JPH0499993A - Measurement of reactor water level - Google Patents
Measurement of reactor water levelInfo
- Publication number
- JPH0499993A JPH0499993A JP2216969A JP21696990A JPH0499993A JP H0499993 A JPH0499993 A JP H0499993A JP 2216969 A JP2216969 A JP 2216969A JP 21696990 A JP21696990 A JP 21696990A JP H0499993 A JPH0499993 A JP H0499993A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- pressure vessel
- water level
- pressure
- valves
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 46
- 238000005259 measurement Methods 0.000 title claims abstract description 11
- 239000007791 liquid phase Substances 0.000 claims description 4
- 238000000691 measurement method Methods 0.000 claims description 4
- 239000012071 phase Substances 0.000 claims description 3
- 238000002955 isolation Methods 0.000 abstract description 5
- 239000007788 liquid Substances 0.000 abstract 3
- 238000009833 condensation Methods 0.000 description 3
- 230000005494 condensation Effects 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 238000007872 degassing Methods 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
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、原子力発電所の原子炉水位を正確に測定する
ことのできる原子炉水位計測方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a reactor water level measuring method that can accurately measure the reactor water level in a nuclear power plant.
（従来の技術）
沸騰水型原子力発電所における原子炉水位の計測方法は
、原子炉圧力容器の上部および下部に計測用ノズルを設
け、上部側は気相部の圧力を、下部側は液相部の圧力を
測定し、両者の差圧を計測することで行うものである。(Prior art) A method for measuring the reactor water level in a boiling water nuclear power plant is to install measurement nozzles at the upper and lower parts of the reactor pressure vessel, with the upper side measuring the pressure in the gas phase and the lower side measuring the liquid phase pressure. This is done by measuring the pressure between the two and measuring the pressure difference between the two.
この場合、上部側計測ノズルには凝縮槽を設け、常に一
定レベルを保っておくことで、差圧計にかかる上部側の
圧力を一定とし、実水位の変動による下部側ノズル部の
圧力変化により差圧の変化を得て原子炉水位変化を測定
している。In this case, by providing a condensation tank in the upper measuring nozzle and always maintaining a constant level, the pressure on the upper side applied to the differential pressure gauge is kept constant, and the pressure changes in the lower nozzle due to fluctuations in the actual water level can cause a difference in pressure. Changes in reactor water level are measured by obtaining changes in pressure.
したがって、正確な原子炉水位を測定するためには、凝
縮槽レベルを一定に保つことが重要であるが、この凝縮
槽への初期水張りは、差圧計が設置されている計装ラッ
クにおいて、差圧計側から水を張る方法で行っている。Therefore, in order to accurately measure the reactor water level, it is important to maintain a constant level in the condensing tank, but the initial filling of the condensing tank with water is carried out at the instrumentation rack where the differential pressure gauge is installed. This is done by filling water from the pressure gauge side.
（発明が解決しようとする課題）
ところで、原子炉起動前におけるこの凝縮槽の水張りに
際し、計装配管の勾配や配管途中に存在する継手部、隔
離弁等の部分で完全にエアーを抜くことが難しい場合が
ある。もしエアーが一部残って水張りした場合、次のよ
うな問題が生ずる。(Problem to be Solved by the Invention) By the way, when filling the condensation tank with water before starting the reactor, it is difficult to completely remove air from the slope of the instrumentation piping, joints in the middle of the piping, isolation valves, etc. It can be difficult. If some air remains and water fills up, the following problems will occur.
原子炉起動時には脱気運転を実施するが、この脱気運転
は、原子炉水温度８０℃近辺で主蒸気隔離弁を開として
高真空状態にあるタービン復水器と原子炉圧力容器とを
一体とし、原子炉圧力容器内圧力を真空状態にして原子
炉水の溶存酸素濃度を低減させるものである。この脱気
運転の時に、上記計装配管内のエアーが原子炉圧力容器
側へ抜けて凝縮槽の水面が低下する。そうすると、原子
炉水位計としての基準水柱が変わるので、実際の原子炉
水位が変化していないにもかかわらず見掛は上の原子炉
水位が変動することになる。When the reactor is started up, a deaeration operation is carried out. This deaeration operation involves opening the main steam isolation valve when the reactor water temperature is around 80°C, and integrating the turbine condenser and the reactor pressure vessel, which are in a high vacuum state. The system reduces the dissolved oxygen concentration in the reactor water by reducing the pressure inside the reactor pressure vessel to a vacuum state. During this degassing operation, the air in the instrumentation pipe escapes to the reactor pressure vessel side, and the water level in the condensation tank decreases. In this case, the reference water column used as a reactor water level gauge changes, so the apparent reactor water level will fluctuate even though the actual reactor water level has not changed.
本発明は、上記問題点に対処してなされたもので、原子
炉水位計装ラインに存在する空気溜りを完全に除去して
原子炉水位計測を正確に行うことを目的とするものであ
る。The present invention has been made in response to the above-mentioned problems, and an object of the present invention is to completely remove air pockets existing in the reactor water level instrumentation line to accurately measure the reactor water level.
［発明の構成］
（課題を解決するための手段）
本発明は、原子炉圧力容器の上部および下部にそれぞれ
計測用ノズルを設け、上部側で圧力容器内の気相部の圧
力を、下部側で圧力容器内の液相部の圧力を測定して両
者の差圧により原子炉圧力容器内の水位を計測する原子
炉水位計測方法において、原子炉圧力容器に該容器内を
大気解放する原子炉圧力容器ベントラインを設け、該ベ
ントラインに設けられたベント弁および真空ポンプによ
り原子炉起動前に原子炉圧力容器内圧力を真空状態とし
て原子炉圧力容器につながる水位計測配管内に存在する
エアーを吸引・除去することを特徴とする原子炉水位計
測方法に関する。[Structure of the Invention] (Means for Solving the Problems) The present invention provides measuring nozzles at the upper and lower parts of the reactor pressure vessel, and measures the pressure of the gas phase in the pressure vessel at the upper side, and measures the pressure at the lower side. In the reactor water level measurement method in which the pressure of the liquid phase part in the pressure vessel is measured and the water level in the reactor pressure vessel is measured based on the pressure difference between the two, the reactor pressure vessel is opened to the atmosphere. A pressure vessel vent line is provided, and a vent valve and a vacuum pump installed in the vent line are used to reduce the pressure inside the reactor pressure vessel to a vacuum state before starting the reactor, and remove the air present in the water level measurement piping connected to the reactor pressure vessel. This invention relates to a reactor water level measurement method characterized by suction and removal.
（作用）
本発明の原子炉水位計測方法では、原子炉起動前に、原
子炉圧力容器ベントラインのベント弁の下流にある真空
ポンプを作動させ、圧力容器内を高真空に保つので、水
位計装配管内に存在するエアーを完全に除去することが
できる。したがって、原子炉起動時の脱気運転時による
凝縮槽水面の変動がなくなり、正確な水位計測が可能に
なる。(Function) In the reactor water level measuring method of the present invention, before reactor startup, the vacuum pump downstream of the vent valve of the reactor pressure vessel vent line is operated to maintain a high vacuum inside the pressure vessel. Air present in the equipment piping can be completely removed. Therefore, fluctuations in the water level of the condensing tank due to the degassing operation at the time of reactor startup are eliminated, making it possible to accurately measure the water level.
（実施例） 本発明の一実施例を図面を参照して説明する。(Example) An embodiment of the present invention will be described with reference to the drawings.
原子炉圧力容器１の上部および下部に水位計測用ノズル
２ａおよび２ｂを設け、上部側には凝縮槽３を有して原
子炉水位計４により基準圧力を測定し、下部側は原子炉
水位計４により液相部の圧力を測定して、両者の差圧に
より原子炉水位の測定を行う。Water level measuring nozzles 2a and 2b are provided at the upper and lower parts of the reactor pressure vessel 1, and the upper side has a condensing tank 3 and a reactor water level gauge 4 measures the reference pressure, and the lower side has a reactor water level gauge. 4, the pressure in the liquid phase is measured, and the reactor water level is measured based on the differential pressure between the two.
以上が従来の原子炉水位の測定方法である。本発明の実
施例では、原子炉圧力容器１にベント弁６ａ、６ｂ、７
を有するベントラインを設け、真空ポンプ９をベント弁
６ｂの下流側に設けて、原子炉起動前に圧力容器内を高
真空状態とする。The above is the conventional method for measuring the reactor water level. In the embodiment of the present invention, vent valves 6a, 6b, 7 are provided in the reactor pressure vessel 1.
A vacuum pump 9 is provided on the downstream side of the vent valve 6b to bring the inside of the pressure vessel into a high vacuum state before starting the reactor.
すなわち、主蒸気隔離弁５を閉とし、ベント弁６ａおよ
び６ｂを開とし、真空ポンプ９の大口弁８を開とし、ベ
ント弁７を閉として、真空ポンプ９を起動する。以上の
操作により圧力容器１内を高真空状態とし、水位計装配
管の継手や弁部に存在しているエアーを抜くことができ
る。That is, the main steam isolation valve 5 is closed, the vent valves 6a and 6b are opened, the large mouth valve 8 of the vacuum pump 9 is opened, the vent valve 7 is closed, and the vacuum pump 9 is started. By the above operations, the inside of the pressure vessel 1 can be brought into a high vacuum state, and the air present in the joints and valve parts of the water level instrumentation piping can be removed.
一定時間圧力容器内を高真空状態に保持した後、真空ポ
ンプ人口弁８を閉弁して真空ポンプを停止し、ベント弁
６ａ、６ｂ、７を開いて、圧力容器内を大気圧にしても
、以後は計装配管に新たにエアーが入り込むことがない
。After maintaining the inside of the pressure vessel in a high vacuum state for a certain period of time, the vacuum pump artificial valve 8 is closed to stop the vacuum pump, and the vent valves 6a, 6b, and 7 are opened to bring the inside of the pressure vessel to atmospheric pressure. After that, no new air will enter the instrumentation piping.
かかる操作により、原子炉起動時の計装配管内のエアー
抜けによる凝縮槽レベル変化を防ぐことができ、以後従
来と同様に計測を行って原子炉水位を正確に測定するこ
とができる。This operation can prevent a change in the condensing tank level due to air leakage in the instrumentation piping at the time of reactor startup, and thereafter it is possible to accurately measure the reactor water level by performing measurements in the same manner as in the past.
［発明の効果］
以上説明したように、本発明によれば、原子炉起動時の
脱気運転で原子炉水位の見掛上の変動が起きることがな
く、正確で安定した炉水位計測を行うことができる。[Effects of the Invention] As explained above, according to the present invention, there is no apparent fluctuation in the reactor water level during the deaeration operation at the time of reactor startup, and accurate and stable reactor water level measurement is performed. be able to.
図は本発明の一実施例を説明するための装置系統図であ
る。
１・・・原子炉圧力容器
２ａ・・・水位計測用上部ノズル
２ｂ・・・水位計測用下部ノズル
３・・・凝縮機
４・・・原子炉水位計
５・・・主蒸気隔離弁
６ａ。
６ｂ。
７・・・圧力容器ベント弁
９・・・真空ポンプThe figure is an apparatus system diagram for explaining one embodiment of the present invention. 1...Reactor pressure vessel 2a...Upper nozzle for water level measurement 2b...Lower nozzle for water level measurement 3...Condenser 4...Reactor water level gauge 5...Main steam isolation valve 6a. 6b. 7...Pressure vessel vent valve 9...Vacuum pump
Claims (1)
用ノズルを設け、上部側で圧力容器内の気相部の圧力を
、下部側で圧力容器内の液相部の圧力を測定して両者の
差圧により原子炉圧力容器内の水位を計測する原子炉水
位計測方法において、原子炉圧力容器に該容器内を大気
解放する原子炉圧力容器ベントラインを設け、該ベント
ラインに設けられたベント弁および真空ポンプにより原
子炉起動前に原子炉圧力容器内圧力を真空状態として原
子炉圧力容器につながる水位計測配管内に存在するエア
ーを吸引・除去することを特徴とする原子炉水位計測方
法。(1) Measurement nozzles are installed at the upper and lower parts of the reactor pressure vessel, and the upper side measures the pressure of the gas phase inside the pressure vessel, and the lower side measures the pressure of the liquid phase inside the pressure vessel. In a reactor water level measurement method that measures the water level in a reactor pressure vessel based on the differential pressure of A reactor water level measurement method characterized by vacuuming the pressure inside the reactor pressure vessel using a valve and a vacuum pump before starting the reactor, and sucking and removing air present in the water level measurement piping connected to the reactor pressure vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2216969A JPH0499993A (en) | 1990-08-20 | 1990-08-20 | Measurement of reactor water level |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2216969A JPH0499993A (en) | 1990-08-20 | 1990-08-20 | Measurement of reactor water level |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0499993A true JPH0499993A (en) | 1992-03-31 |
Family
ID=16696759
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2216969A Pending JPH0499993A (en) | 1990-08-20 | 1990-08-20 | Measurement of reactor water level |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0499993A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1999048104A1 (en) * | 1998-03-19 | 1999-09-23 | Siemens Aktiengesellschaft | Device and method for running off steam |
-
1990
- 1990-08-20 JP JP2216969A patent/JPH0499993A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1999048104A1 (en) * | 1998-03-19 | 1999-09-23 | Siemens Aktiengesellschaft | Device and method for running off steam |
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