CN212774713U - Overspeed test device for steam-driven auxiliary water supply pump of nuclear power plant - Google Patents
Overspeed test device for steam-driven auxiliary water supply pump of nuclear power plant Download PDFInfo
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- CN212774713U CN212774713U CN202021607705.7U CN202021607705U CN212774713U CN 212774713 U CN212774713 U CN 212774713U CN 202021607705 U CN202021607705 U CN 202021607705U CN 212774713 U CN212774713 U CN 212774713U
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Abstract
The utility model relates to a nuclear power plant's steam-operated auxiliary feed water pump overspeed test device, including automatic speed adjusting device, steam generator, steam turbine and steam-assisted pump, automatic speed adjusting device includes first cavity, second cavity and lever, the lever is located the below of first cavity and second cavity, the lever activity sets up on fixed platform, the tip of regulating valve pole and piston rod is articulated with the both ends of lever respectively, steam generator passes through the intake pipe and is connected with first cavity top, the steam turbine passes through the steam conduit and is connected with the upper portion of first cavity, steam turbine and steam-assisted pump coaxial coupling, the pump export and the pump case intake of steam-assisted pump are connected with the lower part and the upper portion of second cavity respectively. The utility model discloses an automatic speed adjusting device, steam generator, steam turbine and vapour assist the cooperation design of pump, effectively solve prior art and assist the inlet valve of pump through closing little vapour and carry out the overspeed test to vapour and assist the pump, lead to vapour to assist the pump and have the problem of damaging the risk.
Description
Technical Field
The utility model belongs to a debugging and operation technical field of nuclear power plant, in particular to steam-driven auxiliary feed pump overspeed test device of nuclear power plant.
Background
An auxiliary water supply system (ASG) is a special safety facility of a pressurized water reactor nuclear power plant, and has the main function of leading out waste heat of a reactor core during an accident so as to ensure the safety and controllability of the reactor. The steam-driven auxiliary water-feeding pump (called as steam-driven auxiliary pump for short) is used as active equipment of an ASG system, is nuclear safety equipment directly related to whether the ASG system can be normally operated, and the reliability of the ASG steam-driven auxiliary pump is important for the safety of a nuclear power station. Therefore, in order to ensure the safe availability of the steam-assisted pump, an overspeed (about 9058-9645 rpm) test is required to be performed periodically.
At present, the overspeed test mode of the steam-assisted pump is as follows: the inlet valve of the steam auxiliary pump is closed, the load is reduced, and the overspeed is carried out, and the mode has the following defects: the testing time is too long, the phenomena of impeller cavitation, even balance piston abrasion and equipment damage are easily caused due to the fact that a valve is closed too small and the water inflow is insufficient, transient cavitation and axial force unbalance are easily caused to a steam-assisted pump, the steam-assisted pump can be seriously damaged irreversibly, and the unit safety is seriously damaged; and the method of closing the inlet valve and the cavitation is adopted, so that great damage is caused to equipment, the overspeed test period of most nuclear power plants is short, the damage to the equipment is great, and the reliability and the economical efficiency of the equipment are reduced in the past.
SUMMERY OF THE UTILITY MODEL
The utility model aims at prior art's not enough and provide a nuclear power plant steam-driven auxiliary water feeding pump overspeed test device, through the cooperation design of automatic speed adjusting device, steam generator, steam turbine and steam auxiliary pump, effectively solve prior art and assist the inlet valve of pump through closing little steam and carry out the overspeed test to steam auxiliary pump, lead to steam auxiliary pump to have the problem of damaging the risk.
The utility model discloses the technical scheme who adopts:
a steam-driven auxiliary water feeding pump overspeed testing device of a nuclear power plant comprises an automatic speed regulating device, a steam generator, a steam turbine and a steam auxiliary pump, wherein the automatic speed regulating device comprises a first cavity, a second cavity and a lever, a plurality of through holes are formed in the side wall of the upper portion of the first cavity, a first regulating valve core and a second regulating valve core are arranged in the first cavity from bottom to top, a regulating valve rod is arranged at the bottom of the second regulating valve core, the regulating valve rod penetrates through the first regulating valve core and the bottom of the first cavity, a piston is arranged in the second cavity, a piston rod is arranged at the bottom of the piston, the end of the piston rod penetrates through the bottom of the second cavity, a spring and a regulating nut are arranged on the piston rod, two ends of the spring are respectively connected with the piston rod and the regulating nut, the lever is positioned below the first cavity and the, the lever is movably arranged on the fixed platform, and two ends of the lever are respectively hinged with the end parts of the adjusting valve rod and the piston rod;
the steam generator is connected with the top of the first cavity through an air inlet pipe, a flow dividing pipe is arranged on the air inlet pipe, the shunt pipe is connected with the lower part of the first cavity, the steam turbine is connected with the upper part of the first cavity through a steam pipeline, the air outlet end of the steam pipeline is arranged on the periphery of the through hole, the steam turbine and the steam-assisted pump are of a coaxial integral structure, a venturi tube is arranged on the outlet of the steam-assisted pump, the lateral outlet of the venturi tube is communicated with a first pipeline, the first pipeline is connected with the lower part of the second cavity, a pump shell water intake of the steam-assisted pump is connected with the top of the second cavity through the second pipeline, the second pipeline is provided with a first isolation valve, a pump inlet of the steam-assisted pump is connected with the second pipeline through a third pipeline, and the third pipeline is provided with a regulating valve.
Further, a second isolation valve is arranged on the third pipeline.
Furthermore, a first sealing ring is arranged at the joint of the first cavity and the adjusting valve rod.
Furthermore, a second sealing ring is arranged at the joint of the second cavity and the piston rod.
Furthermore, the caliber of the air inlet end of the shunt pipe is larger than the thickness of the valve core of the first regulating valve.
Compared with the prior art, the beneficial effects of the utility model are that:
1. the utility model effectively solves the problem that the auxiliary steam pump is damaged due to overspeed test of the auxiliary steam pump by closing the inlet valve of the auxiliary steam pump in the prior art through the matching design of the automatic speed regulating device, the steam generator, the steam turbine and the auxiliary steam pump; the device has low input cost, saves a large amount of maintenance cost and time, has low requirements on the skills of operators, and reduces the risk of human factor errors to a great extent; the method and the device avoid serious irreversible damage to the steam-assisted pump in the overspeed test, seriously harm the unit safety, effectively shorten the speed test time, improve the working efficiency, improve the reliability, economy and safety of the steam-assisted pump, and have wide application market.
2. The elasticity of the spring between the adjusting nut and the second cavity can be changed by adjusting the position of the adjusting nut on the piston rod, and the worker can set the spring force of the corresponding spring according to actual requirements.
3. Through the sliding of the valve core of the first regulating valve and the valve core of the second regulating valve in the first cavity, if the valve core of the first regulating valve is positioned above the air inlet pipe of the flow dividing pipe, the valve core of the second regulating valve is positioned at the top of the first cavity, and at the moment, the air inlet ends of the air inlet pipe and the flow dividing pipe are closed, so that steam cannot be continuously conveyed into the first cavity; if the valve core of the first regulating valve is positioned between the air inlet ends of the shunt pipes, or the valve core of the first regulating valve is positioned below the air inlet ends of the shunt pipes, and the valve core of the second regulating valve is positioned between the through holes, the steam generator conveys steam into the first cavity through the air inlet pipe and the shunt pipes, and then the steam is conveyed to the steam turbine through the through holes and the steam pipeline on the first cavity, so that sufficient steam is provided for the steam turbine.
Drawings
Fig. 1 is a schematic view of the overall structure of the present invention;
FIG. 2 is a state diagram of the present invention;
in the figure: 1. adjusting the valve rod; 2. a first cavity; 3. a first regulator valve spool; 4. a through hole; 5. an air inlet pipe; 6. a shunt tube; 7. a second regulator valve spool; 8. a steam generator; 9. a steam line; 10. a steam turbine; 11. a steam-assisted pump; 12. a venturi tube; 13. a first conduit; 14. a pump shell water intake; 15. a first isolation valve; 16. a pump inlet; 17. adjusting a valve; 18. a third pipeline; 19. a second conduit; 20. a second cavity; 21. a piston; 22. a spring; 23. adjusting the nut; 24. a piston rod; 25. a fixed platform; 26. a lever; 27. an outlet of the pump; 28. a second isolation valve.
Detailed Description
In order to better understand the technical content of the present invention, the following embodiments are provided, and the present invention is further described with reference to the accompanying drawings.
Referring to fig. 1 to 2, the utility model provides a steam-driven auxiliary water feeding pump overspeed test device of a nuclear power plant, which comprises an automatic speed regulating device, a steam generator 8, a steam turbine 10 and a steam auxiliary pump 11, wherein the automatic speed regulating device comprises a first cavity 2, a second cavity 20 and a lever 26, the first cavity 2 and the second cavity 20 are vertically arranged, the lever 26 is transversely arranged, a plurality of through holes 4 are arranged on the side wall of the upper part of the first cavity 2, a first regulating valve core 3 and a second regulating valve core 7 are arranged in the first cavity 2 from bottom to top, an adjusting valve rod 1 is arranged at the bottom of the second regulating valve core 7, the end part of the adjusting valve rod 1 passes through the first regulating valve core 3 and the bottom of the first cavity 2, the end part of the adjusting valve rod 1 extends out of the first cavity 2, the first regulating valve core 3 and the second regulating valve core 7 slide up and down in the first cavity 2, and further drive the adjusting valve, a piston 21 is arranged in the second cavity 20, a vertical piston rod 24 is arranged at the bottom of the piston 21, the end of the piston rod 24 penetrates through the bottom of the second cavity 20, the end of the piston rod 24 extends out of the second cavity 20, the piston 21 slides up and down in the second cavity 20 to further drive the piston rod 24 to move up and down, a spring 22 and an adjusting nut 23 are arranged on the piston rod 24, the spring 22 is sleeved outside the piston rod 24, an external thread is arranged at the lower part of the piston rod 24, the adjusting nut 23 is rotatably connected with the piston rod 24, two ends of the spring 22 are respectively fixedly connected with the bottom of the second cavity 20 and the adjusting nut 23, a lever 26 is positioned below the first cavity 2 and the second cavity 20, the lever 26 is movably arranged on a fixed platform 25, the fixed platform 25 has various structural forms in the mechanical industry, belongs to the conventional technology of the mechanical industry, and, not discussed, the fixed platform 25 is rotatably connected with the middle part of the lever 26, so as to effectively ensure that the lever 26 can generate a lever effect, and two ends of the lever 26 are respectively hinged with the end parts of the adjusting valve rod 1 and the piston rod 24;
the steam generator 8 is connected with the top of the first cavity 2 through an air inlet pipe 5, the air inlet pipe 5 is provided with a shunt pipe 6, the shunt pipe 6 is connected with the lower part on the right side of the first cavity 2, the steam generator 8 conveys steam generated by the steam generator 8 to the upper part and the lower part of the first cavity 2 through the air inlet pipe 5 and the shunt pipe 6, and then the steam is conveyed to the steam turbine 10 through the through hole 4 and the steam pipeline 9 on the first cavity 2 to provide sufficient steam for the steam turbine 10, the steam turbine 10 is connected with the upper part of the first cavity 2 through the steam pipeline 9, the air outlet end of the steam pipeline 9 is arranged at the periphery of the through hole 4, the steam in the first cavity 2 is conveyed into the steam turbine 10 through the through hole 4 and the steam pipeline 9, the steam turbine 10 and the auxiliary steam pump 11 are of a coaxial integral structure, and the problem of load waste caused in, the pump outlet 27 of the steam auxiliary pump 11 is provided with a venturi tube 12, a lateral outlet of the venturi tube 12 is communicated with a first pipeline 13, the first pipeline 13 is connected with the lower part of the right side of the second cavity 20, a pump shell water intake 14 of the steam auxiliary pump 11 is connected with the top of the second cavity 20 through a second pipeline 19, the second pipeline 19 is provided with a first isolation valve 15, a pump inlet 16 of the steam auxiliary pump 11 is connected with the second pipeline 19 through a third pipeline 18, the third pipeline 18 is provided with an adjusting valve 17, the water pressure discharged from the pump outlet 27 of the steam auxiliary pump 11 is lower than the water pressure in the pump shell of the steam auxiliary pump 11 by utilizing the pressure reduction effect of the venturi tube 12, the water pressure difference exists between the water discharged from the pump outlet 27 of the steam auxiliary pump 11 and the water discharged from the pump shell water intake 14 of the steam auxiliary pump 11 by utilizing the pressure reduction effect of the venturi tube 12, the water pressure of the two directly acts on the piston 21 in the second cavity, The lower pressure difference causes the sliding.
Specifically, a second isolation valve 28 is disposed on the third conduit 18. The second isolating valve 28 is additionally arranged, so that abnormal speed regulation of the steam auxiliary pump 11 caused by internal leakage of the regulating valve 17 can be effectively avoided.
Specifically, a first sealing ring is arranged at the joint of the first cavity 2 and the adjusting valve rod 1. Utilize first sealing washer effectively to prevent that adjusting valve rod 1 when reciprocating motion, the steam in the first cavity 2 from leaking from the junction of adjusting valve rod 1 and first cavity 2.
Specifically, a second sealing ring is disposed at a joint of the second cavity 20 and the piston rod 24. The second sealing ring is used to effectively prevent water in the second cavity 20 from seeping out from the connection when the piston rod 24 reciprocates.
Specifically, the air inlet end of the shunt pipe 6 is larger than the thickness of the first regulating valve core 3. Effectively guarantee that steam generator 8 carries to first cavity 2 in from intake pipe 5 and shunt tubes 6, carry to steam turbine 10 by the through-hole 4 of first cavity 2 again, set up the thickness that the inlet end of shunt tubes 6 is greater than first governing valve case 3, effectively guarantee that the air input of shunt tubes 6 inlet end is great.
The utility model discloses a theory of operation does:
the method comprises the following steps that firstly, a steam turbine 10 is started, the steam turbine 10 drives a steam auxiliary pump 11 to work, the steam auxiliary pump 11 forms auxiliary water supply with corresponding flow and pressure, water with different pressures is led out from two positions, namely a pump shell water intake 14 and a pump outlet 27, of the steam auxiliary pump 11 and is respectively conveyed to the upper portion and the lower portion of a second cavity 20, a piston 21 in the second cavity 20 slides up and down through the pressure difference of the water intake and the pump outlet 27, if the water pressure difference force of the water intake and the pump outlet is the same as the elastic force of a spring and the direction of the elastic force of the spring is opposite, the piston 21 does not slide in the second cavity 20, a lever 26 is in a balanced state, a steam generator 8 continuously conveys steam to a first cavity 2;
opening a first isolation valve 15, closing a regulating valve 17 and a second isolation valve 28, performing an overspeed test when the steam turbine 10 and the steam auxiliary pump 11 are in a normal state, gradually closing the first isolation valve 15 until the first isolation valve is closed, then opening the second isolation valve 28 and the regulating valve 17, wherein water at the upper part of a second cavity 20 and water at the downstream of a second pipeline 19 gradually flow back to a pump inlet 16 of the steam auxiliary pump 11 through a third pipeline 18, so that the water pressure at the upper part in the second cavity 20 is gradually reduced, a piston 21 slides upwards along the inner wall of the second cavity 20, because a piston rod 24 arranged at the bottom of the piston 21 is hinged with one end of a lever 26, the piston rod 24 drives one end of the lever 26 hinged with the piston rod to move upwards, the other end of the lever 26 pulls a regulating valve rod 1 to move downwards, so that a first regulating valve core 3 and a second regulating valve core 7 slide downwards in the first cavity 2, and then enough through holes 4 are opened, the steam in the first cavity 2 flows out from the through holes 4 and is conveyed to the steam turbine 10 through the steam pipeline 9, the steam input quantity of the steam turbine 10 is increased, the first regulating valve spool 3 is located between the air inlet ends of the shunt pipes 6, or the first regulating valve spool 3 is located below the air inlet ends of the shunt pipes 6, the second regulating valve spool 7 is located among the through holes 4, then the steam generator 8 conveys the steam into the first cavity 2 through the air inlet pipe 5 and the shunt pipes 6, and then the steam is conveyed to the steam turbine 10 through the through holes 4 on the first cavity 2 and the steam pipeline 9, sufficient steam is provided for the steam turbine 10, sufficient steam is continuously provided for the steam turbine, the rotating speed of a rotor of the steam turbine 10 is increased, and finally the overspeed of the rotor of the steam turbine 10 is realized, and the trip is. This device effectively solves prior art and carries out the overspeed test to vapour auxiliary pump 11 through closing the inlet valve of little vapour auxiliary pump 11, causes vapour auxiliary pump 11 to have the problem of damaging the risk, avoids causing serious irreversible damage to vapour auxiliary pump 11 in carrying out the overspeed test, seriously harms unit safety, has improved vapour auxiliary pump 11's reliability, economic nature and security.
The operation steps of the overspeed test are as follows:
1. fully opening the first isolation valve 15 installed on the second pipe 19 and fully closing the regulating valve 17 and the second isolation valve 28 installed on the third pipe 18;
2. when an overspeed test is carried out, the steam turbine 10 and the steam auxiliary pump 11 are started firstly, and then the next procedure is carried out after the operation is stable;
3. gradually closing the first isolation valve 15 under the normal state of the steam-assisted pump 11 until the first isolation valve 15 is closed;
4. the second isolation valve 28 is completely opened, then the regulating valve 17 is gradually opened, so that the second pipeline 19 positioned below the first isolation valve 15 is gradually depressurized, and the water at the upper part of the second cavity 21 and the water at the downstream of the second pipeline 19 gradually flow back to the pump inlet 16 of the steam-assisted pump 13 through the third pipeline 18;
5. the water pressure above the piston 21 of the second cavity 20 is gradually reduced, so that the piston 21 slides upwards in the second cavity 20, and because the end part of a piston rod 24 arranged at the bottom of the piston 21 is hinged with one end of a lever 26, and the piston rod 24 also drives one end of the lever 26 hinged with the piston rod to move upwards, the other end of the lever 26 drives the regulating valve rod 1 to move downwards, and further drives the first regulating valve spool 3 and the second regulating valve spool 7 to slide downwards in the first cavity 2, so that the steam in the first cavity 2 can be effectively conveyed to the steam turbine 10 from the through holes 4 and the steam pipeline 9, the steam conveying capacity of the steam turbine 10 is effectively increased, the rotor of the steam turbine 10 is gradually accelerated, and finally, the rotor overspeed is realized, and the tripping operation is automatically protected;
6. after the automatic protection is tripped, the second isolation valve 28 and the regulating valve 17 are closed;
7. fully opening the first isolation valve 15;
8. the guard rail box provided on the outer periphery of the regulating valve 17 and the second isolation valve 28 is locked to prevent malfunction.
The foregoing is only a preferred embodiment of the present invention, and it should be noted that, for those skilled in the art, a plurality of improvements and decorations can be made without departing from the technical principle of the present invention, and these improvements and decorations should also be regarded as the protection scope of the present invention.
Claims (5)
1. The utility model provides a steam-driven auxiliary feed pump overspeed test device of nuclear power plant which characterized in that: the automatic speed regulating device comprises a first cavity, a second cavity and a lever, a plurality of through holes are formed in the side wall of the upper portion of the first cavity, a first regulating valve core and a second regulating valve core are arranged in the first cavity from bottom to top, a regulating valve rod is arranged at the bottom of the second regulating valve core and penetrates through the first regulating valve core and the bottom of the first cavity, a piston is arranged in the second cavity, a piston rod is arranged at the bottom of the piston, the end portion of the piston rod penetrates through the bottom of the second cavity, a spring and a regulating nut are arranged on the piston rod, two ends of the spring are respectively connected with the piston rod and the regulating nut, the lever is located below the first cavity and the second cavity, and the lever is movably arranged on a fixed platform, two ends of the lever are respectively hinged with the end parts of the adjusting valve rod and the piston rod;
the steam generator is connected with the top of the first cavity through an air inlet pipe, a flow dividing pipe is arranged on the air inlet pipe, the shunt pipe is connected with the lower part of the first cavity, the steam turbine is connected with the upper part of the first cavity through a steam pipeline, the air outlet end of the steam pipeline is arranged on the periphery of the through hole, the steam turbine and the steam-assisted pump are of a coaxial integral structure, a venturi tube is arranged on the outlet of the steam-assisted pump, the lateral outlet of the venturi tube is communicated with a first pipeline, the first pipeline is connected with the lower part of the second cavity, a pump shell water intake of the steam-assisted pump is connected with the top of the second cavity through the second pipeline, the second pipeline is provided with a first isolation valve, a pump inlet of the steam-assisted pump is connected with the second pipeline through a third pipeline, and the third pipeline is provided with a regulating valve.
2. The nuclear power plant steam-driven auxiliary feed water pump overspeed test device according to claim 1, characterized in that: and a second isolating valve is arranged on the third pipeline.
3. The nuclear power plant steam-driven auxiliary feed water pump overspeed test device according to claim 1, characterized in that: and a first sealing ring is arranged at the joint of the first cavity and the adjusting valve rod.
4. The nuclear power plant steam-driven auxiliary feed water pump overspeed test device according to claim 1, characterized in that: and a second sealing ring is arranged at the joint of the second cavity and the piston rod.
5. The nuclear power plant steam-driven auxiliary feed water pump overspeed test device according to claim 1, characterized in that: the caliber of the air inlet end of the shunt pipe is larger than the thickness of the valve core of the first regulating valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202021607705.7U CN212774713U (en) | 2020-08-05 | 2020-08-05 | Overspeed test device for steam-driven auxiliary water supply pump of nuclear power plant |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202021607705.7U CN212774713U (en) | 2020-08-05 | 2020-08-05 | Overspeed test device for steam-driven auxiliary water supply pump of nuclear power plant |
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| CN212774713U true CN212774713U (en) | 2021-03-23 |
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| CN202021607705.7U Active CN212774713U (en) | 2020-08-05 | 2020-08-05 | Overspeed test device for steam-driven auxiliary water supply pump of nuclear power plant |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113257444A (en) * | 2021-04-22 | 2021-08-13 | 广东核电合营有限公司 | Method for preventing overspeed tripping in full-flow test of auxiliary water supply steam-driven pump of nuclear power station |
| CN114068047A (en) * | 2021-11-15 | 2022-02-18 | 中核检修有限公司 | Auxiliary water inlet device for hydrostatic test |
-
2020
- 2020-08-05 CN CN202021607705.7U patent/CN212774713U/en active Active
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113257444A (en) * | 2021-04-22 | 2021-08-13 | 广东核电合营有限公司 | Method for preventing overspeed tripping in full-flow test of auxiliary water supply steam-driven pump of nuclear power station |
| CN113257444B (en) * | 2021-04-22 | 2022-09-09 | 广东核电合营有限公司 | Method for preventing overspeed tripping in full-flow test of auxiliary water supply steam-driven pump of nuclear power station |
| CN114068047A (en) * | 2021-11-15 | 2022-02-18 | 中核检修有限公司 | Auxiliary water inlet device for hydrostatic test |
| CN114068047B (en) * | 2021-11-15 | 2022-11-08 | 中核检修有限公司 | Auxiliary water inlet device for hydrostatic test |
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