described above, the connecting pipe on one side of the differential pressure detection position of the reactor water level flowmeter is connected to the steam drum liquid phase part. , it is possible to obtain a differential pressure due to the recirculation flow rate that is not affected by water level fluctuations in the steam drum, making it possible to accurately measure the recirculation flow rate and eliminating the need for a recirculation flowmeter equipped with a throttle mechanism. Moreover, since the reactor water level can be measured using the signal from the same detector, the system can be simplified and the equipment can be rationalized.

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

第1図は従来の圧力管型原子炉の原子炉水位計
測装置及び再循環流量計測装置の系統図、及び第
2図はこの発明の一実施例に係わる原子炉水位・
再循環計測装置の系統図である。 3……蒸気ドラム、4……マニホルド、8……
下降管、17……蒸気ドラム圧力計、30……原
子炉水位流量計、31,32……配管、33……
流量計密度補正演算器、35……原子炉水位演算
器。
FIG. 1 is a system diagram of a conventional reactor water level measuring device and recirculation flow rate measuring device of a pressure tube type nuclear reactor, and FIG.
It is a system diagram of a recirculation measuring device. 3... Steam drum, 4... Manifold, 8...
Downcomer pipe, 17... Steam drum pressure gauge, 30... Reactor water level flow meter, 31, 32... Piping, 33...
Flow meter density correction calculator, 35... Reactor water level calculator.

Claims (1)

【特許請求の範囲】[Claims] 1 少なくとも、順次、圧力管、蒸気ドラム、マ
ニホルド、再循環ポンプ、ウオータドラムを経て
前記圧力管に戻る閉ループを備えた圧力管型原子
炉において、一端が配管を介して前記マニホルド
に連通し他の一端が配管を介して蒸気ドラム圧力
計及び前記蒸気ドラムの液相部に連通する原子炉
水位流量計と、前記蒸気ドラム圧力計及び前記原
子炉水位流量計の信号を入力し再循環流量を出力
する流量計密度補正演算器と、前記蒸気ドラム圧
力計及び原子炉水位流量計の信号ならびに前記流
量計密度補正演算器の出力を入力し原子炉水位を
出力する原子炉水位演算器とを備えたことを特徴
とする原子炉水位・再循環流量計測装置。
1 In a pressure tube reactor having at least a closed loop returning to said pressure tube via a pressure tube, a steam drum, a manifold, a recirculation pump and a water drum in sequence, one end communicates with said manifold via piping and the other A reactor water level flow meter whose one end communicates with a steam drum pressure gauge and the liquid phase portion of the steam drum via piping, inputs signals from the steam drum pressure gauge and the reactor water level flow meter, and outputs a recirculation flow rate. a reactor water level calculator that inputs the signals of the steam drum pressure gauge and the reactor water level flowmeter as well as the output of the flowmeter density correction calculator and outputs the reactor water level. A reactor water level/recirculation flow rate measuring device characterized by:
JP58166140A 1983-09-09 1983-09-09 Nuclear reactor water level-recirculating flow-rate measuring device Granted JPS6057292A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58166140A JPS6057292A (en) 1983-09-09 1983-09-09 Nuclear reactor water level-recirculating flow-rate measuring device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58166140A JPS6057292A (en) 1983-09-09 1983-09-09 Nuclear reactor water level-recirculating flow-rate measuring device

Publications (2)

Publication Number Publication Date
JPS6057292A JPS6057292A (en) 1985-04-03
JPH037275B2 true JPH037275B2 (en) 1991-02-01

Family

ID=15825781

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58166140A Granted JPS6057292A (en) 1983-09-09 1983-09-09 Nuclear reactor water level-recirculating flow-rate measuring device

Country Status (1)

Country Link
JP (1) JPS6057292A (en)

Also Published As

Publication number Publication date
JPS6057292A (en) 1985-04-03

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