CN103808513A - Offline testing device of emergency security mechanism of nuclear power station turbine - Google Patents
Offline testing device of emergency security mechanism of nuclear power station turbine Download PDFInfo
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- CN103808513A CN103808513A CN201210460419.6A CN201210460419A CN103808513A CN 103808513 A CN103808513 A CN 103808513A CN 201210460419 A CN201210460419 A CN 201210460419A CN 103808513 A CN103808513 A CN 103808513A
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- Y—GENERAL 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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention relates to an offline testing device of an emergency security mechanism of a nuclear power station turbine. The offline testing device of the emergency security mechanism of the nuclear power station turbine is used for performing offline testing on the GFR side unit of the emergency security mechanism of the nuclear power station turbine and comprises at least one retractable driving unit, at least one pressure sensing unit and a processing unit. The at least retractable driving unit is used for being connected with at least one guide release hook of the GFR side unit to control the moving position of the emergency release valve of the GFR side unit; the at least one pressure sensing unit is used for sensing the corresponding oil pressure signals of the GFR side unit during the testing process; the processing unit is connected with the at least one retractable driving unit and the at least one pressure sensing unit and used for outputting control signals to the at least one retractable driving unit after receiving the oil pressure signals of the at least one pressure sensing unit to control the at least one retractable driving unit to extend or retract correspondingly.
Description
Technical field
The present invention relates to million kilowatt advanced pressurized water reactor nuclear power plant gordian technique, particularly a kind of steam turbine for nuclear power station crisis security personnel mechanism off-line testing equipment.
Background technology
Nuclear power station is to utilize the nuclear fission of nuclear fuel to react the nuclear energy discharging to generate electricity, and thermal power station is that the chemical energy that utilizes the burning of fossil fuel to discharge generates electricity.Nuclear energy is more much bigger than chemical energy, so the fossil fuel that the nuclear fuel that nuclear power station consumes consumes than the thermal power plant of same power is wanted much less.For example, the coal-fired plant of a million kilowatt will consume approximately 3,000,000 tons of raw coal every year, and the nuclear power station of a same power be often only need supplement approximately 30 tons of nuclear fuels, the latter only for the former 100,000/.
The principle of work of typical nuclear power station is: main pump is sent pressure coolant into reactor, and general cooling medium remains on 120～160 atmospheric pressure.Under high-pressure situations, even if the temperature of cooling medium also can not be vaporized more than 300 ℃.The heat energy that cooling medium is emitted nuclear fuel is taken reactor out of, and enters steam generator, by thousands of heat-transfer pipes, heat is passed to the secondary circuit water outside pipe, makes water boiling produce steam; Coolant flow, after steam generator, then is sent into reactor by main pump, and circulation, constantly takes and change generation steam out of the heat in reactor so back and forth.From steam generator high temperature and high pressure steam out, promote Turbo-generator Set generating.The waste vapour that did merit condenses into water in condenser, then sends into well heater by the feed pump that condenses, and after reheating, sends steam generator back to.
Steam turbine for nuclear power station critical security personnel mechanisms (ETV) are the critical Valve control device assemblies of steam turbine; for the safety system of steam turbine; it is in exceeding steam turbine operation design permissible variation; cut off the protection oil that leads to each porthole of steam turbine; thereby make valve closing; steam turbine is stopped transport, and plays the object of Accident prevention generation, expansion and damage equipment.The critical security personnel of steam turbine for nuclear power station mechanism is generally positioned at the 1# bearing seat of unit, is divided into again steam-turbine lubrication, apical axis, cranking system side unit (the lower GGR of abbreviation side unit) and two formants of steam turbine adjusting oil system side (the lower GFR of abbreviation side unit) structural arrangement.
The inner structure complexity of steam turbine for nuclear power station critical security personnel mechanisms (ETV), if will identify it, need to complete oil filler test, overspeed test, electromagnetic trip test, lubricating oil low pressure test (LPT) and the test of steam turbine trip signal etc. again.The test of the critical security personnel of steam turbine for nuclear power station mechanism be all by upper be all by the trigger of GGR side unit, guide's Valve control device position of GFR side unit to be changed, realize the functions such as isolation, tripping operation and reset.The test of GFR side unit in the critical security personnel of steam turbine for nuclear power station mechanism in correlation technique, is to adopt an equipment identical with steam turbine GGR side unit of preparation to carry out site test, and cost is very high.
Summary of the invention
The technical problem to be solved in the present invention is, for the deficiency in correlation technique, provides a kind of improved steam turbine for nuclear power station crisis security personnel mechanism off-line testing equipment.
The technical solution adopted for the present invention to solve the technical problems is: a kind of steam turbine for nuclear power station crisis security personnel mechanism off-line testing equipment is provided, for the GFR side unit of steam turbine for nuclear power station crisis security personnel mechanism is carried out to off-line testing, this off-line testing equipment comprises at least one telescopic driver element, at least one pressure-sensing unit and processing unit; Described at least one telescopic driver element is for being connected with at least one guide's Valve control device of described GFR side unit, to control the emergency trip valve shift position of described GFR side unit; Described at least one pressure-sensing unit is carrying out the corresponding fuel injection pressure signal of process of the test for GFR side unit described in sensing; Described processing unit is connected with described at least one telescopic driver element and described at least one pressure-sensing unit respectively, for after receiving the fuel injection pressure signal of described at least one pressure-sensing unit, output control signal is given described at least one telescopic driver element, controls described at least one telescopic driver element and correspondingly stretches or shrink.
Preferably, described at least one telescopic driver element comprises oil cylinder and for controlling the flexible solenoid valve of piston rod of described oil cylinder, described solenoid valve is connected with described processing unit.
Preferably, described at least one telescopic driver element comprises two telescopic driver elements, and described two telescopic driver elements are connected with rear side guide Valve control device with front side guide's Valve control device of described GFR side unit respectively.
Preferably, described off-line testing equipment comprises the first pressure-sensing unit, the second pressure-sensing unit, the 3rd pressure-sensing unit, the 4th pressure-sensing unit, the 5th pressure-sensing unit, the 6th pressure-sensing unit, the 7th pressure-sensing unit and/or the 7th pressure-sensing unit, for being connected with the first low pressure oil entrance of described GFR side unit, the second low pressure oil entrance, front oiling outlet, rear oiling outlet, first oily B mouth, first oily A mouth, second oily B mouth and/or the second oily A mouth that resets that resets that resets that resets.
Preferably, described off-line testing equipment comprises electromagnetism reset button and/or front and back side electromagnetic trip button.
Preferably, described off-line testing equipment comprises the first fueller, for providing power oil as described GFR side unit.
Preferably, described off-line testing equipment comprises the second fueller, for the oil cylinder of oiling and the described telescopic driver element of driving.
Preferably, described the second fueller is also drawn an oily branch road, and oil is offered to oil test cylinder and/or return piston work after reducing pressure.
Preferably, described off-line testing equipment comprises pressure monitoring device, for monitoring the oil pressure of described GFR side unit.
Preferably, described pressure monitoring device comprises tensimeter on front side outlet and the rear side outlet that is connected to described GFR side unit, is connected to respectively tensimeter in the rear chamber of front and back side lining piston of described GFR side unit and/or the tensimeter on oiling oil circuit and low pressure oil oil circuit respectively.
The invention has the beneficial effects as follows: the GGR side unit that adopts the telescopic driver element replacing nuclear power station steam turbine crisis security personnel mechanism of processing unit control; can realize the off-line testing demand of GFR side unit, can effectively improve test efficiency, reduce experimentation cost.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing:
Fig. 1 is the schematic diagram of the steam turbine for nuclear power station crisis security personnel mechanism in some embodiments of the invention;
Fig. 2 is the mechanical/electrical triggering of the security personnel of steam turbine for nuclear power station crisis shown in Fig. 1 mechanism and the schematic diagram of resetting-mechanism unit;
Fig. 3 is the front/rear side emergency trip valve of the security personnel of steam turbine for nuclear power station crisis shown in Fig. 1 mechanism and the schematic diagram of isolated controlling valve cell;
Fig. 4 is the security personnel's manual operation test/resetting-mechanism of mechanism of steam turbine for nuclear power station crisis shown in Fig. 1 and the schematic diagram of oiling path unit;
Fig. 5 is the theory diagram of the steam turbine for nuclear power station crisis security personnel mechanism off-line testing device in some embodiments of the invention;
Fig. 6 is the layout of the steam turbine for nuclear power station crisis security personnel mechanism off-line testing device in some embodiments of the invention;
Fig. 7 is the schematic diagram of the steam turbine for nuclear power station crisis security personnel mechanism off-line testing device in some embodiments of the invention.
Embodiment
Below in conjunction with specific embodiment and Figure of description, the present invention is described in further details.
Fig. 1 shows the critical security personnel of the steam turbine for nuclear power station mechanism in some embodiments of the invention, it mainly comprises that two mechanical/electrical trigger and resetting-mechanism unit 100 the critical security personnel of this steam turbine for nuclear power station mechanism, front/rear side emergency trip valve and isolated controlling valve cell 200, and manual operation test/resetting-mechanism and oiling path unit 300, wherein, mechanical/electrical triggers and resetting-mechanism unit 100 is GGR side unit, and front/rear side emergency trip valve and isolated controlling valve cell 200 and manual operation test/resetting-mechanism and oiling path unit 300 are GFR side unit.
As shown in Figure 2, each mechanical/electrical triggering and resetting-mechanism unit 100 can comprise flip flop equipment 110, movement device 120 and resetting means 130 in certain embodiments.Flip flop equipment 110 comprises dropout solenoid 111, free-handle 112, bearing oil dropout oil cylinder 113 and overspeed trip pin 114.Movement device 120 comprises trip link 121, triggers trigger 122, hook 123 and guide's Valve control device control lever 124.Resetting means 130 comprises return piston 131 and resets hook pawl 132.
As follows with the mechanical/electrical triggering of front side and the course of action of resetting-mechanism unit 100:
Trip-gear can be realized by three kinds of methods: (1) simulates an electric trip signal to dropout solenoid 111.(2) inject the GGR oil of certain pressure to overspeed trip pin 114 by 11k point, oil pressure outwards throws away flyball, and the effect of simulation ultracentrifugation power makes release pin action.(3) by 10j point to bearing oil dropout oil cylinder 113 bottom drainings with simulation GGR low oil pressure signal.
The precondition that flip flop equipment 110 resets is each point of trigger mechanism attonity signal, by the 8h point injection pressure oil (9i point draining) of return piston 131, return piston 131 moves to left and makes to hook pawl 32 and clockwise rotate, drive hook 123 to move to right, now trigger trigger 122 and clockwise rotate and withstand hook 123 under the effect of its left side spring, thereby operated pilot Valve control device control lever 124 cuts out guide's Valve control device.Then, at the 9i of return piston 131 point injection pressure oil (8h point draining), piston moves to right and drives hook pawl 32 to rotate counterclockwise to spacing, to prevent that hooking pawl 32 tangles hook 123 and make trigger mechanism ineffective always.
As shown in Figure 3, front/rear side emergency trip valve and isolated controlling valve cell 200 can comprise front side guide's Valve control device 210, rear side guide Valve control device 220, front side emergency trip valve 230, rear side emergency trip valve 240, warm reset valve 250 and isolated controlling valve 260 in certain embodiments.
The regular path of front/rear side emergency trip valve and isolated controlling valve cell 200: GFR is fuel-displaced → warm reset valve 250(1a → 2b) and → front side emergency trip valve 230(4d → 5e) → rear side emergency trip valve 240(6f → 7g → 8h → 9i) → unload pressure electromagnetic valve.Now because front side guide's Valve control device 210 and rear side guide Valve control device 220 are closed, 16P point and 18R point are obstructed, 2B point is fuel-displaced through the guide connector 47(10J → 14N/15O that threads off) supply with the left chamber of piston 231 of front side emergency trip valve 230, the effect that oil pressure overcomes front side emergency trip valve 230 right side springs 232 makes piston 231 maintain right positions to block 17Q/19S point drain tap.Now isolated controlling valve 260 is in middle part conduction position, the release of 12L/13M point, and sleeve piston 233 maintains right positions to maintain normal oil circuit under the effect of spring 234 power.
Be described further as an example of front side emergency trip valve 230 example below.
Regular event process: once there is trip signal; flip flop equipment 110 moves front side guide's Valve control device 210; open 16P point drain tap; front side emergency trip valve 230 is because left chamber's decompression moves to left; 5F point oil-in is plugged; 17Q point drain tap is opened, and 5F point downstream oil is discharged by 20T point and 17Q point, makes thus to protect oily release to close GSE valve.
Reset after regular event: the 1) reset of front side emergency trip valve 230 and warm reset valve 250: original state state is as aforementioned, after front side guide's Valve control device 210 resets and closes, 16P point drain tap is closed, because 22V point draws self-shield oil export oil pressure, be zero and now protect oil export oil pressure, warm reset valve 250 pistons 251 move down to right-hand member in the effect of spring force, 1A → 2B primary path is blocked, hydraulic shock to main Valve control device while avoiding fuel feeding path again to get through, 1A → 3C fuel feeding passes through 10J → 15O path to the pressurising of front side emergency trip valve 230 left chamber, oil pressure moves to right piston 231 and blocks 17Q point drain tap.The isolation of 17Q oil extraction point makes 1A → 3C fuel feeding can be at main fuel feeding path setting oil pressure; in the time that increasing to a certain degree, protection oil pressure sends reset signal by 22V point to warm reset valve 250; its piston 251 is moved to left and open 1A → 2B normal fuel injection path; in addition, send forced resetting signal by 21U point to reset solenoid valve (not shown).
As shown in Figure 4, the regular path of manual operation test/resetting-mechanism and oiling path unit 300 is: GGR lubricating oil (GGR F50D7) road (decompression maintains 10S fuel feeding) after 310 voltage stabilizings of dead-weight accumulator supplies with forward and backward side bearing oil dropout oil cylinder 113a, 113b(as shown in Figure 1 by 12/13 path), another road is connected to reset solenoid valve 320.Reset solenoid valve 320 coordinates with wrong fuel tap 340,360, provides return piston 131 return oil by 4 → 5 → 9/10, and the oil extraction of return piston 131 reseting cavities is provided by 7/8 → 6 → X, guarantees thus to hook pawl 132 in the aforementioned state that gets loose.Wrong fuel tap 330,350 mediates, and 2/3 is communicated with assurance overspeed trip pin 114 oil filler test loops without oil pressure with leakage passage.
Fig. 5 and Fig. 6 show the critical security personnel of the steam turbine for nuclear power station mechanism off-line testing equipment 400 in some embodiments of the invention, and this off-line testing equipment system is used for simulating GGR side unit, to GFR side unit is tested by the mode of off-line.This off-line testing equipment 400 comprises two telescopic driver elements 410, several pressure-sensing unit 420 and processing unit 430.These two telescopic driver elements 410 are for being connected with rear side guide Valve control device 220 with front side guide's Valve control device 210 of GFR side unit, to control main Valve control device shift position; This some pressure-sensings unit 420 is carrying out the corresponding fuel injection pressure signal of process of the test for sensing GFR side unit; This processing unit 430 is connected with these two telescopic driver elements 410 and this several pressure-sensing unit 430 respectively, for after receiving the fuel injection pressure signal of these several pressure-sensing unit 430, output control signal is given these two telescopic driver elements 410, controls these two telescopic driver elements 410 and stretches or shrink.
Off-line testing equipment 400 can comprise fueller 440, front and back side electromagnetic trip button 450, electromagnetism reset button 460, reset solenoid valve 470 and pressure monitoring device 480 in certain embodiments.This fueller comprises large pump 441 and little pump 442.Large pump 441 is for example, for the pressure oil of elevated pressures (138Bar) is provided, to simulate GFR oil.Little pump 442 is for example, for the pressure oil of lower pressure (6.3Bar) is provided, with the oil cylinder 411 of oiling and the telescopic driver element 410 of driving.The pressure oil that little pump 442 provides also separates a road simultaneously, for example, after reduction valve decompression (reducing to 1.6Bar), for low pressure oil test cylinder (jar) and return piston.Front and back side electromagnetic trip button 450 is connected with processing unit 430, and electromagnetism reset button 460 is connected with reset solenoid valve 470.Pressure monitoring device 480 is connected with GFR side unit.
Pressure-sensing unit 420 can be pressure switch in certain embodiments, it can comprise front side low oil pressure measuring point MP1, rear side low oil pressure measuring point MP2, front side oiling pressure-measuring-point MP3, rear side oiling pressure-measuring-point MP4, return piston left side, front side pressure-measuring-point MP5, front side return piston right atrial pressure measuring point MP6, rear side return piston left side pressure-measuring-point MP7 and rear side return piston right atrial pressure measuring point MP8, these pressure-measuring-points respectively with the MP1-low oil pressure entrance of GFR side unit, MP2-low oil pressure entrance, oiling outlet before MP3-, oiling outlet after MP4-, the MP5-oily B mouth that resets, the MP6-oily A mouth that resets, MP7-oily B mouth and the MP6-oily A mouth that resets that resets is connected.
As shown in Figure 7, the front side low oil pressure measuring point MP1 of pressure-sensing unit 420 is connected on the oil circuit 301 of manual operation test/resetting-mechanism and oiling path unit 300, oil circuit 301 in the critical security personnel of steam turbine for nuclear power station mechanism, be with the front side bearing oil dropout oil cylinder 113a(of GGR side unit as shown in Figure 1) be connected, to detect the oil pressure in this oil circuit 301, in the time that front side low oil pressure measuring point MP1 senses oil pressure in oil circuit 301 and becomes low pressure by high pressure, show doing front side lubricating oil low pressure test (LPT) in system, processing unit 430 receives after corresponding signal, drive the oil cylinder 410a of telescopic driver element 410a to shrink, before driving, pilot-operated type Valve control device 210 moves to left, the dropout of analog field device can.The rear side low oil pressure measuring point MP2 of pressure-sensing unit 420 is connected with the oil circuit 302 of manual operation test/resetting-mechanism and oiling path unit 300, oil circuit 302 in the critical security personnel of steam turbine for nuclear power station mechanism with the rear side bearing oil dropout oil cylinder 113b(of GGR side unit as shown in Figure 1) be connected, in like manner, in the time that rear side low oil pressure measuring point MP2 senses in oil circuit 302 that oil pressure is by high step-down, be shown to be the low pressure test (LPT) of rear side lubricating oil, processing unit 430 receives after corresponding signal, drive the oil cylinder 410b of telescopic driver element 410b to shrink, drive rear side pilot-operated type Valve control device 220 to move to left, the dropout of analog field device can.
The front side oiling pressure-measuring-point MP3 system of pressure-sensing unit 420 is connected on the oil circuit 303 of manual operation test/resetting-mechanism and oiling path unit 300, oil circuit 303 in the critical security personnel of steam turbine for nuclear power station mechanism with the front side overspeed trip pin 114a(of GGR side unit as shown in Figure 1) be connected, for past front side overspeed trip pin 114a oiling, oil pressure outwards throws away flyball, and the effect of simulation ultracentrifugation power makes release pin action.Therefore, when front side oiling pressure-measuring-point MP3 senses while having pressure in oil circuit 303, show that system doing front side oil filler test, processing unit 430 receives after corresponding signal, drive the oil cylinder 410a of telescopic driver element 410a to shrink, before driving, pilot-operated type Valve control device 210 moves to left, the dropout of analog field device can.The rear side oiling pressure-measuring-point MP4 system of pressure-sensing unit 420 is connected on the oil circuit 304 of manual operation test/resetting-mechanism and oiling path unit 300, oil circuit 304 in the critical mechanism of ensuring public security of steam turbine for nuclear power station with the rear side overspeed trip pin 114b(of GGR side unit as shown in Figure 1) be connected.In like manner, when rear side oiling pressure-measuring-point MP4 senses while having pressure in oil circuit 304, show that system doing rear side oil filler test, processing unit 430 receives after corresponding signal, the oil cylinder 410b that controls telescopic driver element 410b shrinks, before driving, pilot-operated type Valve control device 220 moves to left, the dropout of analog field device can.
Return piston left side, the front side pressure-measuring-point MP5 of pressure-sensing unit 420, be connected with the oil circuit 305 of manual operation test/resetting-mechanism and oiling path unit 300, oil circuit 305 is connected with left chamber's (as shown in Figure 1) of the front side return piston 131a of GGR side unit in the critical security personnel of steam turbine for nuclear power station mechanism.The front side return piston right atrial pressure measuring point MP6 of pressure-sensing unit 420, be connected with the oil circuit 306 of manual operation test/resetting-mechanism and oiling path unit 300, oil circuit 306 is connected with the right chamber (as shown in Figure 1) of the front side return piston 131a of GGR side unit in the critical security personnel of steam turbine for nuclear power station mechanism.Return piston left side, front side pressure-measuring-point MP5 combines generating reset signal with front side return piston right atrial pressure measuring point MP6, processing unit 430 receives after reset signal, control and drive the oil cylinder 410b of telescopic driver element 410b to stretch, and drive front side guide's Valve control device 210 to move to right.
Rear side return piston left side pressure-measuring-point MP7 and the rear side return piston right atrial pressure measuring point MP8 of pressure-sensing unit 420, be connected with oil circuit 308 with the oil circuit 307 of manual operation test/resetting-mechanism and oiling path unit 300 respectively, the principle of work of its principle of work and front side return piston left side pressure-measuring-point MP5 and front side return piston right atrial pressure measuring point MP6 is basic identical, does not repeat them here.
Again as shown in Figure 7, pressure monitoring device 480 can comprise tensimeter 001LP, 002LP, 003LP, 004LP, 005SP and 006SP in certain embodiments, and tensimeter 001LP, 002LP are connected to respectively on the front/rear side emergency trip valve of GFR side unit and the front side outlet and rear side outlet of isolated controlling valve cell 200.Tensimeter 005SP, 006SP are connected to respectively in the rear chamber of front and back side lining piston of front/rear side emergency trip valve and isolated controlling valve cell 200.Tensimeter 003LP, 004LP are connected to respectively on oiling oil circuit and low pressure oil oil circuit.
From the above, off-line testing equipment 400 in some embodiments of the invention can be simulated the various field test of the critical security personnel of steam turbine for nuclear power station mechanism, realized the off-line testing requirement of the critical security personnel of steam turbine for nuclear power station mechanisms, for the critical security personnel of steam turbine for nuclear power station mechanism the test of GFR side unit splendid off-line testing platform is provided.
The above is only the preferred embodiment of the present invention, and protection scope of the present invention is also not only confined to above-described embodiment, and all technical schemes belonging under thinking of the present invention all belong to protection scope of the present invention.It should be pointed out that for those skilled in the art, several improvements and modifications without departing from the principles of the present invention, these improvements and modifications also should be considered as protection scope of the present invention.
Claims (10)
1. a steam turbine for nuclear power station crisis security personnel mechanism off-line testing equipment, for the GFR side unit of steam turbine for nuclear power station crisis security personnel mechanism is carried out to off-line testing, it is characterized in that, this off-line testing equipment comprises at least one telescopic driver element, at least one pressure-sensing unit and processing unit; Described at least one telescopic driver element is for being connected with at least one guide's Valve control device of described GFR side unit, to control the emergency trip valve shift position of described GFR side unit; Described at least one pressure-sensing unit is carrying out the corresponding fuel injection pressure signal of process of the test for GFR side unit described in sensing; Described processing unit is connected with described at least one telescopic driver element and described at least one pressure-sensing unit respectively, for after receiving the fuel injection pressure signal of described at least one pressure-sensing unit, output control signal is given described at least one telescopic driver element, controls described at least one telescopic driver element and correspondingly stretches or shrink.
2. off-line testing equipment according to claim 1, is characterized in that, described at least one telescopic driver element comprises oil cylinder and for controlling the flexible solenoid valve of piston rod of described oil cylinder, described solenoid valve is connected with described processing unit.
3. off-line testing equipment according to claim 2, it is characterized in that, described at least one telescopic driver element comprises two telescopic driver elements, and described two telescopic driver elements are connected with rear side guide Valve control device with front side guide's Valve control device of described GFR side unit respectively.
4. according to the off-line testing equipment described in claim 1-3 any one, it is characterized in that, described off-line testing equipment comprises the first pressure-sensing unit, the second pressure-sensing unit, the 3rd pressure-sensing unit, the 4th pressure-sensing unit, the 5th pressure-sensing unit, the 6th pressure-sensing unit, the 7th pressure-sensing unit and/or the 7th pressure-sensing unit, be used for the first low pressure oil entrance with described GFR side unit, the second low pressure oil entrance, front oiling outlet, rear oiling outlet, the oily B mouth of the first reset, the oily A mouth of the first reset, the second oily B mouth of reset and/or the oily A mouth of the second reset are connected.
5. according to the off-line testing equipment described in claim 1-3 any one, it is characterized in that, described off-line testing equipment comprises electromagnetism reset button and/or front and back side electromagnetic trip button.
6. according to the off-line testing equipment described in claim 1-3 any one, it is characterized in that, described off-line testing equipment comprises the first fueller, for providing power oil as described GFR side unit.
7. according to the off-line testing equipment described in claim 1-3 any one, it is characterized in that, described off-line testing equipment comprises the second fueller, for the oil cylinder of oiling and the described telescopic driver element of driving.
8. off-line testing equipment according to claim 7, is characterized in that, described the second fueller is also drawn an oily branch road, and oil is offered to oil test cylinder and/or return piston work after reducing pressure.
9. according to the off-line testing equipment described in claim 1-3 any one, it is characterized in that, described off-line testing equipment comprises pressure monitoring device, for monitoring the oil pressure of described GFR side unit.
10. off-line testing equipment according to claim 9, it is characterized in that, described pressure monitoring device comprises tensimeter on front side outlet and the rear side outlet that is connected to described GFR side unit, be connected to respectively tensimeter in the rear chamber of front and back side lining piston of described GFR side unit and/or the tensimeter on oiling oil circuit and low pressure oil oil circuit respectively.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210460419.6A CN103808513B (en) | 2012-11-15 | 2012-11-15 | Steam turbine for nuclear power station crisis security agencies off-line testing equipment |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210460419.6A CN103808513B (en) | 2012-11-15 | 2012-11-15 | Steam turbine for nuclear power station crisis security agencies off-line testing equipment |
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| CN103808513A true CN103808513A (en) | 2014-05-21 |
| CN103808513B CN103808513B (en) | 2016-12-21 |
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Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1160840A (en) * | 1967-06-30 | 1969-08-06 | Stal Laval Turbin Ab | Improvements in Release Mechanisms in Prime Movers |
| JPS58133404A (en) * | 1982-02-04 | 1983-08-09 | Toshiba Corp | Safety device of steam turbine |
| JPH03264708A (en) * | 1990-03-15 | 1991-11-26 | Toshiba Corp | Safety device for steam turbine |
| JPH11107706A (en) * | 1997-10-02 | 1999-04-20 | Toshiba Corp | Safety system for steam turbine |
| CN2791262Y (en) * | 2005-12-01 | 2006-06-28 | 青岛捷能汽轮机股份有限公司 | Online moving device for turbine security system |
| CN101514641A (en) * | 2003-09-22 | 2009-08-26 | 株式会社东芝 | Protection system for turbo machine and power generating equipment |
-
2012
- 2012-11-15 CN CN201210460419.6A patent/CN103808513B/en not_active Expired - Fee Related
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1160840A (en) * | 1967-06-30 | 1969-08-06 | Stal Laval Turbin Ab | Improvements in Release Mechanisms in Prime Movers |
| JPS58133404A (en) * | 1982-02-04 | 1983-08-09 | Toshiba Corp | Safety device of steam turbine |
| JPH03264708A (en) * | 1990-03-15 | 1991-11-26 | Toshiba Corp | Safety device for steam turbine |
| JPH11107706A (en) * | 1997-10-02 | 1999-04-20 | Toshiba Corp | Safety system for steam turbine |
| CN101514641A (en) * | 2003-09-22 | 2009-08-26 | 株式会社东芝 | Protection system for turbo machine and power generating equipment |
| CN2791262Y (en) * | 2005-12-01 | 2006-06-28 | 青岛捷能汽轮机股份有限公司 | Online moving device for turbine security system |
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| CN103808513B (en) | 2016-12-21 |
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Address after: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Applicant after: China General Nuclear Power Corporation Applicant after: Dayawan Nuclear Power Running Management Co., Ltd. Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Applicant before: China Guangdong Nuclear Power Group Co., Ltd. Applicant before: Dayawan Nuclear Power Running Management Co., Ltd. |
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