CN101916596A - Device and system for vacuum-pumping loop of pressurized water reactor of nuclear power station - Google Patents
Device and system for vacuum-pumping loop of pressurized water reactor of nuclear power station Download PDFInfo
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- CN101916596A CN101916596A CN2010102398250A CN201010239825A CN101916596A CN 101916596 A CN101916596 A CN 101916596A CN 2010102398250 A CN2010102398250 A CN 2010102398250A CN 201010239825 A CN201010239825 A CN 201010239825A CN 101916596 A CN101916596 A CN 101916596A
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- vacuumizing
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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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a device for vacuum-pumping a loop of a pressurized water reactor of a nuclear power station, for vacuum-pumping the loop comprising a reactor pressure container, a pressure stabilizer and a steam generator. The vacuum-pumping device is respectively communicated with the reactor pressure container and the pressure stabilizer so as to form a sealed pumping loop. The vacuum-pumping device comprises a vacuum-pumping frame which is accessed into the sealed pumping loop so as to separate water from steam in the sealed pumping loop. The invention also discloses a system for vacuum-pumping a loop of a pressurized water reactor of a nuclear power station. The device and the system of the invention can be connected to a loop so as to form the sealed pumping loop and separate water from steam in the sealed pumping loop, therefore promoting the running economical efficiency of the nuclear power station and decreasing the abrasion ratio of the device in the loop.
Description
Technical field
The present invention relates to the nuclear power field, relate in particular to a kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device and vacuumizing and exhausting system.
Background technology
As shown in Figure 1, structural representation for reactor primary circuit of pressurized water reactor nuclear power station in the prior art, wherein, when the pressurized-water reactor nuclear power plant unit normally moves, reactor is a full water state by reactor pressure vessel 701, voltage stabilizer 702 and steam generator 703 loop that forms that is connected, (discharge level need reach below the trunk line upper surface to need all that when the each overhaul of unit draining is carried out in above-mentioned loop, this loop water level elevation 9.28m is following), to finish unit relevant state exchange and maintenance of equipment work.Before unit starting or hydrostatic circuit test, then need this loop water-filling again, to discharge a large amount of air (the especially air in the steam generator 703U type pipe) in this loop, the air capacity in one loop is dropped to below the program required value of power station, to satisfy the service requirement of system and equipment, particularly guarantee the normal operation of three reactor coolant loop pumps 704.
At present, the basic mode of static exhaust and moving exhaust phase combination that adopts is finished the exhaust work in this loop during the pressurized-water reactor nuclear power plant overhaul.The concrete operations mode is as follows: at first, carry out the be connected water-filling exhaust in this loop of forming of reactor pressure vessel 701, voltage stabilizer 702 and steam generator 703, be called static exhaust, be about to this loop and be full of water, finish the exhaust of respective reaction core pressure vessel 701, voltage stabilizer 702 and some pipelines, but still retain a large amount of air in the steam generator 703U type pipe this moment, need move exhaust.In moving exhaust process, three reactor coolant loop pumps 704 move once respectively, three reactor coolant loop pumps 704 start once simultaneously then, gas in the U type pipe of steam generator 703 is arrived in the top of pressure vessel 701 and voltage stabilizer 702 and discharge thus, if disqualified upon inspection then needs to carry out again dynamic exhaust.Static exhaust adds the mode length consuming time of exhaust, needs more than 20 hour usually.
Adopt static exhaust to add the method for exhaust, not only need the long time, and repeatedly utilize reactor coolant loop pump 704 to move exhaust, increased the wearing and tearing of reactor coolant loop pump 704 and the risk of damage.
Summary of the invention
Technical matters to be solved by this invention is, a kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device and vacuumizing and exhausting system are provided, can seal and conduct mutually to form with a loop and seal the loop of bleeding, and can realize carbonated drink separation to the steam that described sealing is bled in the loop, improve the economy of nuclear power station operation, reduce the rate of wear of key equipment in the loop.
For solving the problems of the technologies described above, the invention discloses a kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device, be used for carrying out vacuumizing and exhausting to comprising by reactor pressure vessel, voltage stabilizer and the steam generator loop that forms that is connected, described vacuumizing and exhausting device seals and conducts mutually with described reactor pressure vessel, described voltage stabilizer respectively and forms the sealing loop of bleeding;
Described vacuumizing and exhausting device comprises that inserting described sealing bleeds in the loop and can realize the vacuumizing and exhausting stand that carbonated drink is separated to the described sealing steam of bleeding in the loop.
Described vacuumizing and exhausting stand comprises: be used for making the described sealing loop steam of bleeding to flow and the water ring vacuum pump of power is provided, is used to carry out steam-water separator, the filtrator with filtration and the blower fan that carbonated drink is separated along the described sealing fixed-direction of bleeding in the loop;
The described sealing of access that described water ring vacuum pump, described steam-water separator, described filtrator and described blower fan are connected is successively bled in the loop.
The described sealing loop of bleeding comprises supply channel, described vacuumizing and exhausting stand also comprises decompression regulating device and flow regulator, and described decompression regulating device and described flow regulator insert the adjusting of in the described supply channel water supply in the described supply channel being carried out pressure and flow respectively by isolation valve.
The described sealing loop of bleeding also comprises: the steam that ventilation air pipeline and white-out water lines, described sealing are bled in the loop enters in the described ventilation air pipeline through the described filtrator and the described blower fan of described vacuumizing and exhausting stand;
The steam that described sealing is bled in the loop inserts respectively in the described white-out water lines by isolation valve through described water ring vacuum pump, described steam-water separator, described filtrator.
Preferably, coating is provided with and is used to form water seal, the sealing water pot that waste gas can not be drained from hydrophobic loop on the described white-out water lines.
The described sealing loop of bleeding also comprises: be used for replenishing the destruction vacuum air inlet pipeline of air to the described sealing loop of bleeding;
Described vacuumizing and exhausting stand also comprises the vacuum pressure measuring instrument, and described vacuum pressure measuring instrument inserts in the described destruction vacuum air inlet pipeline.
The bottom of the framework that described vacuumizing and exhausting stand has is provided with water-collecting tray; Install universal wheel on the described vacuumizing and exhausting rack frame.
Described vacuumizing and exhausting device also comprises the top pressure closure that seals described reactor pressure vessel, and described top pressure closure is fixedly installed on the opening end of the described reactor pressure vessel that described reactor pressure vessel and described vacuumizing and exhausting stand can be sealed and conducted mutually.
Described top pressure closure comprises: the flange of described reactor pressure vessel of sealing cover and two way seal and described sealing cover, described sealing cover and described flange be welded seal mutually.
Described sealing cover is the hood-like body of disk with certain depth degree of depth, offer bleed interface and liquid level interface respectively, described vacuumizing and exhausting stand respectively by bleed interface and the flexible pipe of bleeding be tightly connected and the described sealing of access that is tightly connected of liquid level interface and water level metering flexible pipe is bled in the loop.
Lifting guiding orienting sleeve is set on the relative sidewall edge of described sealing cover;
Welding is provided with reinforcement on the inwall of described sealing cover, and described reinforcement is the radioactivity setting of arranging;
Described sealing cover extends from its inwall the supporting leg that is parallel to each other with its central axis is set.
Described flange is weldingly fixed on the lateral body end edge of described sealing cover, be flat circular, comprise: annular groove, air collector and keyway, described annular groove be opened in along described flange can with the contacted annular end face of described reactor pressure vessel on, described annular groove is offered the vent port that is conducted with described air collector;
Described air collector can be collected when described top pressure closure seals envelope and be pressed in escaping gas in described the above annular groove of reactor pressure vessel opening end;
Described keyway is opened in the correspondence position that described flange is used for ccontaining described reactor pressure vessel in-pile component positioning key.
The invention also discloses a kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station system, comprise the pressurized-water reactor nuclear power plant circuit system that is connected and is formed by reactor pressure vessel, voltage stabilizer and steam generator, also comprise: salable conducting inserts in the described pressurized-water reactor nuclear power plant circuit system can realize the sealing extract system that carbonated drink is separated to steam in the described pressurized-water reactor nuclear power plant circuit system;
Described sealing extract system comprises water ring vacuum pump, steam-water separator, filtrator and the blower fan that is connected successively.
Described vacuumizing and exhausting system also comprises: insert water system, ventilation ventilating system, white-out water system and vacuum breaker gas handling system in the described sealing extract system respectively.
Described water system inserts nuclear island demineralized water distribution system;
Described ventilation ventilating system access security shell ventilation ventilating system; Described white-out water system inserts nuclear island exhaust and draining system;
Described vacuum breaker gas handling system comprises access security shell continuous ventilating system.
A kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device of the embodiment of the invention and vacuumizing and exhausting system, can seal and conduct mutually to form with a loop and seal the loop of bleeding, and can realize carbonated drink separation to the steam that described sealing is bled in the loop, be applicable to reactor pit draining, reactor pressure vessel draining and two kinds of operating modes of not draining of reactor pit; Top pressure closure need not seal by other fasteners by being pressed on the reactor pressure vessel opening end from the resealing envelope; Vacuumizing and exhausting device and system can improve the economy of nuclear power station operation, reduce the rate of wear of key equipment in the loop.
Description of drawings
In order to be illustrated more clearly in the embodiment of the invention or technical scheme of the prior art, to do to introduce simply to the accompanying drawing of required use in embodiment or the description of the Prior Art below, apparently, accompanying drawing in describing below only is some embodiments of the present invention, for those of ordinary skills, under the prerequisite of not paying creative work, can also obtain other accompanying drawing according to these accompanying drawings.
Fig. 1 is the structural representation of reactor primary circuit of pressurized water reactor nuclear power station in the prior art;
Fig. 2 is that vacuumizing and exhausting device conducting that the embodiment of the invention provides inserts the principle of work synoptic diagram in the described reactor primary circuit of pressurized water reactor nuclear power station;
Fig. 3 a is first structural representation of the vacuumizing and exhausting stand that provides of the embodiment of the invention;
Fig. 3 b is second structural representation of the vacuumizing and exhausting stand that provides of the embodiment of the invention;
Fig. 4 is the principle of work synoptic diagram of the vacuumizing and exhausting stand that provides of the embodiment of the invention;
Fig. 5 a is the side-looking cross-sectional view of top pressure closure in the reactor primary circuit of pressurized water reactor nuclear power station that provides of the embodiment of the invention;
Fig. 5 b is the plan structure synoptic diagram of top pressure closure in the reactor primary circuit of pressurized water reactor nuclear power station that provides of the embodiment of the invention;
Fig. 5 c be in the reactor primary circuit of pressurized water reactor nuclear power station that provides of the embodiment of the invention top pressure closure look up structural representation;
Fig. 6 is the vacuumizing and exhausting system architecture synoptic diagram of the reactor primary circuit of pressurized water reactor nuclear power station that provides of the embodiment of the invention.
Embodiment
Below with reference to accompanying drawing the preferred embodiments of the present invention are described.
Referring to Fig. 2, for vacuumizing and exhausting device conducting that the embodiment of the invention provided inserts structural representation in the described reactor primary circuit of pressurized water reactor nuclear power station, wherein, described vacuumizing and exhausting device 1 is used for comprising by reactor pressure vessel 2, vacuumizing and exhausting is carried out in voltage stabilizer 3 and steam generator 4 loop that forms that is connected, described vacuumizing and exhausting device 1 respectively with described reactor pressure vessel 2, described voltage stabilizer 3 seals and conducts mutually and forms the sealing loop 10 of bleeding, and described vacuumizing and exhausting device 1 comprises that inserting described sealing bleeds in the loop 10 and can realize the vacuumizing and exhausting stand 12 that carbonated drink is separated to the described sealing gas of bleeding in the loop 10.
In conjunction with referring to Fig. 3 a, Fig. 3 b and Fig. 4, it is cubic that vacuumizing and exhausting stand 12 roughly is, and its some bars (not shown) that are connected successively by head and the tail are pieced together mutually and taken the framework 120 that forms and is supported, and preferably, framework 120 is double-deck weight body structure.
Vacuumizing and exhausting stand 12 comprises also and is used for making described sealing loop 10 gases of bleeding to flow and the water ring vacuum pump 121 of power is provided, is used for the described sealing steam that loop 10 flows along fixed-direction of bleeding is carried out steam-water separator 122, the filtrator 123 with filtration and the blower fan 124 that carbonated drink is separated along bleed fixed-direction in the loop 10 of described sealing that the described sealing of access that described water ring vacuum pump 121, described steam-water separator 122, filtrator 123 and described blower fan 124 are connected is successively bled in the loop 10.
During concrete enforcement, when vacuumizing and exhausting device 1 seals and conducts when forming sealing and bleeding loop 10 mutually with reactor pressure vessel 2, voltage stabilizer 3 respectively, under the effect of water ring vacuum pump 121, sealing is bled, and gas entrainment moisture can pass through water ring vacuum pump 121 and steam-water separator 122 respectively in the loop 10, realizes the carbonated drink separation.
The described sealing loop 10 of bleeding also comprises supply channel 101, described vacuumizing and exhausting stand 12 also comprises decompression regulating device 125 and flow regulator 126, and described decompression regulating device 125 and described flow regulator 126 insert respectively in the described supply channel 101 by some isolation valves (not shown) adjusting of pressure and flow is carried out in the water supply in the described supply channel 101.
In concrete the enforcement, because in the access vacuumizing and exhausting stand 12 of supply channel 101 scalable pressure of supply waters and water supply flow, by the adjusting of decompression regulating device 125 and flow regulator 126, pressure of supply water and water supply flow can be adjusted into the best-fit operating mode of water ring vacuum pump 121.
The described sealing loop 10 of bleeding also comprises ventilation air pipeline 102 and white-out water lines 103, and the gas that described sealing is bled in the loop 10 enters in the described ventilation air pipeline 102 through the described filtrator 123 and the described blower fan 124 of described vacuumizing and exhausting stand 12; The moisture that described sealing is bled in the loop 10 inserts respectively in the described white-out water lines 103 by some isolation valves (not shown) through described water ring vacuum pump 121, described steam-water separator 122, filtrator 123.
Preferably, coat on the described white-out water lines 103 and be provided with the sealing water pot 127 that is used to form water seal, during concrete enforcement, when the moisture in being bled in loop 10 in sealing entered in the white-out water lines 103, sealing water pot 127 can prevent effectively that radgas from revealing from white-out water lines 103.
The described sealing loop 10 of bleeding also comprises and is used for replenishing the destruction vacuum air inlet pipeline 104 of air to bleed loop 10 of described sealing, described vacuumizing and exhausting stand 12 also comprises vacuum pressure measuring instrument 128, and described vacuum pressure measuring instrument 128 inserts in the described destruction vacuum air inlet pipeline 104.
Preferably, the bottom of vacuumizing and exhausting stand 12 frameworks 120 is provided with water-collecting tray 1201, and water-collecting tray 1201 can effectively prevent to seal bleeds each pipeline that loop 10 has when revealing, and the radioactivity dirt is to the pickup on ground.
Preferably, installing universal wheel 1202 on vacuumizing and exhausting stand 12 frameworks 120.
Be understandable that, the quantity of water ring vacuum pump 121 and steam-water separator 122 does not limit, can be that water ring vacuum pump 121 and steam-water separator 122 each one accesses seal in the loop 10 of bleeding, also can insert many water ring vacuum pumps 121 and steam-water separator 122, two water ring vacuum pump structures as vacuumizing and exhausting stand 12, wherein, can adopt an operation, a standby mode, also can adopt two modes of working simultaneously, can effectively guarantee the normal operation of vacuumizing and exhausting stand 12.
In conjunction with referring to Fig. 5 a, Fig. 5 b and Fig. 5 c, embodiment of the invention vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device 1 also comprises the top pressure closure 14 that seals described reactor pressure vessel 2, and described top pressure closure 14 is fixedly installed on the opening end 21 of the described reactor pressure vessel 2 that described reactor pressure vessel 2 and described vacuumizing and exhausting stand 12 can be sealed and conducted mutually.
The lifting guiding is set with orienting sleeve 1414 on the sidewall edge of the lateral body that sealing cover 141 is relative, be understandable that, the mode of position that orienting sleeve 1414 is provided with and fixed guide cover 1414 can have multiple mode, for example, orienting sleeve 1414 can adopt bolted mode to be fixedly installed on the sealing cover 141, because bolted dismounting convenience can be adjusted the radial position of orienting sleeve 1414, to adapt to the position of the on-the-spot guidepost of nuclear power station.
Welding is provided with plurality of strengthening ribs 1415 on the inwall of sealing cover 141, and is preferred to strengthen the rigidity of sealing cover 141, and reinforcement 1415 is set to long and narrowly tabular be four that radioactivity is arranged.
Described air collector 1424 is arranged on described flange 142 and offers on the relative other end of annular groove 1,422 one ends, in concrete the enforcement, when top pressure closure 14 sealing envelopes were pressed in reactor pressure vessel 2 opening ends 21, escaping gas can enter air collector 1424 by the vent port in the annular groove 1,422 14222 in the annular groove 1422.
Number that air collector 1424 is provided with and particular location to each other do not limit, its can be opened in annular groove 1422 in arbitrary position of the described flange that is conducted of vent port 14222.
Keyway 1426 is opened in the correspondence position that flange 142 is used for ccontaining reactor pressure vessel 2 in-pile component positioning keys, in concrete the enforcement, when top pressure closure 14 sealing envelopes were pressed in reactor pressure vessel 2 opening ends 21, keyway 1426 can be dodged the positioning key of reactor pressure vessel 2 in-pile components.
A kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device of the embodiment of the invention is mainly used in the vacuumizing and exhausting operation that is connected and is formed a loop by reactor pressure vessel 2, voltage stabilizer 3 and steam generator 4 during the pressurized-water reactor nuclear power plant overhaul.
In the specific implementation, the principle of work synoptic diagram of the vacuumizing and exhausting stand that the embodiment of the invention provided as shown in Figure 4, reactor pressure vessel 2 in a loop is by pipeline and voltage stabilizer 3, steam generation. and device 4 is connected, the reactor-loop border isolates finishes that (water level drops to below the trunk line upper surface, among Fig. 1 below 9.28 meters) time, vacuumizing and exhausting device 1 seals and conducts mutually to form with described reactor pressure vessel 2, described voltage stabilizer 3 respectively and seals the loop 10 of bleeding, and vacuum pumping is carried out in 1 pair of this loop of vacuumizing and exhausting device.Concrete: by the hanger 1417 that has on the sealing cover 141 top pressure closure 14 is lifted to reactor pressure vessel 2 opening ends 21, because top pressure closure 14 has bigger deadweight, top pressure closure 14 sealing envelopes are pressed on described reactor pressure vessel 2 opening ends 21.
In other embodiments of above-mentioned seal process, vacuumizing and exhausting device 1 also can be other mechanisms except that above-mentioned top pressure closure 14 structures, can seal and conduct mutually with reactor pressure vessel 2 and forms the sealing loop 10 of bleeding as long as satisfy vacuumizing and exhausting device 1.
After reactor pressure vessel 2 sealing, by flexible pipe bleed interface 1412 and liquid level interface 1413 on top pressure closure 14 sealing covers 141 are connected on the vacuumizing and exhausting stand 12 respectively, the use of flexible pipe be more convenient for dismounting, save the running time.
During vacuumizing and exhausting stand 12 work, under the effect of water ring vacuum pump 121, sealing is bled, and gas entrainment moisture can pass through water ring vacuum pump 121 and steam-water separator 122 respectively in the loop 10, realizes the carbonated drink separation.During concrete enforcement: open the isolation valve 501 that seals in loop 10 supply channels 101 of bleeding, regulate decompression regulating device 125 and pressure of supply water is adjusted to the pressure of supply water that is fit to 121 work of vacuumizing and exhausting stand 12 water ring vacuum pumps, regulate flow regulator 126 in succession water supply flow is adjusted to the required working flow of water ring vacuum pump 121, water ring vacuum pump 121 water-fillings.Afterwards, close isolation valve 501 and flow regulator 126.
And then, open the isolation valve 502, isolation valve 503, isolation valve 504, isolation valve 505 and the isolation valve 506 that seal in the loop 10 of bleeding, when flexible pipe is connected to bleed interface 1412 and liquid level interface 1413 on top pressure closure 14 sealing covers 141 on the vacuumizing and exhausting stand 12, the water level monitoring instrument of opening in isolation valve 507, one loops is monitored demonstration to the bleed water level in loop 10 of sealing.
Reopen isolation valve 501 and flow regulator 126, start water ring vacuum pump 121, at this moment, the sealing that one loop gas entrapped moisture forms along voltage stabilizer 3 and reactor pressure vessel 2 and vacuumizing and exhausting stand 12 loop 10 of bleeding is passed through water ring vacuum pump 121 and steam-water separator 122 successively, after carbonated drink is separated, gas is through filter 123, blower fan 124 enters the ventilation air pipeline 102 that seals in the loop 10 of bleeding, enter in the containment ventilation ventilating system (EBA) in the nuclear power station by this pipeline, discharge at last, moisture is then through isolation valve 505, isolation valve 506 and sealing water pot 127 enter the white-out water lines 103 that seals in the loop 10 of bleeding, and are handled by nuclear island exhaust and draining system (RPE) that this pipeline enters in the nuclear power station.On white-out water lines 103, coat the sealing water pot 127 that is provided with, on white-out water lines 103, form water seal, can prevent effectively that radgas from releasing from white-out water lines 103.
Through the running of above-mentioned vacuumizing and exhausting stand 12, be evacuated to the value of regulation by the be connected pressure in the loop that forms of reactor pressure vessel 2, voltage stabilizer 3 and steam generator 4 the most at last.
A period of time is carried out in the vacuum pumping of vacuumizing and exhausting stand 12, after one circuit pressure reaches predetermined value, close isolation valve 504, isolation valve 501, carry out by the be connected moisturizing operation in the loop that forms of reactor pressure vessel 2, voltage stabilizer 3 and steam generator 4, (trunk line upper surface absolute altitude when water level is lower than the absolute altitude of this loop water level, 9.28 meters as shown in drawings), can water-filling limit, limit vacuumize keep this loop pressure in target pressure value.When water level is higher than this loop water level elevation, stoppage in transit water ring vacuum pump 121, only carry out the moisturizing operation, and can open isolation valve 508, replenish air by the isolation valve 508 that destroys in the vacuum air inlet pipeline 104 to the sealing loop 10 of bleeding through the air that purifies, accelerate a loop and be returned to atmospheric speed, in this process, need to guarantee that a loop water level is not less than the absolute altitude of this loop water level.When the final water level in a loop that forms when being connected by reactor pressure vessel 2, voltage stabilizer 3 and steam generator 4 is increased in the reactor pressure vessel 2 near 142 of top pressure closure 14 flanges (10.5 meters as shown in drawings), finish the water-filling exhaust in a loop.Gas is discharged from the loop at this moment, though still retain a small amount of gas in the U type pipe of steam generator 4, but can satisfy the program requirement of nuclear power station, after one vacuum-pumping loop water-filling exhaust is finished, can open isolation valve 509, isolation valve 510 in the white-out water lines 103, with the water emptying in the device.
Preferably, vacuumize with the moisturizing process in, destroy the pressure that vacuum pressure measuring instrument 128 in the vacuum air inlet pipeline 104 can tightly be monitored a loop, the water level monitoring instrument in the loop can be monitored demonstration to the bleed water level in loop 10 of sealing.
A kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device of the embodiment of the invention is applicable to reactor pit draining, reactor pressure vessel draining and two kinds of operating modes of not draining of reactor pit; All leave the level measuring interface on reactor pressure vessel 2 top pressure closures 14 and the vacuumizing and exhausting stand 12, when in the reactor pit when anhydrous, one loop middle water level measuring instrument seals in the nuclear island exhaust and draining system (RPE) in the loop 10 access nuclear power stations of bleeding by the level measuring interface 1413 on the top pressure closure 14 on the flexible pipe coupled reaction core pressure vessel; When in the reactor pit water being arranged, a loop middle water level measuring instrument is by the level measuring interface on the flexible pipe connection vacuumizing and exhausting stand 12.
As shown in Figure 6, the embodiment of the invention also discloses a kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station system 6, described vacuumizing and exhausting system 6 comprises the pressurized-water reactor nuclear power plant circuit system 60 that is connected and is formed by reactor pressure vessel 601, voltage stabilizer 602 and steam generator 603, and salable conducting inserts in the described pressurized-water reactor nuclear power plant circuit system 60 and can realize the sealing extract system 61 that carbonated drink is separated to gas in the described pressurized-water reactor nuclear power plant circuit system 60.
Described sealing extract system 61 comprises water ring vacuum pump 611, steam-water separator 612, filtrator 613 and blower fan 614, and described water ring vacuum pump 611, described steam-water separator 612, described filtrator 613 and described blower fan 614 are connected successively.
Vacuumizing and exhausting system 6 also comprises water system 62, ventilation ventilating system 63, white-out water system 64 and the vacuum breaker gas handling system 65 that inserts respectively in the described sealing extract system 61.
Described water system 62 comprises decompression regulating device 621 and flow regulator 622, and described decompression regulating device 621 and described flow regulator 622 insert respectively in the described water system 62 by some isolation valves (not shown) adjusting of pressure and flow is carried out in the water supply in the described sealing extract system 61.
Preferably, described water system 62 comprises nuclear island demineralized water distribution system.
Gas in the described sealing extract system 61 enters in the described ventilation ventilating system 63 through described filtrator 613 and described blower fan 614; Moisture in the described sealing extract system 61 inserts respectively in the described white-out water system 64 by some isolation valves (not shown) through described water ring vacuum pump 611, described steam-water separator 612, filtrator 613.
Preferably, ventilation ventilating system 63 access security shells ventilation ventilating system; Described white-out water system 64 inserts nuclear island exhaust and draining system.
Preferably, vacuum breaker gas handling system 65 access security shell continuous ventilating systems.
The embodiment of a kind of vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station of embodiment of the invention system 6 is identical with the embodiment of above-mentioned vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station, repeats no more.
Embodiment of the invention vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device and system, can seal and conduct mutually to form with a loop and seal the loop of bleeding, and can realize carbonated drink separation to the steam that described sealing is bled in the loop, be applicable to reactor pit draining, reactor pressure vessel draining and two kinds of operating modes of not draining of reactor pit, save the process of dynamic exhaust, saved the overhaul critical path; Top pressure closure need not seal by other fasteners by being pressed on the reactor pressure vessel opening end from the resealing envelope; Vacuumizing and exhausting device and system can improve the economy of nuclear power station operation, reduce the rate of wear of key equipment in the loop, reduce risk and equipment maintenance cost.
Above disclosed is a kind of preferred embodiment of the present invention only, can not limit the present invention's interest field certainly with this, and therefore the equivalent variations of doing according to claim of the present invention still belongs to the scope that the present invention is contained.
Claims (15)
1. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device, be used for carrying out vacuumizing and exhausting to comprising by reactor pressure vessel, voltage stabilizer and the steam generator loop that forms that is connected, it is characterized in that described vacuumizing and exhausting device seals and conducts mutually to form with described reactor pressure vessel, described voltage stabilizer respectively and seals the loop of bleeding;
Described vacuumizing and exhausting device comprises that inserting described sealing bleeds in the loop and can realize the vacuumizing and exhausting stand that carbonated drink is separated to the described sealing steam of bleeding in the loop.
2. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 1, it is characterized in that described vacuumizing and exhausting stand comprises: be used for making the described sealing loop steam of bleeding to flow and the water ring vacuum pump of power is provided, is used to carry out steam-water separator, filtrator and the blower fan that carbonated drink is separated with filtration along the described sealing fixed-direction of bleeding in the loop;
The described sealing of access that described water ring vacuum pump, described steam-water separator, described filtrator and described blower fan are connected is successively bled in the loop.
3. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 2, it is characterized in that, the described sealing loop of bleeding comprises supply channel, described vacuumizing and exhausting stand also comprises decompression regulating device and flow regulator, and described decompression regulating device and described flow regulator insert the adjusting of in the described supply channel water supply in the described supply channel being carried out pressure and flow respectively by isolation valve.
4. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 2, it is characterized in that, the described sealing loop of bleeding also comprises: the steam that ventilation air pipeline and white-out water lines, described sealing are bled in the loop enters in the described ventilation air pipeline through the described filtrator and the described blower fan of described vacuumizing and exhausting stand;
The steam that described sealing is bled in the loop inserts respectively in the described white-out water lines by isolation valve through described water ring vacuum pump, described steam-water separator, described filtrator.
5. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 4 is characterized in that, coats to be provided with on the described white-out water lines to be used to form water seal, the sealing water pot that waste gas can not be drained from hydrophobic loop.
6. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 2 is characterized in that, the described sealing loop of bleeding also comprises: be used for replenishing the destruction vacuum air inlet pipeline of air to the described sealing loop of bleeding;
Described vacuumizing and exhausting stand also comprises the vacuum pressure measuring instrument, and described vacuum pressure measuring instrument inserts in the described destruction vacuum air inlet pipeline.
7. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 1 is characterized in that, the bottom of the framework that described vacuumizing and exhausting stand has is provided with water-collecting tray; Install universal wheel on the described vacuumizing and exhausting rack frame.
8. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 1, it is characterized in that, described vacuumizing and exhausting device also comprises the top pressure closure that seals described reactor pressure vessel, and described top pressure closure is fixedly installed on the opening end of the described reactor pressure vessel that described reactor pressure vessel and described vacuumizing and exhausting stand can be sealed and conducted mutually.
9. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 8, it is characterized in that, described top pressure closure comprises: the flange of described reactor pressure vessel of sealing cover and two way seal and described sealing cover, described sealing cover and described flange be welded seal mutually.
10. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 9, it is characterized in that, described sealing cover is the hood-like body of disk with certain depth degree of depth, offer bleed interface and liquid level interface respectively, described vacuumizing and exhausting stand respectively by bleed interface and the flexible pipe of bleeding be tightly connected and the described sealing of access that is tightly connected of liquid level interface and water level metering flexible pipe is bled in the loop.
11. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 10 is characterized in that, lifting guiding orienting sleeve is set on the relative sidewall edge of described sealing cover;
Welding is provided with reinforcement on the inwall of described sealing cover, and described reinforcement is the radioactivity setting of arranging;
Described sealing cover extends from its inwall the supporting leg that is parallel to each other with its central axis is set.
12. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station device as claimed in claim 9, it is characterized in that, described flange is weldingly fixed on the lateral body end edge of described sealing cover, be flat circular, comprise: annular groove, air collector and keyway, described annular groove be opened in along described flange can with the contacted annular end face of described reactor pressure vessel on, described annular groove is offered the vent port that is conducted with described air collector;
Described air collector can be collected when described top pressure closure seals envelope and be pressed in escaping gas in described the above annular groove of reactor pressure vessel opening end;
Described keyway is opened in the correspondence position that described flange is used for ccontaining described reactor pressure vessel in-pile component positioning key.
13. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station system, comprise the pressurized-water reactor nuclear power plant circuit system that is connected and forms by reactor pressure vessel, voltage stabilizer and steam generator, it is characterized in that, also comprise: salable conducting inserts in the described pressurized-water reactor nuclear power plant circuit system can realize the sealing extract system that carbonated drink is separated to steam in the described pressurized-water reactor nuclear power plant circuit system;
Described sealing extract system comprises water ring vacuum pump, steam-water separator, filtrator and the blower fan that is connected successively.
14. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station as claimed in claim 13 system, it is characterized in that described vacuumizing and exhausting system also comprises: insert water system, ventilation ventilating system, white-out water system and vacuum breaker gas handling system in the described sealing extract system respectively.
15. vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station as claimed in claim 14 system is characterized in that, described water system inserts nuclear island demineralized water distribution system;
Described ventilation ventilating system access security shell ventilation ventilating system; Described white-out water system inserts nuclear island exhaust and draining system;
Described destruction vacuum gas handling system access security shell continuous ventilating system.
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| CN2010102398250A CN101916596B (en) | 2010-07-28 | 2010-07-28 | Device and system for vacuum-pumping loop of pressurized water reactor of nuclear power station |
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| CN2010102398250A CN101916596B (en) | 2010-07-28 | 2010-07-28 | Device and system for vacuum-pumping loop of pressurized water reactor of nuclear power station |
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| CN101916596B CN101916596B (en) | 2013-05-08 |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102269606A (en) * | 2011-06-29 | 2011-12-07 | 中广核工程有限公司 | Method for monitoring flow rate of radioactive gas exhaust flow of nuclear power plant |
| CN103531258A (en) * | 2013-09-27 | 2014-01-22 | 中广核工程有限公司 | Exhaust method of one loop of nuclear power station |
| CN105957570A (en) * | 2016-06-28 | 2016-09-21 | 西安热工研究院有限公司 | System and method for carrying out hot test by utilizing external steam to raise temperature of primary circuit of nuclear power plant |
| CN111180095A (en) * | 2020-02-21 | 2020-05-19 | 三门核电有限公司 | Primary loop physical pre-deoxygenation method for pressurized water reactor nuclear power plant |
| CN112216411A (en) * | 2020-09-17 | 2021-01-12 | 岭东核电有限公司 | Primary circuit exhaust method of pressurized water reactor nuclear power station |
| CN112242205A (en) * | 2019-07-16 | 2021-01-19 | 中核核电运行管理有限公司 | Method for rapidly cooling voltage stabilizer of nuclear power unit |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002326002A (en) * | 2001-05-02 | 2002-11-12 | Mitsubishi Heavy Ind Ltd | Multistage gas-water separator |
| EP1489624A2 (en) * | 2003-06-18 | 2004-12-22 | Mitsubishi Heavy Industries, Ltd. | Nuclear reactor internal structure |
| CN101213615A (en) * | 2005-06-28 | 2008-07-02 | 阿雷瓦核能有限责任公司 | Pump unit for nuclear installations |
| CN101542633A (en) * | 2006-11-24 | 2009-09-23 | 阿雷瓦核能有限责任公司 | Nuclear engineering plant and method for operating a nuclear engineering plant |
| CN201780801U (en) * | 2010-07-28 | 2011-03-30 | 中科华核电技术研究院有限公司 | Primary circuit vacuum-pumping exhaustion device for reactor of pressurized water reactor nuclear power station and system |
-
2010
- 2010-07-28 CN CN2010102398250A patent/CN101916596B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002326002A (en) * | 2001-05-02 | 2002-11-12 | Mitsubishi Heavy Ind Ltd | Multistage gas-water separator |
| EP1489624A2 (en) * | 2003-06-18 | 2004-12-22 | Mitsubishi Heavy Industries, Ltd. | Nuclear reactor internal structure |
| CN101213615A (en) * | 2005-06-28 | 2008-07-02 | 阿雷瓦核能有限责任公司 | Pump unit for nuclear installations |
| CN101542633A (en) * | 2006-11-24 | 2009-09-23 | 阿雷瓦核能有限责任公司 | Nuclear engineering plant and method for operating a nuclear engineering plant |
| CN201780801U (en) * | 2010-07-28 | 2011-03-30 | 中科华核电技术研究院有限公司 | Primary circuit vacuum-pumping exhaustion device for reactor of pressurized water reactor nuclear power station and system |
Non-Patent Citations (1)
| Title |
|---|
| 《核动力工程》 20100430 黎春梅 岭澳核电站一回路系统真空排气台架设计 第94页到第95页及图1 1-15 第31卷, 第2期 2 * |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102269606A (en) * | 2011-06-29 | 2011-12-07 | 中广核工程有限公司 | Method for monitoring flow rate of radioactive gas exhaust flow of nuclear power plant |
| CN103531258A (en) * | 2013-09-27 | 2014-01-22 | 中广核工程有限公司 | Exhaust method of one loop of nuclear power station |
| CN103531258B (en) * | 2013-09-27 | 2016-08-17 | 中广核工程有限公司 | The method for exhausting of one loop of nuclear power station |
| CN105957570A (en) * | 2016-06-28 | 2016-09-21 | 西安热工研究院有限公司 | System and method for carrying out hot test by utilizing external steam to raise temperature of primary circuit of nuclear power plant |
| CN112242205A (en) * | 2019-07-16 | 2021-01-19 | 中核核电运行管理有限公司 | Method for rapidly cooling voltage stabilizer of nuclear power unit |
| CN112242205B (en) * | 2019-07-16 | 2022-08-19 | 中核核电运行管理有限公司 | Method for quickly cooling voltage stabilizer of nuclear power unit |
| CN111180095A (en) * | 2020-02-21 | 2020-05-19 | 三门核电有限公司 | Primary loop physical pre-deoxygenation method for pressurized water reactor nuclear power plant |
| CN112216411A (en) * | 2020-09-17 | 2021-01-12 | 岭东核电有限公司 | Primary circuit exhaust method of pressurized water reactor nuclear power station |
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Address after: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Patentee after: Dayawan Nuclear Power Running Management Co., Ltd. Patentee after: China General Nuclear Power Corporation Address before: 518000 Guangdong city of Shenzhen province Futian District science and technology building, Shangbu Road 15 Patentee before: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Patentee before: Dayawan Nuclear Power Running Management Co., Ltd. Patentee before: China Guangdong Nuclear Power Group Co., Ltd. |