CN204610231U - A kind of nuclear power pump performance test system - Google Patents
A kind of nuclear power pump performance test system Download PDFInfo
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- CN204610231U CN204610231U CN201520275082.0U CN201520275082U CN204610231U CN 204610231 U CN204610231 U CN 204610231U CN 201520275082 U CN201520275082 U CN 201520275082U CN 204610231 U CN204610231 U CN 204610231U
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Abstract
The utility model discloses a kind of nuclear power pump performance test system, described system comprises: water source, small pump, separating valve, electric control valve, voltage stabilizer, electrical heating rod, heater, test pump, instrumentation, cooler, measuring circuit, wherein, described small pump is connected with between described water source and described measuring circuit, described voltage stabilizer, described heater, described cooler is all connected with described measuring circuit, described experimental pump and described instrumentation are installed on described measuring circuit, electrical heating rod described in one is equipped with in described voltage stabilizer and described heater, described cooler, described heater, described measuring circuit is equipped with described electric control valve, achieve nuclear power Pump Characteristic Test System structural design simple, cost is lower, versatility is better, the technique effect that test accuracy rate simple to operate is higher.
Description
Technical field
The utility model relates to nuclear-plant research field, particularly relates to a kind of nuclear power pump performance test system.
Background technique
Nuclear power pump is the visual plant in nuclear power, the maximum difference of nuclear power pump and conventional pump is to emphasize the integrity of pressure boundary and the performability under special operation condition, the reliability of pump and Security are had higher requirement, therefore need to make a service test before being installed to concrete equipment use at nuclear power pump, under nuclear power pump generally operates in high temperature, hyperbaric environment, and the Operational Limits of different pump is different, no matter newly the pump of research and development or product pump dispatch from the factory and all need to carry out corresponding evaluation test and performance test etc.
In the prior art, existing test platform mainly adopts the parameter of multiple testing apparatus to nuclear power pump to test one by one, causes platform device more, and occupation area is comparatively large, and design is complicated, and cost is comparatively large, and complicated operation, test accuracy rate is lower.
In sum, present inventor, in the process realizing model utility technological scheme in the embodiment of the present application, finds that above-mentioned technology at least exists following technical problem:
In the prior art, because existing test platform mainly adopts the parameter of multiple testing apparatus to nuclear power pump to test one by one, cause platform device more, occupation area is comparatively large, and design is complicated, and cost is larger, and complicated operation, test accuracy rate is lower, so existing nuclear power pump performance test platform exists the technical problem that design is complicated, cost is comparatively large, equipment takes up room greatly more, complicated operation test accuracy rate is lower.
Model utility content
The utility model provides a kind of nuclear power pump performance test system, solve existing nuclear power pump performance test platform and there is the technical problem that design is complicated, cost is comparatively large, equipment takes up room greatly, complicated operation test accuracy rate is lower more, achieve the technique effect that nuclear power Pump Characteristic Test System structural design is simple, cost is lower, versatility is better, test accuracy rate simple to operate is higher.
For solving the problems of the technologies described above, the embodiment of the present application provides a kind of nuclear power pump performance test system, and described system comprises:
Water source, small pump, electric control valve, voltage stabilizer, electrical heating rod, heater, test pump, instrumentation, cooler, measuring circuit, wherein, described small pump is connected with between described water source and described measuring circuit, described voltage stabilizer, described heater, described cooler is all connected with described measuring circuit, described test pump and described instrumentation are installed on described measuring circuit, electrical heating rod described in one is equipped with in described voltage stabilizer and described heater, described small pump, described heater, described cooler, described measuring circuit is equipped with described electric control valve.
Wherein, described system also comprises safety valve, and described safety valve is arranged on described voltage stabilizer.
Wherein, be provided with N bar flux test branch road in described measuring circuit, described flux test branch road is provided with flux test table and flow control valve, described N be more than or equal to 1 positive integer.
Wherein, described instrumentation includes but not limited to: temperature measuring instrument, pressure measuring instruments, flow measurement instrument.
Wherein, the described electric control valve stated described in measuring circuit is flow control valve.
Wherein, corresponding interface is provided with according to the interface parameters testing apparatus of described test pump.
The one or more technological schemes provided in the embodiment of the present application, at least have following technique effect or advantage:
Be that system comprises: water source owing to have employed nuclear power pump performance test system, small pump electric control valve, voltage stabilizer, electrical heating rod, heater, test pump, instrumentation, cooler, measuring circuit, wherein, is connected with described small pump between described water source and described measuring circuit, described voltage stabilizer, described heater, described cooler is all connected with described measuring circuit, and described test pump and described instrumentation are installed on described measuring circuit, is equipped with electrical heating rod described in, described heater in described voltage stabilizer and described heater, described cooler, described measuring circuit is equipped with the technological scheme of described electric control valve, that is, utilize heater, voltage stabilizer, cooler realizes temperature, pressure adjustable, and integrated many test loops are for measuring different flows (comprising small flow), to realize temperature on same device, pressure and flow is adjustable is applicable to the integrated of multiple nuclear power pump performance test, arranges voltage stabilizer and heater separately and by circuit cools, achieves the control respectively of loop temperature and pressure, to arrive temperature, the object that pressure is adjustable respectively, due to the restriction of flow measurement weight range and precision, in order to reach the measurement requirement of wide range of flow and measuring accuracy, the requirement of different flow measurement is realized by arranging different flow measurement branch roads, thus ensure that the requirement of measuring accuracy, in order to realize the adjustment of flow, be provided with multiple flow control valve, thus realize the requirement of flow coarse adjustment and accurate adjustment, to meet the requirement of Flow-rate adjustment, in order to meet the requirement of multiple test pump interface, be provided with different pump interface forms, achieve versatility comparatively strong, so, efficiently solve existing nuclear power pump performance test platform and there is design complexity, cost is larger, equipment takes up room greatly more, the technical problem that complicated operation test accuracy rate is lower, and then it is simple to achieve nuclear power Pump Characteristic Test System structural design, cost is lower, versatility is better, the technique effect that test accuracy rate simple to operate is higher.
Accompanying drawing explanation
Fig. 1 is the structural representation of the embodiment of the present application one center electric pump performance test system;
Wherein, 1-water source, 2-small pump, 3-cooler, 4-safety valve, 5-electric control valve, 6-heater, 7-electrical heating rod, 8-instrumentation, 9-test pump, 10-voltage stabilizer, 11-measuring circuit, 12-first branch road, 13-second branch road.
Embodiment
The utility model provides a kind of nuclear power pump performance test system, solve existing nuclear power pump performance test platform and there is the technical problem that design is complicated, cost is comparatively large, equipment takes up room greatly, complicated operation test accuracy rate is lower more, achieve the technique effect that nuclear power Pump Characteristic Test System structural design is simple, cost is lower, versatility is better, test accuracy rate simple to operate is higher.
Technological scheme during the application implements is for solving the problems of the technologies described above.General thought is as follows:
Have employed nuclear power pump performance test system is that system comprises: water source, small pump electric control valve, voltage stabilizer, electrical heating rod, heater, test pump, instrumentation, cooler, measuring circuit, wherein, is connected with described small pump between described water source and described measuring circuit, described voltage stabilizer, described heater, described cooler is all connected with described measuring circuit, and described test pump and described instrumentation are installed on described measuring circuit, is equipped with electrical heating rod described in, described heater in described voltage stabilizer and described heater, described cooler, described measuring circuit is equipped with the technological scheme of described electric control valve, that is, utilize heater, voltage stabilizer, cooler realizes temperature, pressure adjustable, and integrated many test loops are for measuring different flows (comprising small flow), to realize temperature on same device, pressure and flow is adjustable is applicable to the integrated of multiple nuclear power pump performance test, arranges voltage stabilizer and heater separately and by circuit cools, achieves the control respectively of loop temperature and pressure, to arrive temperature, the object that pressure is adjustable respectively, due to the restriction of flow measurement weight range and precision, in order to reach the measurement requirement of wide range of flow and measuring accuracy, the requirement of different flow measurement is realized by arranging different flow measurement branch roads, thus ensure that the requirement of measuring accuracy, in order to realize the adjustment of flow, be provided with multiple flow control valve, thus realize the requirement of flow coarse adjustment and accurate adjustment, to meet the requirement of Flow-rate adjustment, in order to meet the requirement of multiple test pump interface, be provided with different pump interface forms, achieve versatility comparatively strong, so, efficiently solve existing nuclear power pump performance test platform and there is design complexity, cost is larger, equipment takes up room greatly more, the technical problem that complicated operation test accuracy rate is lower, and then it is simple to achieve nuclear power Pump Characteristic Test System structural design, cost is lower, versatility is better, the technique effect that test accuracy rate simple to operate is higher.
In order to better understand technique scheme, below in conjunction with Figure of description and concrete mode of execution, technique scheme is described in detail.
Embodiment one:
In embodiment one, provide a kind of nuclear power pump performance test system, please refer to Fig. 1, described system comprises:
Water source 1, small pump 2, electric control valve 5, voltage stabilizer 10, electrical heating rod 7, heater 6, test pump 9, instrumentation 8, cooler 3, measuring circuit 11, wherein, described small pump 2 is connected with between described water source 1 and described measuring circuit 11, described voltage stabilizer 10, described heater 6, described cooler 3 is all connected with described measuring circuit 11, described test pump 9 and described instrumentation 8 are installed on described measuring circuit 11, electrical heating rod 7 described in one is equipped with in described voltage stabilizer 10 and described heater 6, described heater 6, described cooler 3, described measuring circuit 11 is equipped with described electric control valve 5.
Wherein, in actual applications, the described electric control valve in described measuring circuit 11 is specially flow control valve 5.
Wherein, in the embodiment of the present application, described system also comprises safety valve 4, and described safety valve 4 is arranged on described voltage stabilizer 10.
Wherein, in the embodiment of the present application, be provided with N bar flux test branch road in described measuring circuit 11, described flux test branch road is provided with flux test table and flow control valve, described N be more than or equal to 1 positive integer, as the first branch road 12 and the second branch road 13 in Fig. 1.
Wherein, in the embodiment of the present application, described instrumentation includes but not limited to: temperature measuring instrument, pressure measuring instruments, flow measurement instrument.
Wherein, in the embodiment of the present application, the described electric control valve stated described in measuring circuit is flow control valve.
Wherein, in the embodiment of the present application, corresponding interface is provided with according to the interface parameters testing apparatus of described test pump.
Wherein, in actual applications, please refer to Fig. 1, when carrying out nuclear power pump testing, different interfaces can be selected to be connected with testing apparatus according to the interface parameters of test pump, after test pump has connected, utilize small pump from water source water intaking to testing apparatus water-filling, and make testing apparatus reach the initial pressure of test pump operation, then stop small pump.
After aforesaid operations completes, firing test pump, according to the requirement of test, cold test can be carried out, cold test temperature can realize the control of loop temperature by heater and cooler, pressure can be heated by voltage stabilizing and the mode of cooler cooling controls, loop flow can be realized by flow control valve, the flow measurement loop (first branch road and second branch road) different according to the Selecting parameter of test pump, to realize the requirement of different flow measuring accuracy, in process of the test, technical data required for the pump can be measured by instrumentation, for generating the flow-lift of pump, the pump performance curves such as power-efficient curve.
After completing cold test, by starting the electrical heating rod in voltage stabilizer and heater, can combine and test loop heated, the system that realizes heats up, boosting, after device to be tested reaches certain pressure, heats separately to voltage stabilizer, make its state that reaches capacity, then carry out draining, thus make in voltage stabilizer, to set up vapour chamber, after vapour chamber is set up, start the electrical heating rod in heater, heated up in loop together with voltage stabilizer, after the parameter that test pump to be achieved requires, carry out pump performance test.The pressure of voltage stabilizer, cooler regulating loop can be passed through in process of the test, the temperature of heater, cooler regulating loop can be passed through, be regulated the flow of test pump by modulating valve, by the measurement regulating different measurement branch roads to realize different flow.In process of the test, technical data required for the pump can be measured by instrumentation, for generating the pump performance curve such as flow-lift, power-efficient curve of pump, realizes overpressure protection in process of the test by safety valve.
After completing pump performance test, by cooler to testing apparatus decrease temperature and pressure, heat is imported water source, cooling rate is regulated by electric control valve, after test loop pressure reaches certain value, to disappear vapour chamber to voltage stabilizer, after vapour chamber is eliminated, open electric control valve and make voltage stabilizer and test loop associating step-down, after loop temperature to be tested, pressure drop to normal temperature, normal pressure, testing apparatus returns to stand-by state.
Wherein, in the embodiment of the present application, system in the application can realize loop temperature, pressure and flow and can regulate, namely for different pumps requirement (if any pump require 15MPa, 230 DEG C, some requirement 14MPa, 200 DEG C), all can be realized by present gantries, under same temperature, pressure state, the measurement of the different flow point of pump can be realized.
Technological scheme in above-mentioned the embodiment of the present application, at least has following technique effect or advantage:
Be that system comprises: water source owing to have employed nuclear power pump performance test system, small pump electric control valve, voltage stabilizer, electrical heating rod, heater, test pump, instrumentation, cooler, measuring circuit, wherein, is connected with described small pump between described water source and described measuring circuit, described voltage stabilizer, described heater, described cooler is all connected with described measuring circuit, and described test pump and described instrumentation are installed on described measuring circuit, is equipped with electrical heating rod described in, described heater in described voltage stabilizer and described heater, described cooler, described measuring circuit is equipped with the technological scheme of described electric control valve, that is, utilize heater, voltage stabilizer, cooler realizes temperature, pressure adjustable, and integrated many test loops are for measuring different flows (comprising small flow), to realize temperature on same device, pressure and flow is adjustable is applicable to the integrated of multiple nuclear power pump performance test, arranges voltage stabilizer and heater separately and by circuit cools, achieves the control respectively of loop temperature and pressure, to arrive temperature, the object that pressure is adjustable respectively, due to the restriction of flow measurement weight range and precision, in order to reach the measurement requirement of wide range of flow and measuring accuracy, the requirement of different flow measurement is realized by arranging different flow measurement branch roads, thus ensure that the requirement of measuring accuracy, in order to realize the adjustment of flow, be provided with multiple flow control valve, thus realize the requirement of flow coarse adjustment and accurate adjustment, to meet the requirement of Flow-rate adjustment, in order to meet the requirement of multiple test pump interface, be provided with different pump interface forms, achieve versatility comparatively strong, so, efficiently solve existing nuclear power pump performance test platform and there is design complexity, cost is larger, equipment takes up room greatly more, the technical problem that complicated operation test accuracy rate is lower, and then it is simple to achieve nuclear power Pump Characteristic Test System structural design, cost is lower, versatility is better, the technique effect that test accuracy rate simple to operate is higher.
Although described preferred embodiment of the present utility model, those skilled in the art once obtain the basic creative concept of cicada, then can make other change and amendment to these embodiments.So claims are intended to be interpreted as comprising preferred embodiment and falling into all changes and the amendment of the utility model scope.
Obviously, those skilled in the art can carry out various change and modification to the utility model and not depart from spirit and scope of the present utility model.Like this, if these amendments of the present utility model and modification belong within the scope of the utility model claim and equivalent technologies thereof, then the utility model is also intended to comprise these change and modification.
Claims (6)
1. a nuclear power pump performance test system, is characterized in that, described system comprises:
Water source, small pump, electric control valve, voltage stabilizer, electrical heating rod, heater, test pump, instrumentation, cooler, measuring circuit, wherein, described small pump is connected with between described water source and described measuring circuit, described voltage stabilizer, described heater, described cooler are all connected with described measuring circuit, described test pump and described instrumentation are installed on described measuring circuit, be equipped with electrical heating rod described in described voltage stabilizer and described heater, described heater, described cooler, described measuring circuit are equipped with described electric control valve.
2. system according to claim 1, is characterized in that, described system also comprises safety valve, and described safety valve is arranged on described voltage stabilizer.
3. system according to claim 1, is characterized in that, be provided with N bar flux test branch road in described measuring circuit, described flux test branch road is provided with flux test table and flow control valve, described N be more than or equal to 1 positive integer.
4. system according to claim 1, is characterized in that, described instrumentation includes but not limited to: temperature measuring instrument, pressure measuring instruments, flow measurement instrument.
5. system according to claim 1, is characterized in that, described in the described electric control valve stated in measuring circuit be flow control valve.
6. system according to claim 1, is characterized in that, the interface parameters testing apparatus according to described test pump is provided with corresponding interface.
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| CN201520275082.0U CN204610231U (en) | 2015-04-30 | 2015-04-30 | A kind of nuclear power pump performance test system |
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| CN201520275082.0U CN204610231U (en) | 2015-04-30 | 2015-04-30 | A kind of nuclear power pump performance test system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109555712A (en) * | 2018-11-21 | 2019-04-02 | 深圳中广核工程设计有限公司 | A kind of nuclear power station main pump integrated verification experimental rig |
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2015
- 2015-04-30 CN CN201520275082.0U patent/CN204610231U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109555712A (en) * | 2018-11-21 | 2019-04-02 | 深圳中广核工程设计有限公司 | A kind of nuclear power station main pump integrated verification experimental rig |
| CN109555712B (en) * | 2018-11-21 | 2020-08-11 | 深圳中广核工程设计有限公司 | Nuclear power station main pump integration verification test device |
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