CN102169733A - Passive and active combined special safety system for nuclear power plant - Google Patents
Passive and active combined special safety system for nuclear power plant Download PDFInfo
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- CN102169733A CN102169733A CN2011100377057A CN201110037705A CN102169733A CN 102169733 A CN102169733 A CN 102169733A CN 2011100377057 A CN2011100377057 A CN 2011100377057A CN 201110037705 A CN201110037705 A CN 201110037705A CN 102169733 A CN102169733 A CN 102169733A
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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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Abstract
The invention belongs to safety equipment for a nuclear power plant, in particular to a passive and active combined special safety system for the nuclear power plant. The system comprises a passive high-pressure core water supply tank, an accumulator, a low-pressure safety injection pump, a refueling water tank, a secondary-side passive residual heat removal heat exchanger, a vapor condensation water tank, a containment spray system, a passive reactor cavity water injection system, related valves and related pipes. When the nuclear power plant has a design basis accident or beyond design basis accident, through a series of passive and active safety facilities used in all steps, the circuit of a reactor and the core can be cooled effectively, so that the nuclear power plant can enter a safe cold shutdown condition smoothly; and thus, the serious accident consequence of the reactor is inhibited or relieved, damage caused by accidents is relieved, and the safety of the nuclear power plant is improved.
Description
Technical field
The invention belongs to nuclear plant safety equipment, be specifically related to a kind of nuclear power station non-actively with the engineered safety system that actively combines.
Background technology
The reactor of pressurized-water reactor nuclear power plant is under accident conditions, after taking the shutdown measure, reactor core still has a large amount of decay heats to be continued to discharge, and for reactor core is effectively cooled off, current now technical method promptly injects the lower boron water of big amount temperature (safety is injected) in a circuit system.At the accident initial stage, when a circuit system pressure was higher, existing power station adopted the enabling fashion of high-pressure safety injection pump to a loop water filling more, and the AP1000 of US Westinghouse company then realizes this goal by non-active high pressure reactor core water supply tank; After one circuit system pressure reduced, most power stations adopted the low pressure safety injection pump to a loop water filling, and AP1000 still utilizes the gravity head water filling by the non-active mode built-in material-changing water tank higher from the position.Non-ly be meant that actively equipment or system only rely on the modes relevant with spontaneous phenomenon such as gravity, density, Natural Circulation and drive, and need not to introduce other propulsion system, can reduce the equipment failure probability that causes because of the power machine fault greatly, improved the reliability of security system, active equipment then has advantages such as power is strong, pressure is high, flow is big, compact conformation.
Nuclear power plant containment shell is the 4th a road physical barrier of nuclear safety, under some accident conditions, the containment leak tightness that need prevent the too high initiation of containment internal pressure can lose efficacy, usually the method that adopts is to spray by pacifying in the jet pipe alignment containment space at the containment top, and the high-temperature vapor in the containment or other gas are carried out condensation or decrease temperature and pressure.Existing power station is general adopts by the material-changing water tank water intaking, and the mode of injecting spray pipe by spray pump realizes this security function.
Reactor pressure vessel is the important component part of presurized water reactor pressure boundary (the 3rd road physical barrier), and especially under the major accident operating mode, behind the core meltdown, pressure vessel is the visual plant that contains the reactor core fused mass.Remove the AP1000 of Westinghouse Electric, AP600 has designed outside the heap chamber waterflood system of being fetched water by built-in material-changing water tank, and other heap types are not found to melt the report of the engineered safeguards features design proposal of wearing about prevention major accident operating mode downforce container as yet at present.
Summary of the invention
The purpose of this invention is to provide a kind of nuclear power station non-actively with the engineered safety system that actively combines, high under the realization nuclear power plant emergency conditions that not only can be complete, in, the low pressure peace is annotated, security functions such as heap chamber water filling under safety shower and the major accident operating mode, and owing in design, taken into account the advantage of active equipment and non-active equipment, effectively raise the security system reliability, strengthened the adaptibility to response of security system under the nuclear power plant accident operating mode, can effectively prevent the gentle serious accident of separating, reduce the risk probability that major accident and extensive radioactivity discharge, improve the nuclear plant safety performance greatly.
Technical scheme of the present invention is as follows: a kind of nuclear power station non-actively with the engineered safety system that actively combines, comprise the non-active high pressure reactor core water supply tank of the corresponding some row of columns and loop number, described non-active high pressure reactor core water supply tank is higher than the reactor core setting, inject pipeline by safety and be communicated with, inject pipeline and be provided with the valve that triggers unlatching by a circuit pressure low signal with reactor-loop.
Further, aforesaid nuclear power station non-active and the engineered safety system that actively combines, wherein, described safety is injected pipeline one end and is connected bottom the non-active high pressure reactor core water supply tank, and the other end links to each other with the pressure vessel descending branch; The upper end of described non-active high pressure reactor core water supply tank links to each other for cold section with a loop main leg by pressure-equalizing line.
Further, aforesaid nuclear power station non-actively with the engineered safety system that actively combines, wherein, also comprise the corresponding some row secondary side passive residual heats discharge heat exchangers of columns and loop number, the heating surface bank that every row secondary side passive residual heat is discharged heat exchanger is immersed in the corresponding steam condensate (SC) case, described heating surface bank upstream connects main steam line, and the downstream is communicated with the steam generator water-supply line.
Further, aforesaid nuclear power station non-actively with the engineered safety system that actively combines, wherein, described steam condensate (SC) case is installed on the containment top layer, remove and to be used as the hot trap that the secondary side passive residual heat is discharged heat exchanger, also as the water source of containment spray system and non-active heap chamber waterflood system.
Further, aforesaid nuclear power station non-actively with the engineered safety system that actively combines, wherein, also comprise containment spray system, described containment spray system is connected with described steam condensate (SC) case with material-changing water tank with valve by pipeline respectively.
Further, aforesaid nuclear power station non-actively with the engineered safety system that actively combines, wherein, also comprise non-active heap chamber waterflood system, non-active heap chamber waterflood system is made up of pipeline and valve, and an end of its pipeline is communicated with the steam condensate (SC) case, and the other end is communicated with the heap chamber.
Further, aforesaid nuclear power station non-active and the engineered safety system that actively combines wherein, also comprise peace notes case and low pressure safety injection pump that existing nuclear power station is adopted.
Beneficial effect of the present invention is as follows:
(1) the present invention combines the advantage of active equipment and non-active equipment, on the basis that guarantees various security function completenesses, has improved system reliability, has reduced the risk probability of nuclear power plant's major accident, has improved the security performance of nuclear power station;
(2) application of secondary side passive residual heat discharge heat exchanger among the present invention, guaranteed that secondary side steam and condensate water are contained within the containment all the time under the accident conditions, reduced the risk that the secondary side radioactivity is revealed under the heat-transfer pipe of evaporator fracture accidents such as (SGTR);
(3) the present invention adopts non-active design proposal to subsystems such as the high-pressure safety injection of engineered safety system, auxiliary feedwaters, and structure obtains simplifying, and has reduced the quantity of active equipment, has reduced construction cost;
(4) at core meltdown phenomena under the major accident, designed non-active heap chamber waterflood system, utilize the cooling medium of continuous flooding pressure vessel bottom in the heap chamber, pressure vessel is effectively cooled off, effectively prevent from and alleviated the reactor core fused mass to melt and wear pressure vessel, thus the damage sequence that causes a large amount of radioactivity to discharge.
Description of drawings
Fig. 1 for the present invention non-actively with the engineered safety system structural representation that actively combines.
Among the figure, 1. non-active high pressure reactor core water supply tank 2. peaces are annotated case 3. low pressure safety injection pumps 4. material-changing water tanks 5. secondary side passive residual heats and are discharged cold section of heat exchanger 6. steam condensate (SC) casees 7. containment spray systems 8. non-active heap chamber waterflood systems 9. pressure vessels 10. reactor cores 11. main steam lines 12. steam generators 13. 1 loop main legs
Embodiment
The present invention will be described in detail below in conjunction with drawings and Examples.
As shown in Figure 1, a kind of non-active and engineered safety system that actively combines that is directed to pressurized-water reactor nuclear power plant, comprise the non-active high pressure reactor core water supply tank 1 of the corresponding some row of columns and loop number, described non-active high pressure reactor core water supply tank 1 is higher than reactor core 10 and is provided with, inject pipeline by safety and be communicated with, inject pipeline and be provided with the valve that triggers unlatching by a circuit pressure low signal with reactor-loop.In addition, described engineered safety system also comprises columns and the corresponding some row secondary side passive residual heats discharge heat exchangers 5 of loop number, the heating surface bank that every row secondary side passive residual heat is discharged heat exchanger 5 is immersed in the corresponding steam condensate (SC) case 6, described heating surface bank upstream connects main steam line 11, and the downstream is communicated with steam generator 12 water-supply lines.Further, described engineered safety system also comprises non-active heap chamber waterflood system 8, and non-active heap chamber waterflood system 8 is made up of pipeline and valve, and an end of its pipeline is communicated with steam condensate (SC) case 6, and the other end is communicated with the heap chamber.On this basis, described engineered safety system also comprises the containment spray system 7 that existing nuclear power station is possessed, and peace notes case 2 and low pressure safety injection pump 3, described containment spray system 7 is connected with described steam condensate (SC) case 6 with material-changing water tank 4 with valve by pipeline respectively.
In the present embodiment, the said equipment is according to single failure principle and symmetry, design two row autonomous systems, its columns is corresponding with the loop number of reactor, realize the corresponding device of identical function in the two row systems, its device structure, safe class and power system capacity are consistent, and the successful startup of the non-active high pressure reactor core water supply tank of arbitrary row all can be satisfied under the design basis accident operating mode demand to the flow and the capacity of high-pressure safety injection.Be different from the design of the AP1000 of Westinghouse Electric reactor core water supply tank, non-active high pressure reactor core water supply tank 1 among the present invention is by a circuit pressure signal triggering, the error safety injection of having avoided measuring system the voltage stabilizer false water level to occur and having caused, cancel level Four ADS fast pressure relief system in addition, avoided the more artificial introducing of large break of next circuit pressure border of accident conditions.In order to simplify description, the characterization device that present embodiment is only got in the row system is introduced.
Above-mentioned non-active high pressure reactor core water supply tank 1 injects a pipeline and a circuit communication, long term maintenance high pressure conditions by safety.Safety is injected the bottom that pipeline one end connects non-active high pressure reactor core water supply tank 1, and the other end links to each other with pressure vessel 9 descending brancies; The upper end of described non-active high pressure reactor core water supply tank 1 links to each other for cold section 13 with a loop main leg by pressure-equalizing line.Under the accident conditions, be subjected to the triggering of a circuit pressure low signal, related valve is opened, and when the pressure in a loop is in 10.0～12.0Mpa scope, promptly produces the pressure low signal, and the row of one in the electronic isolation valve of two-column parallel are opened.Non-active high pressure reactor core water supply tank 1 can inject pipeline with cooling medium along safety and enter the pressure vessel descending branch by the gravity head of difference in height generation, compensates the decline of water table in a loop, keeps the submergence and the waste heat of reactor core and derives; If accident conditions is difficult to smooth release in a loop down, non-active high pressure reactor core water supply tank 1 can utilize the connection effect of pressure-equalizing line, and total energy keeps certain drive ram, thereby has guaranteed that the safety to a loop is injected under the high pressure operating mode.
It all is the ripe equipment of using of existing power plant that above-mentioned peace is annotated case 2, low pressure safety injection pump 3 and material-changing water tank 4, can start action under relevant trigger pip, in the realization, the low pressure peace annotates security function.
Above-mentioned secondary side passive residual heat is discharged heat exchanger 5, and heating surface bank is immersed in the steam condensate (SC) case 6, and the heating surface bank upstream connects main steam line 11, and the downstream leads to the water-supply line of steam generator 12.Under the accident conditions, need to carry out when utilizing steam generator to discharge the function of residual heat of nuclear core, one loop hot water passes through steam generator heat-transfer pipe, heat is passed to secondary side, make the feedwater boiling of secondary side become steam, because the main steam line isolation valve cuts out under the accident conditions, steam is subjected to the effect of elevated pressures in the steam generator, enter the secondary side passive residual heat along pipeline and discharge heat exchanger 5, the heat-transfer pipe that the secondary side passive residual heat is discharged heat exchanger 5 is immersed in the steam condensate (SC) case 6, in the pipe is vapour, pipe is outer to be water, the steam condensation, condensate water flows out the heat-transfer pipe that the secondary side passive residual heat is discharged heat exchanger 5 under action of gravity, flow back to the feedwater piping of steam generator 12 along pipeline, reenter steam generator 12, keep the water level in the steam generator 12, secondary side passive residual heat discharge heat exchanger 5 pattern is according to this finished circulation, realize the refrigerating function of secondary side to a loop, make the smooth decrease temperature and pressure in a loop, and then in reaching, the low pressure peace is annotated the condition that drops into, thereby finally makes nuclear power station enter the safe condition of cold shut.
Above-mentioned steam condensate (SC) case 6, be installed on the containment top layer, arrange ringwise, submergence under water has the secondary side passive residual heat to discharge the heating surface bank of heat exchanger 5, when the secondary side passive residual heat is discharged heat exchanger 5 when carrying out its security function, a large amount of water can provide hot trap in the steam condensate (SC) case 6, make steam condensation in the heat-transfer pipe, realize the Natural Circulation of secondary side passive residual heat discharge heat interchanger 5, in the steam condensate (SC) case 6, density reduced after near the water the heat-transfer pipe was heated, and upwards flowed by buoyancy, arrive at behind the water surface by natural convection with the temperature of mixing of peripheral cold water and reduce density and increase, gravitate sinks under the water again, goes round and begins again, and forms the Natural Circulation that continues near heating surface bank, continue to take out of heat, facilitate the secondary side passive residual heat to discharge the condensation of vapours in heat interchanger 5 heat-transfer pipes; In addition, steam condensate (SC) case 6 also connects by relevant pipeline, water source as containment spray system 7 and non-active heap chamber waterflood system 8, under the disabled operating mode in material-changing water tank 4 water sources, water in the steam condensate (SC) case 6 enters containment spray system 7 as alternate source, under the pressurization of peace spray pump, in containment, spray, to realize the function of containment decrease temperature and pressure, in addition, because steam condensate (SC) case 6 positions are higher, under the major accident operating mode, can provide enough power pressure heads directly by segregation drive, inject enough cooling flows to the heap chamber by non-active heap chamber waterflood system 8.
Above-mentioned containment spray system 7, preferentially by material-changing water tank 4 water intakings, its trigger pip is consistent with existing pressurized-water reactor nuclear power plant with the safe action implementation, but under the disabled operating mode in material-changing water tank 4 water sources, can switch by pipeline, by 6 water intakings of steam condensate (SC) case, by the spray pump supercharging, to spraying in the containment, still can realize the security function of containment decrease temperature and pressure, the present invention contrasts existing design, and it is redundant to be equivalent to increase on choosing source a row safety, has improved security.
Above-mentioned non-active heap chamber waterflood system 8, under the major accident operating mode, by 6 water intakings of secondary side steam condensate (SC) case, utilize the gravity head of secondary side steam condensate (SC) case 6, chilled water is injected the heap chamber, flood the pressure vessel bottom, pressure container cylinder and low head are directly cooled off, prevent the reactor core fused mass fall fall behind in low head bottom and assemble after, concentrated because of generating heat, melt and wear end socket,, guarantee that the 3rd road physical barrier is to a large amount of radioactive containment roles to guarantee the delay of reactor core in pressure vessel.
Obviously, those skilled in the art can carry out various changes and modification to the present invention and not break away from the spirit and scope of the present invention.Like this, if of the present invention these are revised and modification belongs within the scope of claim of the present invention and equivalent technology thereof, then the present invention also is intended to comprise these changes and modification interior.
Claims (8)
- A nuclear power station non-actively with the engineered safety system that actively combines, it is characterized in that: comprise columns and the loop number non-active high pressure reactor core water supply tanks of corresponding some row (1), described non-active high pressure reactor core water supply tank (1) is higher than reactor core (10) setting, inject pipeline by safety and be communicated with, inject pipeline and be provided with the valve that triggers unlatching by a circuit pressure low signal with reactor-loop.
- 2. nuclear power station as claimed in claim 1 non-active and the engineered safety system that actively combines, it is characterized in that: described safety is injected pipeline one end and is connected bottom the non-active high pressure reactor core water supply tank (1), and the other end links to each other with pressure vessel (9) descending branch; The upper end of described non-active high pressure reactor core water supply tank (1) links to each other by a pressure-equalizing line and a loop main leg cold section (13).
- 3. nuclear power station as claimed in claim 1 or 2 non-actively with the engineered safety system that actively combines, it is characterized in that: also comprise the corresponding some row secondary side passive residual heats discharge heat exchangers (5) of columns and loop number, the heating surface bank that every row secondary side passive residual heat is discharged heat exchanger (5) is immersed in the corresponding steam condensate (SC) case (6), described heating surface bank upstream connects main steam line (11), and the downstream is communicated with steam generator (12) water-supply line.
- 4. nuclear power station as claimed in claim 3 non-actively with the engineered safety system that actively combines, it is characterized in that: described steam condensate (SC) case (6) is installed on the containment top layer.
- 5. nuclear power station as claimed in claim 4 non-actively with the engineered safety system that actively combines, it is characterized in that: also comprise containment spray system (7), described containment spray system (7) is connected with described steam condensate (SC) case (6) with material-changing water tank (4) with valve by pipeline respectively.
- 6. nuclear power station as claimed in claim 5 non-actively with the engineered safety system that actively combines, it is characterized in that: also comprise non-active heap chamber waterflood system (8), non-active heap chamber waterflood system (8) is made up of pipeline and valve, one end of its pipeline is communicated with steam condensate (SC) case (6), and the other end is communicated with the heap chamber.
- 7. nuclear power station as claimed in claim 1 or 2 non-active and the engineered safety system that actively combines is characterized in that: also comprise peace notes case (2) and low pressure safety injection pump (3) that existing nuclear power station is adopted.
- 8. nuclear power station as claimed in claim 7 non-actively with the engineered safety system that actively combines, it is characterized in that: described nuclear power station is a pressurized-water reactor nuclear power plant.
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| CN2011100377057A CN102169733B (en) | 2011-02-14 | 2011-02-14 | Passive and active combined special safety system for nuclear power plant |
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