JPS6244638B2 - - Google Patents

Info

Publication number
JPS6244638B2
JPS6244638B2 JP54139266A JP13926679A JPS6244638B2 JP S6244638 B2 JPS6244638 B2 JP S6244638B2 JP 54139266 A JP54139266 A JP 54139266A JP 13926679 A JP13926679 A JP 13926679A JP S6244638 B2 JPS6244638 B2 JP S6244638B2
Authority
JP
Japan
Prior art keywords
water level
sump
containment vessel
level detection
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
Application number
JP54139266A
Other languages
Japanese (ja)
Other versions
JPS5663297A (en
Inventor
Hitoshi Ichama
Eiichi Watanabe
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
Kitashiba Electric Co Ltd
Original Assignee
Toshiba Corp
Kitashiba Electric Co Ltd
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 Toshiba Corp, Kitashiba Electric Co Ltd filed Critical Toshiba Corp
Priority to JP13926679A priority Critical patent/JPS5663297A/en
Publication of JPS5663297A publication Critical patent/JPS5663297A/en
Publication of JPS6244638B2 publication Critical patent/JPS6244638B2/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は、原子炉一次格納容器サンプから原子
炉建家サンプへの排水方法を改良した原子炉一次
格納容器サンプ流量測定装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a primary reactor containment vessel sump flow rate measuring device that improves the method of draining water from a reactor primary containment vessel sump to a reactor building sump.

従来原子炉一次格納容器(以下D/Wと云う)
内に発生した水は、D/W内のD/Wサンプ(原
子炉一次格納容器サンプ)に集め、そこから原子
炉建屋(以下R/Bと云う)内のR/Bサンプ
(原子炉建屋サンプ)にサイフオンで落とすよう
にし、その排水ラインに流量変換器(以下FTと
云う)を挿入して流量を検出し、設定値を越える
流量には警報を発生させ、またD/Wサンプにレ
ベルスイツチを設け、設定値以上に水が貯つたら
警報を発するようにしていた。しかしこのような
装置では、排水ラインを流れる流量がごく僅かで
あることから、サイフオンが切れたり、FTがタ
ービンメータであるため、ごみ、さびなどによつ
て作動不良になる可能性が高く、安定性に欠ける
ものであつた。
Conventional reactor primary containment vessel (hereinafter referred to as D/W)
The water generated in the reactor is collected in the D/W sump (reactor primary containment vessel sump) in the D/W, and from there is transferred to the R/B sump (reactor building sump) in the reactor building (hereinafter referred to as R/B). A flow rate converter (hereinafter referred to as FT) is inserted into the drainage line to detect the flow rate, and an alarm is generated when the flow rate exceeds a set value. A switch was installed to issue an alarm if water accumulated above a set value. However, in such devices, since the flow rate flowing through the drainage line is very small, there is a high possibility that the siphon will break, and since the FT is a turbine meter, there is a high possibility that it will malfunction due to dirt, rust, etc. It lacked sex.

本発明は、以上の事情に鑑み、低流量を精度よ
く測定でき、また安定した作用を継続する原子炉
一次格納容器サンプ流量測定装置を提供する。
In view of the above circumstances, the present invention provides a primary reactor containment vessel sump flow rate measuring device that can accurately measure low flow rates and continues stable operation.

以下図に就いて詳しく説明する。 The figure will be explained in detail below.

原子炉一次格納容器サンプ(D/Wサンプ)1
にD/W13内で発生する水が集められ、排水ライ
ン2によつて原子炉建屋サンプ(R/Bサンプ)
11にサイフオン原理によつて導く。排水ライン
2のD/Wサンプ開口はD/Wサンプ1内に設け
た逆U字管3に接続し、途中U字シール部4、排
出を制御する制御弁5および流量検出器(以下
FIと云う)6を挿入する。
Reactor primary containment vessel sump (D/W sump) 1
The water generated in D/W13 is collected and sent to the reactor building sump (R/B sump) by drainage line 2.
11 by the siphon principle. The D/W sump opening of the drainage line 2 is connected to an inverted U-shaped pipe 3 provided in the D/W sump 1, and there is a U-shaped seal part 4, a control valve 5 that controls discharge, and a flow rate detector (hereinafter referred to as
Insert 6 (called FI).

D/Wサンプ1には高、低二つの水位検出スイ
ツチ(以下LSH,LSLと云う)8,7を設け、
D/Wサンプ1内の水位を検出して上記制御弁5
を制御する。LSH8の信号で制御弁5を開き、
LSL7の信号で制御弁5を閉じる。LSL7は上記
逆U字管3の開口端3aより上位(50m/m〜
100m/m)に設置し、LSH8はそれより上位の
適当な位置に設置する。LSH8の上位には更に
高高水位検出スイツチ(以下LSHHと云う)9を
設置する。LSHH9はその検出信号で警報器15
を作動する。
The D/W sump 1 is equipped with two high and low water level detection switches (hereinafter referred to as LSH and LSL) 8 and 7.
The water level in the D/W sump 1 is detected and the control valve 5 is activated.
control. Open the control valve 5 with the signal from LSH8,
The control valve 5 is closed by the signal from LSL7. LSL7 is above the opening end 3a of the above-mentioned inverted U-shaped tube 3 (50m/m ~
100m/m), and LSH8 is installed at an appropriate position above it. A high/high water level detection switch (hereinafter referred to as LSHH) 9 is further installed above the LSH 8. LSHH9 uses the detection signal to activate alarm 15.
operate.

LSL7およびLSH8は、その検出信号を別に導
いてタイマ10,10および警報器16を制御す
る。
LSL7 and LSH8 separately guide their detection signals to control timers 10, 10 and alarm 16.

また前記U字シール部4の上流側に水位検出ス
イツチ(以下LSという)12をセツトし、その
検出信号で前記制御弁5を閉動作させる。このU
字シール部4の上流には補給水路14が接続さ
れ、常閉の制御弁14aで制御される。
Further, a water level detection switch (hereinafter referred to as LS) 12 is set on the upstream side of the U-shaped seal portion 4, and the control valve 5 is closed by its detection signal. This U
A supply waterway 14 is connected upstream of the seal portion 4 and is controlled by a normally closed control valve 14a.

なお、符号17は、異常時の隔離弁であつて、
排水ライン2の異常時に他の系統に排出するよう
になつている。
Note that the reference numeral 17 is an isolation valve in the event of an abnormality,
When there is an abnormality in the drainage line 2, the water is discharged to another system.

以上のように構成し、作用は次の通りである。
D/Wサンプ1内に集められた水の水位がLSH
8を越すとその検出信号で制御弁5を開き、排水
系2からR/Bサンプ3に落とす。水位が下がり
LSL7が作動すると制御弁5を閉じる。即ちD/
Wサンプ1に一定量貯水してはその一定量を排水
する間歇的排水を行う。LSL7は逆U字管開口3
aより上位にあり、排水系2への空気の入りを防
ぐ。LSH8は適当位置に設定するが、異常があ
つて水位がLSH8を越えてLSHH9に達すると警
報を発する。
The structure is constructed as described above, and the operation is as follows.
The water level collected in D/W sump 1 is LSH
When the detection signal exceeds 8, the control valve 5 is opened by the detection signal, and water is discharged from the drainage system 2 to the R/B sump 3. water level goes down
When LSL7 operates, control valve 5 is closed. That is, D/
Intermittent drainage is performed in which a certain amount of water is stored in the W sump 1 and then the certain amount is drained. LSL7 is inverted U-shaped tube opening 3
It is located above a and prevents air from entering the drainage system 2. LSH8 is set at an appropriate position, but if an abnormality occurs and the water level exceeds LSH8 and reaches LSHH9, an alarm will be issued.

排水系2に落とす水はFI6で検出する。流量
が大きいと警報信号を発する。このFI6は、従
来のFTのようにプロペラがさびついて作動不能
となるようなことがない。排水系2の配管径(約
2インチ)に応じたものが使用されるために目詰
りがない。
Water dropped into drainage system 2 is detected by FI6. If the flow rate is large, it will issue an alarm signal. This FI6 does not have the problem of the propeller rusting and becoming inoperable like the conventional FT. There is no clogging because the pipe diameter of the drainage system 2 (approximately 2 inches) is used.

またLSL7,LSH8の信号でタイマ10,10
を作動し、その作動時間を記録する。これによつ
てD/Wサンプ1の満水時、排水時間を検出し、
異常は警報する。FI6の流量検出と共に、排水
間隔によつて流量の増大傾向など、総体的な情況
把握ができる。
Also, timers 10 and 10 are activated by LSL7 and LSH8 signals.
and record the operating time. By this, when D/W sump 1 is full of water, the drainage time is detected,
Alerts you if there is an abnormality. Along with the flow rate detection by FI6, it is possible to grasp the overall situation, such as the tendency of increase in flow rate depending on the drainage interval.

U字シール部4では排水がなくなつたときLS
12がこれを検出し、制御弁5を閉じる。そして
制御弁14aを開いて補給水路14から水を補給
し、排水系2のサイフオン機能を保持する。
When the drainage water runs out in U-shaped seal part 4, LS
12 detects this and closes the control valve 5. Then, the control valve 14a is opened to supply water from the supply waterway 14, and the siphon function of the drainage system 2 is maintained.

以上の通り本発明の原子炉一次格納容器サンプ
流量測定装置は、微量で流れる水を一度サンプに
貯め、一定量づつ排出することによつて排水流量
を精度よく検出できる。また排水間隔を把握し、
換算によつて流量をチエツクできる。さらにこの
間隔を測定することによつてD/Wに洩れ出す水
の量の増減傾向を測定できる。排水系に空気が混
入することなくサイフオン原理が保持され、低流
量の流量を精度よく測定できる特徴ある装置であ
る。
As described above, the primary reactor containment vessel sump flow rate measuring device of the present invention can accurately detect the drainage flow rate by once storing a small amount of flowing water in the sump and discharging it in fixed amounts at a time. Also, understand the drainage interval,
The flow rate can be checked by conversion. Furthermore, by measuring this interval, it is possible to measure the tendency of increase or decrease in the amount of water leaking into the D/W. This is a unique device that maintains the siphon principle without introducing air into the drainage system and can accurately measure low flow rates.

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

図は本発明の一実施態様を示す構成図である。 1……D/Wサンプ(原子炉一次格納容器サン
プ、2……排水系、3……逆U字管、4……U字
シール部、5……制御弁、6……FI(流量検出
器)、7,8,9……LSL,LSH,LSHH(水位
検出スイツチ低、高、高高)、10……タイマ、
11……R/Bサンプ原子炉建屋サンプ)、12
……LS(水位検出スイツチ)、13……D/W、
14……補給水路、15,16……警報器。
The figure is a configuration diagram showing one embodiment of the present invention. 1...D/W sump (reactor primary containment vessel sump, 2...drainage system, 3...inverted U-shaped pipe, 4...U-shaped seal section, 5...control valve, 6...FI (flow rate detection) 7, 8, 9...LSL, LSH, LSHH (water level detection switch low, high, high/high), 10...timer,
11...R/B sump reactor building sump), 12
...LS (water level detection switch), 13...D/W,
14... Supply waterway, 15, 16... Alarm.

Claims (1)

【特許請求の範囲】 1 原子炉一次格納容器サンプより原子炉建屋サ
ンプにサイフオン原理による排水系を接続し、排
水系に制御弁を挿入するとともに、原子炉一次格
納容器サンプに高水位検出スイツチと低水位検出
スイツチとを設置し、高水位検出信号により上記
制御弁を開き、低水位検出スイツチの水位検出信
号によつて制御弁を閉じるように制御させたこと
を特徴とする原子炉一次格納容器サンプ流量測定
装置。 2 排水系に流量検出器を挿入し、排水流量を検
出するようにしたことを特徴とする特許請求の範
囲第1項記載の原子炉一次格納容器サンプ流量測
定装置。 3 原子炉一次格納容器サンプ内に逆U字管を挿
入してその一端を排水系に接続すると共に、低水
位検出スイツチを逆U字管の開口端より上位に設
定したことを特徴とする特許請求の範囲第1項記
載の原子炉一次格納容器サンプ流量測定装置。 4 原子炉一次格納容器サンプは高水位検出スイ
ツチより高位に高高水位検出スイツチを有し、こ
の高高水位検出スイツチにより警報器を制御する
ようにしたことを特徴とする特許請求の範囲第1
項記載の原子炉一次格納容器サンプ流量測定装
置。 5 高水位および低水位検出スイツチによつて制
御される1〜複数個のタイマーを備え、原子炉一
次格納容器サンプの満水時、排水時間などを測定
するようにしたことを特徴とする特許請求の範囲
第1項記載の原子炉一次格納容器サンプ流量測定
装置。 6 排水系にU字管通路を構成し、その上流側に
水位検出スイツチを備え、水位低下を検出したと
き制御弁を閉じるようにしたことを特徴とする特
許請求の範囲第1項記載の原子炉一次格納容器サ
ンプ流量測定装置。
[Claims] 1. A drainage system based on the siphon principle is connected from the primary reactor containment vessel sump to the reactor building sump, a control valve is inserted in the drainage system, and a high water level detection switch is connected to the reactor primary containment vessel sump. A reactor primary containment vessel characterized in that a low water level detection switch is installed, the control valve is controlled to open in response to a high water level detection signal, and to be closed in response to a water level detection signal from the low water level detection switch. Sump flow rate measuring device. 2. The reactor primary containment vessel sump flow rate measuring device according to claim 1, characterized in that a flow rate detector is inserted into the drainage system to detect the drainage flow rate. 3. A patent characterized in that an inverted U-shaped tube is inserted into the reactor primary containment vessel sump and one end thereof is connected to the drainage system, and a low water level detection switch is set above the open end of the inverted U-shaped tube. A reactor primary containment vessel sump flow rate measuring device according to claim 1. 4. Claim 1, characterized in that the reactor primary containment vessel sump has a high/high water level detection switch located higher than the high/high water level detection switch, and the alarm is controlled by this high/high water level detection switch.
Reactor primary containment vessel sump flow rate measuring device as described in . 5. A patent claim characterized in that one or more timers controlled by high water level and low water level detection switches are provided to measure when the reactor primary containment vessel sump is full of water, drain time, etc. A reactor primary containment vessel sump flow rate measuring device according to scope 1. 6. The atom according to claim 1, characterized in that a U-shaped pipe passage is configured in the drainage system, and a water level detection switch is provided on the upstream side of the drainage system, and the control valve is closed when a drop in the water level is detected. Primary containment vessel sump flow rate measuring device.
JP13926679A 1979-10-30 1979-10-30 Primary reactor container sump flow rate measuring device Granted JPS5663297A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP13926679A JPS5663297A (en) 1979-10-30 1979-10-30 Primary reactor container sump flow rate measuring device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP13926679A JPS5663297A (en) 1979-10-30 1979-10-30 Primary reactor container sump flow rate measuring device

Publications (2)

Publication Number Publication Date
JPS5663297A JPS5663297A (en) 1981-05-29
JPS6244638B2 true JPS6244638B2 (en) 1987-09-21

Family

ID=15241274

Family Applications (1)

Application Number Title Priority Date Filing Date
JP13926679A Granted JPS5663297A (en) 1979-10-30 1979-10-30 Primary reactor container sump flow rate measuring device

Country Status (1)

Country Link
JP (1) JPS5663297A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01171535U (en) * 1988-05-17 1989-12-05
JPH0260443U (en) * 1988-10-26 1990-05-02
JPH02125533U (en) * 1989-03-17 1990-10-16

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61195399A (en) * 1985-02-26 1986-08-29 千代田化工建設株式会社 Counterflow preventive device for radioactive solution
JPH0779754B2 (en) * 1989-08-17 1995-08-30 株式会社クボタ Commercial rice cooker

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01171535U (en) * 1988-05-17 1989-12-05
JPH0260443U (en) * 1988-10-26 1990-05-02
JPH02125533U (en) * 1989-03-17 1990-10-16

Also Published As

Publication number Publication date
JPS5663297A (en) 1981-05-29

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