CN104005946A - Reactor coolant pump flow speed controller - Google Patents
Reactor coolant pump flow speed controller Download PDFInfo
- Publication number
- CN104005946A CN104005946A CN201410200720.2A CN201410200720A CN104005946A CN 104005946 A CN104005946 A CN 104005946A CN 201410200720 A CN201410200720 A CN 201410200720A CN 104005946 A CN104005946 A CN 104005946A
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- China
- Prior art keywords
- coolant pump
- reactor coolant
- speed controller
- housing
- flow speed
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- 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.)
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- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measuring Volume Flow (AREA)
Abstract
The invention relates to a reactor coolant pump flow speed controller which is placed at a reactor coolant pump low-pressure leakage system and is used for monitoring low-pressure leakage flow of three-level fluid dynamic pressure mechanical sealing. The reactor coolant pump flow speed controller is one of the most important auxiliary devices of a reactor coolant pump. Important study-judge data are provide for analyzing whether the reactor coolant pump is in a normal working state. The principle of a volumetric flowmeter is used for designing a flow measuring device special for a reactor coolant pump low-pressure leakage system, and the controller has the advantages of being simple in structure, accurate in measured data and reliable in operation.
Description
Technical field: the present invention relates to reactor coolant pump flow speed controller.
Background technique: reactor coolant pump flow speed controller is one of measuring and controlling equipment important in reactor coolant pump auxiliary system, whether be normally used for monitoring three grades of hydrodynamic mechanical seal working staties of reactor coolant pump, whether can directly judge nuclear power plant reactor coolant pump in safe and reliable running state by its feedack.At present, domestic not for the like product of reactor coolant pump.
Summary of the invention:
The object of the invention is that openly a kind of reliability is high, maintenance cost is low, be convenient to the reactor coolant pump flow speed controller of integral disassembly, assembly.Technological scheme of the present invention is: a kind of reactor coolant pump flow speed controller, a flange is all respectively installed with main valve body bottom in main valve body left side, left side flange (18) is communicated with inlet tube, inlet tube (11) with hexagon nut (12) is threaded with housing (1), seal ring (13) is installed in housing (1) seal groove, liquid-level switch (15) is vertically mounted on lid (17), between the two, adopt seal ring (16) sealing, the probe (21) of liquid-level switch (15) is positioned at measuring vessel (10), measuring vessel (10) is positioned at valve chamber (22), flange in the bottom (14) is with outer pipe (23), outer pipe (23) is communicated with measuring vessel (10), between lid (17) and housing (1), adopt spirotallic gasket (2) to seal and pass through waisting bolt (3) and hexagon nut (4) is fixed, housing (1) is upper with straight pin (5), straight pin (5) is time location for mounting cover (17), between flange in the bottom (14) and housing (1), rely on spirotallic gasket (6) to seal and pass through hexagon nut (9), sleeve (8) is connected with waisting bolt (7).
Working principle of the present invention:
Flow speed controller is positioned in reactor coolant pump low-pressure leak system, for monitoring three grades of hydrodynamic mechanical seal low-pressure leak flows.
When low-pressure leak flow is during higher than design load, illustrate that damaging appears in three grades of hydrodynamic mechanical seals, now do not allow reactor coolant pump to continue operation.
The import of flow speed controller and outlet(discharge) flange (14) are welded on low-pressure leak system pipeline, low-pressure leak enters flow speed controller by arrow direction indication in figure, flow into measuring vessel (10) through inlet tube (11), the volume of interior measuring vessel (10) and osculum size are by calculative determination, in the time that flow is less than design load, the osculum that liquid stream can pass through on measuring vessel (10) flows out, and flow out flow speed controller along arrow direction indication in figure, the liquid level switch liquid level that not will rise; In the time that flow is greater than design load, liquid stream can not all be discharged by osculum, and now the liquid level in measuring vessel (10) can constantly raise, and while arriving switch liquid level, liquid-level switch (15) can send signal, and prompting low-pressure leak flow is excessive.
The invention has the beneficial effects as follows:
The present invention is a measuring device of measuring three grades of hydrodynamic mechanical seal low-pressure leak flows of reactor coolant pump that is specifically designed to, and has filled up the blank of domestic this series products.The present invention relies on inlet tube and measuring vessel to form the liquid chunnel of low-pressure leak at flow speed controller inner chamber, the volume of measuring vessel and osculum flow are through demarcating, in the time that low-pressure leak flow is less than design load, liquid can flow out by the osculum from measuring vessel; In the time that flow is greater than design load, liquid can not all be discharged by osculum, and at this moment the liquid level in measuring vessel will rise, and in the time increasing to switch liquid level, liquid-level switch will be by probe to control room transmitted signal.Succeeding in developing of flow speed controller, strides forward major step by the production domesticization work that makes China's core main pump, for the safety of nuclear power station provides powerful guarantee, also for the competition of national nuclear power in international market and carry out condition to third party's outlet and prepare.Reactor coolant pump flow speed controller reliability of the present invention is high, is easy to dismounting, and maintenance cost is low, is conducive to the maintenance of core main pump, applied widely.
Brief description of the drawings
Fig. 1 is reactor coolant pump flow speed controller structure sectional view
Fig. 2 is the sectional view of measuring vessel (10)
Embodiment
As shown in Figure 1, a kind of reactor coolant pump flow speed controller, a flange is all respectively installed with main valve body bottom in main valve body left side, left side flange 18 is communicated with inlet tube, is threaded with housing 1 with the inlet tube 11 of hexagon nut 12, and seal ring 13 is installed in housing 1 seal groove, liquid-level switch 15 is vertically mounted on and covers on 17, between the two, adopt seal ring 16 to seal, the probe 21 of liquid-level switch 15 is positioned at measuring vessel 10, and measuring vessel 10 is positioned at valve chamber 22; Flange in the bottom 14 is with outer pipe 23, outer pipe 23 is communicated with measuring vessel 10, between lid 17 and housing 1, adopt spirotallic gasket 2 to seal and pass through waisting bolt 3 and hexagon nut 4 is fixed, on housing 1 with straight pin 5, straight pin 5 is time location for mounting cover 17, relies on spirotallic gasket 6 to seal and be connected by hexagon nut 9, sleeve 8 and waisting bolt 7 between flange in the bottom 14 and housing 1.
As shown in Figure 2, the structure of described measuring vessel 10 is: container side wall is with the osculum 19 through flow calibration, and the inner chamber 24 of container is with volumetric calibration, and rhone 25 is arranged at container bottom.
The present invention, by the demarcation to measuring vessel and osculum, ensures the accuracy of measurement result, reliable in structure, and operation expense is low.
Claims (2)
1. a reactor coolant pump flow speed controller, it is characterized in that: a flange is all respectively installed with main valve body bottom in main valve body left side, left side flange (18) is communicated with inlet tube, inlet tube (11) with hexagon nut (12) is threaded with housing (1), seal ring (13) is installed in housing (1) seal groove, liquid-level switch (15) is vertically mounted on lid (17), between the two, adopt seal ring (16) sealing, the probe (21) of liquid-level switch (15) is positioned at measuring vessel (10), measuring vessel (10) is positioned at valve chamber (22), flange in the bottom (14) is with outer pipe (23), outer pipe (23) is communicated with measuring vessel (10), between lid (17) and housing (1), adopt spirotallic gasket (2) to seal and pass through waisting bolt (3) and hexagon nut (4) is fixed, housing (1) is upper with straight pin (5), straight pin (5) is time location for mounting cover (17), between flange in the bottom (14) and housing (1), rely on spirotallic gasket (6) to seal and pass through hexagon nut (9), sleeve (8) is connected with waisting bolt (7).
2. a kind of reactor coolant pump flow speed controller according to claim 1, it is characterized in that: the structure of described measuring vessel (10) is: container side wall is with the osculum (19) through flow calibration, the inner chamber (24) of container is with volumetric calibration, and rhone (25) is arranged at container bottom.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410200720.2A CN104005946B (en) | 2014-05-13 | 2014-05-13 | Reactor coolant pump flow speed controller |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410200720.2A CN104005946B (en) | 2014-05-13 | 2014-05-13 | Reactor coolant pump flow speed controller |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104005946A true CN104005946A (en) | 2014-08-27 |
| CN104005946B CN104005946B (en) | 2016-07-06 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410200720.2A Active CN104005946B (en) | 2014-05-13 | 2014-05-13 | Reactor coolant pump flow speed controller |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104005946B (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108730310A (en) * | 2018-07-18 | 2018-11-02 | 哈尔滨电气动力装备有限公司 | Reactor coolant pump bolt tension conversion equipment |
| CN111255701A (en) * | 2020-01-22 | 2020-06-09 | 中国核动力研究设计院 | Low-pressure leakage flow measuring device and method for shaft seal pump for nuclear power plant |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4394346A (en) * | 1979-12-20 | 1983-07-19 | Tokyo Shibaura Denki Kabushiki Kaisha | Water level gauge for a nuclear reactor |
| GB2122356B (en) * | 1982-06-11 | 1986-02-05 | Exxon Research Engineering Co | Flow rate detector |
| JPS61246625A (en) * | 1985-04-25 | 1986-11-01 | Toshiba Corp | Flow rate detector |
| JPH0650439A (en) * | 1992-07-31 | 1994-02-22 | Fukuhara:Kk | Mechanical seal leakage detector |
| JP2009014477A (en) * | 2007-07-04 | 2009-01-22 | Chugoku Electric Power Co Inc:The | Device for measuring amount of leaked water |
| CN201886789U (en) * | 2010-12-09 | 2011-06-29 | 秦山核电有限公司 | Flowmeter for main pump seal leakage flow |
| CN102456418A (en) * | 2010-10-21 | 2012-05-16 | 中国广东核电集团有限公司 | Method for preventing abnormity of mechanical seal leakage rate of nuclear reactor coolant pump |
| CN203847368U (en) * | 2014-05-13 | 2014-09-24 | 哈尔滨电气动力装备有限公司 | Flow rate controller for reactor coolant pump |
-
2014
- 2014-05-13 CN CN201410200720.2A patent/CN104005946B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4394346A (en) * | 1979-12-20 | 1983-07-19 | Tokyo Shibaura Denki Kabushiki Kaisha | Water level gauge for a nuclear reactor |
| GB2122356B (en) * | 1982-06-11 | 1986-02-05 | Exxon Research Engineering Co | Flow rate detector |
| JPS61246625A (en) * | 1985-04-25 | 1986-11-01 | Toshiba Corp | Flow rate detector |
| JPH0650439A (en) * | 1992-07-31 | 1994-02-22 | Fukuhara:Kk | Mechanical seal leakage detector |
| JP2009014477A (en) * | 2007-07-04 | 2009-01-22 | Chugoku Electric Power Co Inc:The | Device for measuring amount of leaked water |
| CN102456418A (en) * | 2010-10-21 | 2012-05-16 | 中国广东核电集团有限公司 | Method for preventing abnormity of mechanical seal leakage rate of nuclear reactor coolant pump |
| CN201886789U (en) * | 2010-12-09 | 2011-06-29 | 秦山核电有限公司 | Flowmeter for main pump seal leakage flow |
| CN203847368U (en) * | 2014-05-13 | 2014-09-24 | 哈尔滨电气动力装备有限公司 | Flow rate controller for reactor coolant pump |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108730310A (en) * | 2018-07-18 | 2018-11-02 | 哈尔滨电气动力装备有限公司 | Reactor coolant pump bolt tension conversion equipment |
| CN111255701A (en) * | 2020-01-22 | 2020-06-09 | 中国核动力研究设计院 | Low-pressure leakage flow measuring device and method for shaft seal pump for nuclear power plant |
Also Published As
| Publication number | Publication date |
|---|---|
| CN104005946B (en) | 2016-07-06 |
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