JPS5912193A - Leakage detecting device for recirculating pump of reactor - Google Patents

Leakage detecting device for recirculating pump of reactor

Info

Publication number
JPS5912193A
JPS5912193A JP57120505A JP12050582A JPS5912193A JP S5912193 A JPS5912193 A JP S5912193A JP 57120505 A JP57120505 A JP 57120505A JP 12050582 A JP12050582 A JP 12050582A JP S5912193 A JPS5912193 A JP S5912193A
Authority
JP
Japan
Prior art keywords
pressure
leak detection
leakage
pump
casing
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.)
Granted
Application number
JP57120505A
Other languages
Japanese (ja)
Other versions
JPH0413559B2 (en
Inventor
Takahisa Arima
有馬 高久
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
Toshiba Corp
Tokyo Shibaura 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, Tokyo Shibaura Electric Co Ltd filed Critical Toshiba Corp
Priority to JP57120505A priority Critical patent/JPS5912193A/en
Publication of JPS5912193A publication Critical patent/JPS5912193A/en
Publication of JPH0413559B2 publication Critical patent/JPH0413559B2/ja
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • 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

Abstract

PURPOSE:To detect leakage promptly even during the operation of a plant by a method wherein a leakage detecting pipeline is opened in a pocket formed in the opposing surface of a pump casing to measure the pressure of the pocket. CONSTITUTION:When the value of pressure of a pressure meter 22, which is indicated on an external leak detecting operation board 24, is increased, an operator closes a sluice valve 23 temporarily by the operation of the external leak detecting operation board 24, reduces the pressure in the leak detecting pipeline 21 to the degree of an atmospheric pressure and closes the sluice valve 23 again. The pressure in the leakage detecting pipeline 21 is increased again by closing the sluice valve 23 and the value of pressure indicated on the external leakage detecting operation board 24 is changed, however, the amount of leakage of cooling water from a seal mechanism 15 may be computed.

Description

【発明の詳細な説明】 [発明の技術分野] 本発明は原子炉再循環ポンプの漏洩検出装置に関する。[Detailed description of the invention] [Technical field of invention] The present invention relates to a leak detection device for a nuclear reactor recirculation pump.

[発明の技術的背景] 例えば沸騰水形原子炉では、原子炉圧力容器内に冷却水
を再循環させるために原子炉再循環ポンプが配設されて
いる。
[Technical Background of the Invention] For example, in a boiling water nuclear reactor, a reactor recirculation pump is provided to recirculate cooling water within the reactor pressure vessel.

この原子炉再循環ポンプの耐圧部は、例えばポンプケー
シング、ケーシングカバーおJ:びモータ台から構成さ
れており、ケーシングカバーはポンプケーシングとモー
タ台とにより3枚締めされスタッドポル1−により押圧
され−Cいる。そして、従来、ポンプケーシングとケー
シングカバーとの接触部は、例えばガスケットのような
シール機構により外部とシールされている。
The pressure-resistant part of this reactor recirculation pump is composed of, for example, a pump casing, a casing cover, and a motor stand.The casing cover is tightened by the pump casing and the motor stand, and is pressed by a stud pole. There is C. Conventionally, the contact portion between the pump casing and the casing cover is sealed from the outside by a sealing mechanism such as a gasket.

以上のように構成された原子炉再循環ポンプでは、ガス
ケットの劣化等により耐圧部から冷却水がリークするこ
とが考えるため、点検時等に目視によりリークの検出が
行われている。そして一定期間使用後は、ガスケットを
そのシール効梁の良否にかかわらず交換することにより
耐圧部からのリーク防止が図られている。
In the reactor recirculation pump configured as described above, cooling water is likely to leak from the pressure-resistant part due to deterioration of the gasket, etc., so leaks are detected visually during inspections and the like. After a certain period of use, the gasket is replaced regardless of the quality of the sealing beam to prevent leakage from the pressure-resistant section.

[背頻技術の問題点1 しかしながら、このような方法により耐圧部のリーク防
止対策を行なう場合には、ガスケツ1〜が健全であるに
も係わらずガスケットの交換作業を行なう必要があり、
作業者に多大な労力がかがるとともに作業者が放射線被
曝を被るおそれがある。
[Problem with the repetitive technology 1. However, when taking measures to prevent leaks from the pressure-resistant part using this method, it is necessary to replace the gaskets even though the gaskets 1 to 1 are healthy.
This requires a great deal of effort on the part of the workers, and there is a risk that the workers may be exposed to radiation.

また、一般にプラント運転中においては、目視によるリ
ーク検出は不可能であるため、耐圧部からのリークを迅
速に検出することができないという問題があった。
Furthermore, since it is generally impossible to visually detect leaks during plant operation, there has been a problem in that leaks from pressure-resistant parts cannot be detected quickly.

[発明の目的] 本発明はかかる従来の事情に対処してなされたもので、
原子炉再循環ポンプのリークをプラント運転時において
も迅速に、かつ、遠隔部において検出することのできる
原子炉再循環ポンプの漏洩検出装置を提供しようとする
ものである。
[Object of the invention] The present invention has been made in response to such conventional circumstances,
It is an object of the present invention to provide a leak detection device for a reactor recirculation pump that can detect leaks from a reactor recirculation pump quickly and remotely even during plant operation.

[発明の概要] すなわち本発明は、ポンプケーシングとケーシングカバ
ーとの対向面間に間隔をおいて配設される一組のシール
機構と、この−組のシール機構の間であって前記ポンプ
ケーシングまたはケーシングカバーの前記対向面に形成
されるポケットと、このポケットに開口するリーク検出
配管と、この3− リーク検出配管内の圧力を測定する圧力計と、前記リー
ク検出配管の前記圧力計下流に配設される仕切弁とから
なることを特徴とする原子炉再循環ポンプの漏洩検出装
置である。
[Summary of the Invention] That is, the present invention includes a pair of sealing mechanisms arranged at intervals between opposing surfaces of a pump casing and a casing cover, and a sealing mechanism between the pair of sealing mechanisms and the pump casing. or a pocket formed on the opposing surface of the casing cover, a leak detection pipe opening into the pocket, a pressure gauge for measuring the pressure in the leak detection pipe, and a pressure gauge downstream of the leak detection pipe. This is a leakage detection device for a nuclear reactor recirculation pump, characterized by comprising a gate valve provided therein.

[発明の実施例] 以下本発明の詳細を図面に示す一実施例について説明す
る。
[Embodiment of the Invention] The details of the present invention will be described below with reference to an embodiment shown in the drawings.

第1図は本発明の一実施例が適用される原子炉再循環ポ
ンプの一実施例を示すもので、図において符号1は高温
流体流入口2および流出口3を備えたポンプケーシング
を示している。このポンプケーシング1内にはポンプ挙
4が形成され、このポンプ室4内にはインペラ5が収容
されCいる。
FIG. 1 shows an embodiment of a nuclear reactor recirculation pump to which an embodiment of the present invention is applied, and in the figure, reference numeral 1 indicates a pump casing equipped with a hot fluid inlet 2 and an outlet 3. There is. A pump chamber 4 is formed within the pump casing 1, and an impeller 5 is accommodated within the pump chamber 4.

インペラ5の背面側には回転軸6が取付(プられ、この
回転軸6はポンプケーシング11而を覆うケーシングカ
バー7を貫通して外部に導出され、図示しない電動機等
に接続されている。インペラ5とケーシングカバー7と
の間には回転軸6を囲繞してジャーナル8が配設されて
おり、さらに、このジャーナル8を囲繞して水中ベアリ
ング9が配−Δ − 設されCいる。
A rotating shaft 6 is attached to the back side of the impeller 5, and this rotating shaft 6 passes through a casing cover 7 that covers the pump casing 11, is led out, and is connected to an electric motor, etc. (not shown). A journal 8 is disposed between the rotating shaft 6 and the casing cover 7, and an underwater bearing 9 is disposed surrounding the journal 8.

また、ケーシングカバー7と回転軸6との間にはメカニ
カルシール10が配設されおり、ケーシングカバー7は
モータ台11とポンプケーシング1により3枚締めされ
、スタッドボルト12によりポンプケーシング1に固定
されている。そしてポンプケーシング1とケーシングカ
バー7との間には本発明の一実施例の原子炉再循環ポン
プの漏洩検出装置13が配設されている。
Furthermore, a mechanical seal 10 is provided between the casing cover 7 and the rotating shaft 6, and the casing cover 7 is fastened with three pieces by the motor stand 11 and the pump casing 1, and is fixed to the pump casing 1 with stud bolts 12. ing. A leak detection device 13 for a reactor recirculation pump according to an embodiment of the present invention is disposed between the pump casing 1 and the casing cover 7.

第2図は第1図のA部の詳細を示すもので、図において
符@1はポンプケーシングを示しており、このポンプケ
ーシング1の上面にはケーシングカバー7の下端が当接
して配設されている。ポンプケーシング1の内周上端縁
には四部14が形成され、この凹部14には例えばガス
ケットからなるシール機構15が配設されている。ケー
シングカバー7の下面外周部には凹溝16が形成され、
この凹溝16には例えばOリングからなるシール機構1
7が配設されている。ケーシングカバー7の下向のシー
ル機構15とシール機構16との間には断面矩形状のポ
ケット18が形成され、このポケット18にはケーシン
グカバ−7側面に開口する連通孔19が開口している。
FIG. 2 shows details of part A in FIG. 1. In the figure, the symbol @1 indicates the pump casing, and the lower end of the casing cover 7 is placed in contact with the upper surface of the pump casing 1. ing. A four part 14 is formed on the upper edge of the inner circumference of the pump casing 1, and a sealing mechanism 15 made of, for example, a gasket is disposed in this recess part 14. A groove 16 is formed on the outer periphery of the lower surface of the casing cover 7.
This groove 16 has a sealing mechanism 1 consisting of an O-ring, for example.
7 are arranged. A pocket 18 having a rectangular cross section is formed between the downward sealing mechanism 15 and the sealing mechanism 16 of the casing cover 7, and a communication hole 19 opening on the side surface of the casing cover 7 is opened in the pocket 18. .

連通孔19の側面開口部にはエルボ20によりリーク検
出配管21が接続されており、このリーク検出配管21
には上流から順に圧力計22および仕切弁23が配設さ
れでいる。
A leak detection pipe 21 is connected to the side opening of the communication hole 19 by an elbow 20.
A pressure gauge 22 and a gate valve 23 are arranged in this order from upstream.

図におい゛C符号24は、例えば中央操作室に配設され
る外部リーク検出操作盤を示しており、この外部リーク
検出操作盤24は圧力計22からの圧力信号を入力しこ
の値を表示するとともに仕切弁23の開閉操作を行なう
In the figure, the symbol C 24 indicates an external leak detection operation panel disposed in the central operation room, for example, and this external leak detection operation panel 24 inputs the pressure signal from the pressure gauge 22 and displays this value. At the same time, the gate valve 23 is opened and closed.

以上のように構成された原子炉再循環ポンプの漏洩検出
装置では、例えばシール機構15の劣化によりシール機
構15から冷却水がリークした場合には、冷却水はポケ
ット18、連通孔19、リーク検出配管21を通り圧力
計21の圧力値を上昇させる。
In the reactor recirculation pump leak detection device configured as described above, when cooling water leaks from the seal mechanism 15 due to deterioration of the seal mechanism 15, for example, the cooling water is transferred to the pocket 18, the communication hole 19, and the leak detection device. It passes through the pipe 21 and increases the pressure value of the pressure gauge 21.

なお、一般に原子炉再循環ポンプ内の圧力は、例えば7
0K(1/cdであるため冷却水がシール機構15から
リークした場合には、圧力計22の圧力値は大幅に変化
する。また通常詩において仕切弁23は閉とされている
Generally, the pressure inside the reactor recirculation pump is, for example, 7.
Since it is 0K (1/cd), if the cooling water leaks from the seal mechanism 15, the pressure value of the pressure gauge 22 will change significantly.Also, in normal poetry, the gate valve 23 is closed.

このようにして外部リーク検出操作盤24に表示される
圧力計22の圧力値が上昇した場合には、作業者は外部
リーク検出操作盤24の操作により仕切弁23を一時開
とし、リーク検出配管21内の圧力を大気圧程度に低下
させ、再び仕切弁23を閉とする。この仕切弁23の閉
によりリーク検出配管21内の圧力が再び増加し、外部
リーク検出操作盤24に表示される圧力値が変化するこ
ととなるが、作業者はこの圧力値の変化の上昇速度から
シール機構15からの冷却水のり二り量を算出すること
ができる。
If the pressure value of the pressure gauge 22 displayed on the external leak detection operation panel 24 increases in this way, the operator temporarily opens the gate valve 23 by operating the external leak detection operation panel 24 and The pressure inside 21 is lowered to approximately atmospheric pressure, and the gate valve 23 is closed again. By closing this gate valve 23, the pressure inside the leak detection pipe 21 increases again, and the pressure value displayed on the external leak detection operation panel 24 changes. The amount of cooling water flowing from the seal mechanism 15 can be calculated from .

従って、以上のように構成された原子炉再循環ポンプの
漏洩検出装置では、原子炉再循環ポンプのリークを迅速
かつ確実に遠隔部において検出することかできるので、
原子炉再循環ポンプの信頼性を大幅に向上することがで
きる。また、ガスケット等のシール機構15の不必要な
交換作業は不要となるため、作業者の労力が軽減され、
これに伴う作業者の放射線被曝を大幅に低減することが
できる。ぞして、さらに圧力計22の圧力1昇速度から
リーク量を算出することができるため、リーク量の大小
に応じて適切な対策を迅速にたてることが可能となる。
Therefore, with the reactor recirculation pump leak detection device configured as described above, leaks in the reactor recirculation pump can be detected quickly and reliably at a remote location.
The reliability of reactor recirculation pumps can be significantly improved. In addition, unnecessary replacement work of the sealing mechanism 15 such as gaskets is not required, so the labor of the operator is reduced.
The accompanying radiation exposure of workers can be significantly reduced. Furthermore, since the amount of leakage can be calculated from the rate of increase in pressure per pressure of the pressure gauge 22, it becomes possible to quickly take appropriate measures depending on the magnitude of the amount of leakage.

[発明の効果] 以−1−述べたように本発明の原子炉再循環ポンプの漏
洩検出装置によれば、原子炉再循環ポンプからのリーク
をプラント運転中においても遠隔で迅速確実に検出する
ことができ、原子炉再循環ポンプの信頼性を大幅に向上
することができる。また、シール機構の交換に伴う作業
者の労力および放射線被曝を大幅に減少することができ
る。
[Effects of the Invention] As described in -1- above, according to the reactor recirculation pump leak detection device of the present invention, leaks from the reactor recirculation pump can be detected quickly and reliably remotely even during plant operation. This can greatly improve the reliability of the reactor recirculation pump. Furthermore, the labor and radiation exposure of workers associated with replacing the seal mechanism can be significantly reduced.

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

第1図は本発明の一実施例の原子炉再循環ポンプの漏洩
検出装置が適用される原子炉再循環ポンプを示す縦断面
図、第2図は本発明の一実施例の原子炉再循環ポンプの
漏洩検出装置を示す縦断面図である。 7− 1・・・・・・・・・・・・ポンプケーシング7・・・
・・・・・・・・・ケーシングカバー15.17・・・
シール機構 18・・・・・・・・・・・・ポケット21・・・・・
・・・・・・・リーク検出配管22・・・・・・・・・
・・・圧力計 23・・・・・・・・・・・・仕切弁 (7317)  代理人弁理士 則近憲佑(ばか1名) 8− 第1図
FIG. 1 is a vertical sectional view showing a reactor recirculation pump to which a leakage detection device for a reactor recirculation pump according to an embodiment of the present invention is applied, and FIG. 2 is a longitudinal sectional view showing a reactor recirculation pump according to an embodiment of the present invention. FIG. 2 is a longitudinal cross-sectional view showing a leakage detection device for a pump. 7- 1・・・・・・・・・Pump casing 7...
......Casing cover 15.17...
Seal mechanism 18...Pocket 21...
......Leak detection piping 22...
...Pressure gauge 23...Gate valve (7317) Representative patent attorney Norichika Kensuke (one idiot) 8- Figure 1

Claims (1)

【特許請求の範囲】[Claims] (1)ポンプケーシングとケーシングカバーとの対向面
間に間隔をおいて配設される一組のシール機構と、この
−組のシール機構の間であって前記ポンプケーシングま
たはケーシングカバーの前記対向面に形成されるポケッ
トと、このポケットに開口するリーク検出配管と、この
リーク検出配管内の圧力を測定する圧力計と、前記リー
ク検出配管の前記圧力計下流に配設される仕切弁とから
なることを特徴とする原子炉再循環ポンプの漏洩検出装
置。
(1) A pair of sealing mechanisms arranged at intervals between opposing surfaces of a pump casing and a casing cover, and a portion of the opposing surface of the pump casing or casing cover that is between this pair of sealing mechanisms. A leak detection pipe that opens into the pocket, a pressure gauge that measures the pressure inside the leak detection pipe, and a gate valve that is disposed downstream of the pressure gauge of the leak detection pipe. A leak detection device for a nuclear reactor recirculation pump, characterized by:
JP57120505A 1982-07-13 1982-07-13 Leakage detecting device for recirculating pump of reactor Granted JPS5912193A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57120505A JPS5912193A (en) 1982-07-13 1982-07-13 Leakage detecting device for recirculating pump of reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57120505A JPS5912193A (en) 1982-07-13 1982-07-13 Leakage detecting device for recirculating pump of reactor

Publications (2)

Publication Number Publication Date
JPS5912193A true JPS5912193A (en) 1984-01-21
JPH0413559B2 JPH0413559B2 (en) 1992-03-10

Family

ID=14787853

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57120505A Granted JPS5912193A (en) 1982-07-13 1982-07-13 Leakage detecting device for recirculating pump of reactor

Country Status (1)

Country Link
JP (1) JPS5912193A (en)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59100292U (en) * 1982-12-24 1984-07-06 株式会社日立製作所 reactor recirculation pump
JPH0158794U (en) * 1987-10-07 1989-04-12
JPH01142499A (en) * 1987-11-30 1989-06-05 Toshiba Corp Shaft seal operation diagnosis aid apparatus for reactor recirculation pump
JPH0216398A (en) * 1988-07-01 1990-01-19 Kubota Ltd Shaft seal device
EP0902439A2 (en) * 1997-09-11 1999-03-17 Siemens Aktiengesellschaft Leakage monitoring device and method of operating such a device
CN107654384A (en) * 2017-11-13 2018-02-02 利欧集团浙江泵业有限公司 A kind of water pump
CN108180149A (en) * 2017-12-20 2018-06-19 西安航天动力研究所 A kind of novel turbine pumps end face seal air-tightness detection method

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110491532B (en) * 2019-07-25 2021-07-06 岭澳核电有限公司 Nuclear power station main pump leakage abnormity processing system and method

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5313097A (en) * 1976-07-22 1978-02-06 Toshiba Corp Abnormality detector in nuclear container
JPS5768585A (en) * 1980-10-14 1982-04-26 Toshiba Corp Recirculation pump in nuclear reactor

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5313097A (en) * 1976-07-22 1978-02-06 Toshiba Corp Abnormality detector in nuclear container
JPS5768585A (en) * 1980-10-14 1982-04-26 Toshiba Corp Recirculation pump in nuclear reactor

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59100292U (en) * 1982-12-24 1984-07-06 株式会社日立製作所 reactor recirculation pump
JPH0158794U (en) * 1987-10-07 1989-04-12
JPH01142499A (en) * 1987-11-30 1989-06-05 Toshiba Corp Shaft seal operation diagnosis aid apparatus for reactor recirculation pump
JPH0216398A (en) * 1988-07-01 1990-01-19 Kubota Ltd Shaft seal device
EP0902439A2 (en) * 1997-09-11 1999-03-17 Siemens Aktiengesellschaft Leakage monitoring device and method of operating such a device
EP0902439A3 (en) * 1997-09-11 1999-06-23 Siemens Aktiengesellschaft Leakage monitoring device and method of operating such a device
CN107654384A (en) * 2017-11-13 2018-02-02 利欧集团浙江泵业有限公司 A kind of water pump
CN107654384B (en) * 2017-11-13 2024-01-09 利欧集团浙江泵业有限公司 Water pump
CN108180149A (en) * 2017-12-20 2018-06-19 西安航天动力研究所 A kind of novel turbine pumps end face seal air-tightness detection method
CN108180149B (en) * 2017-12-20 2019-07-16 西安航天动力研究所 A kind of turbine pump end face seal air-tightness detection method

Also Published As

Publication number Publication date
JPH0413559B2 (en) 1992-03-10

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