CN202887746U - Active and passive combined reactor core surplus heat discharging system for nuclear power station - Google Patents
Active and passive combined reactor core surplus heat discharging system for nuclear power station Download PDFInfo
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- CN202887746U CN202887746U CN2012205034477U CN201220503447U CN202887746U CN 202887746 U CN202887746 U CN 202887746U CN 2012205034477 U CN2012205034477 U CN 2012205034477U CN 201220503447 U CN201220503447 U CN 201220503447U CN 202887746 U CN202887746 U CN 202887746U
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Abstract
The utility model relates to an active and passive combined reactor core surplus heat discharging system for a nuclear power station, comprising a safety injection system, a containment spray system, an assistant water feed system, a reactor cavity water injection system, a secondary side passive surplus heat discharging system, a passive containment heat output system and associated valves and pipelines. When an accident happens, the system can achieve three safety functions of controlling reactivity, discharging reactor core heat and containing radial materials by using an active and passive combined multi-redundancy and multifarious manner. The system can not only completely achieve the safety injection and safety spray under the working condition of an accident of the nuclear power station and achieve the safety functions of reactor cavity water injection and the like under the working condition of a serious accident, but also effectively improves the reliability of the safety system and strengthens the coping capacity of the safety system under the working condition of accidents of the nuclear power station, and can effectively prevent and relieve serious accidents and reduce the reactor core fusing probability and the risk probability of large-scale radial release, thus the safety property of the nuclear power station is greatly improved.
Description
Technical field
The utility model belongs to nuclear plant safety equipment, is specifically related to the active reactor core surplus heat with non-active combination of a kind of nuclear power station and discharges system.
Background technology
In the reactor operation process of nuclear power station, if nuclear reaction is ended, nuclear fuel can continue to produce waste heat, still needs the water circulation of power supply or other power maintenance one loop and secondary circuit, and the waste heat of reactor core is derived, and prevents the overheated meltdown of reactor core.This is an important goal that guarantees that nuclear safety will realize.Another important goal of nuclear safety is to contain radiomaterial, and nuclear power station is provided with three road barriers for this reason: can, pressure vessel and containment.Only need to guarantee the intact of any one barrier, just can prevent that radiomaterial from leaking in the environment.No matter under which kind of emergency conditions, only need after the reactor shutdown, realize this two targets, just complete protection of the environment and the public's safety.
For realizing Security Target, nuclear power station is provided with the reactor core surplus heat and discharges system, and implementation has two kinds: the enabling fashion of traditional M310 heap type, and western room AP1000 is the non-enabling fashion of representative.Non-ly refer to 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 greatly reduce the equipment failure probability that causes because of the power machine fault, improved the reliability of security system, active equipment then has the advantages such as power is strong, pressure is high, flow is large, compact conformation.
The reactor of pressurized-water reactor nuclear power plant is under accident conditions, for reactor core is carried out effective cooling, current technical method is to inject the lower boron water (Safety Injection) of large amount temperature in a circuit system now, namely adopt the enabling fashion of safety injection pump to a loop water filling, the AP1000 of US Westinghouse company then realizes this goal by the higher built-in material-changing water tank of non-active high pressure Core makeup tank and position.
Reactor pressure vessel is the important component part of presurized water reactor pressure boundary, 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.Except Westinghouse Electric had designed the Reactor cavity flooding system that is fetched water by built-in material-changing water tank, other heap types were not yet found to melt the report of the design proposal of wearing about prevention major accident operating mode downforce container at present.But the design attitude of the built-in material-changing water tank of AP1000 heap type of Westinghouse Electric is higher, can't directly compile the water source that brings from container spray, pipeline cut, and therefore, system is comparatively complicated.
Nuclear power plant containment shell is last one physical barrier of nuclear safety, under some accident conditions, the containment leak tightness that need to 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.But because conventional design places material-changing water tank outside the containment, in the situation that has an accident, the peace of external material-changing water tank is annotated and spray system need to carry out blocked operation under liquid level gauge cooperates, and has increased the potential risk of system running pattern switching failure.
Chinese patent application 201110037705.7 disclose a kind of nuclear power station non-actively with the engineered safety system that actively combines, this system secondary side passive residual heat removal heat exchanger, be used for deriving the reactor core heat by the reactor secondary side under the accident conditions, the heating surface bank of secondary side passive residual heat removal heat exchanger is immersed in the corresponding steam-condensation water tank, and the steam-condensation water tank is arranged on the inside of containment.Because the position that the steam-condensation water tank arranges, cause its heat still not discharge containment and since after the accident in the containment temperature and pressure very high (145 ℃, 0.52MPa), therefore, this steam-condensation water tank is arranged on the formation that scheme in the containment is unfavorable for the Natural Circulation heat-exchanging loop.
The utility model content
The purpose of this utility model is for the adaptibility to response of strengthening security system under the nuclear power plant accident operating mode and reliability, overcome simultaneously the design defect that exists in the prior art, provide a kind of reactor core surplus heat that can greatly improve the active and non-active combination of nuclear plant safety performance to discharge system.
The technical solution of the utility model is as follows: the active reactor core surplus heat with non-active combination of a kind of nuclear power station is discharged system, comprise safety injection system, containment spray system, auxiliary feedwater system, the Reactor cavity flooding system, Passive residual heat removal system, passive containment thermal conduction system, wherein, described safety injection system comprises the material-changing water tank that is arranged on melt pit position, containment inner reactor core below, described material-changing water tank bottom is connected with hot arc with cold section of reactor-loop respectively behind safety injection pump by pipeline, reactor top is provided with Passive SIT, and described peace is annotated case and is connected by with reactor-loop cold section of pipeline.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, wherein, pipeline one end of described containment spray system connects described material-changing water tank bottom, and the other end is connected to the circular spray tube at containment top behind containment spray pump and heat interchanger.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, wherein, the pipeline upstream of described Passive residual heat removal system connects the main steam line of steam generator, behind heat exchanger, the downstream is connected with the main feed water pipe road of steam generator, and described heat exchanger places in the heat-exchanging water tank of containment outside.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, wherein, described passive containment thermal conduction system comprises heat interchanger or the heat exchanger package that is arranged on containment inside, described heat interchanger or heat exchanger package are connected with the heat-exchanging water tank that is arranged on the containment outside by pipeline, and the height of heat-exchanging water tank is higher than the height of heat interchanger or heat exchanger package.Passive containment thermal conduction system and Passive residual heat removal system share same heat-exchanging water tank.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, wherein, be provided with steam-water separator in the heat-exchanging water tank of containment outside, the heat interchanger of described passive containment thermal conduction system or the tedge of heat exchanger package are connected with steam-water separator.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, wherein, described auxiliary feedwater system comprises the auxiliary feed-water tank that is arranged on outside the containment, auxiliary feed-water tank is connected with the main feed water pipe road of steam generator by pipeline, is arranged in parallel pneumatic pump and electrodynamic pump at pipeline.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, wherein, is arranged in parallel two pneumatic pumps and two electrodynamic pumps on the pipeline of described auxiliary feedwater system.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, wherein, described Reactor cavity flooding system comprises active injection pipeline and the non-active injection pipeline that is communicated with the heap chamber, described active injection pipeline is connected with fire extinguisher canvas hose with described material-changing water tank respectively, and described non-active injection pipeline is connected with the non-active Reactor cavity flooding case that is arranged at the reactor top.
Further, the active reactor core surplus heat with non-active combination of aforesaid nuclear power station is discharged system, and wherein, the safety injection pump on the described safety injection system pipeline is pressed safety injection pump in adopting, and the injection pressure head scope of middle pressure safety injection pump is 600mWC ~ 1100mWC.
The beneficial effects of the utility model are as follows:
(1) the utility model 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 generation major accident, has improved the security performance of nuclear power station;
(2) the utility model places the inner lowest part of containment with material-changing water tank, conveniently compile the water source that brings from container spray, pipeline cut, after compiling in the lump, supply with cooling water via pump to safety injection system, spray system, Reactor cavity flooding system, built-in material-changing water tank is originated as the water source of active security system uniformly, and combine with the melt pit of reactor, played the effect of simplified apparatus;
(3) application of secondary side passive residual heat removal heat exchanger in the utility model, the means of reactor core have been guaranteed to derive by secondary side under the accident conditions, increase the diversity that derives the reactor core heat, reduced the risk that the secondary side radioactivity is revealed under the accidents such as heat-transfer pipe of evaporator fracture (SGTR); Heat-exchanging water tank is positioned at outside the containment, will directly exchange to heat outside the containment, has strengthened the Natural Circulation exchange capability of heat;
(4) design of passive containment thermal conduction system in the utility model has guaranteed the long-term heat extraction of containment in the beyond design basis accident situation, has improved traditional active security system nuclear power plant to the dependence of safe level power supply, has improved inherent safety; Passive containment thermal conduction system and Passive residual heat removal system share heat-exchanging water tank, have simplified equipment;
(5) the utility model is for core meltdown phenomena under the major accident, designed non-active Reactor cavity flooding system, utilize the cooling medium of continuous flooding pressure vessel bottom in the heap chamber, by pressure vessel reactor core is carried out effective cooling, preventing effectively that the reactor core fused mass from melting wears pressure vessel, thereby causes the damage sequence of a large amount of radioactivity releases;
(6) safety injection system of the present utility model arranges special-purpose middle pressure safety injection pump, carry out function singleness, can improve the reliability of system, safety injection pump has reduced (becoming pressure by high pressure) behind the injection pressure head, error starting accident in the time of can effectively preventing high-pressure safety injection, avoid a circuit pressure too high, also can alleviate or avoid the too high and steam generator spill-over that may cause of next circuit pressure of steam generator tube rupture accident, thereby reduce under this accident radiomaterial to the possibility of environmental emission.
Description of drawings
Fig. 1 is system architecture synoptic diagram of the present utility model.
Among the figure, 1. reactor core 2. material-changing water tanks 3. containment spray pumps 4. heat interchanger 5. safety injection pumps 6. fire extinguisher canvas hoses 7. safety injection pumps 8. heat-exchanging water tanks 9. heat interchanger 10. steam-water separators 11. circular spray tubes 12. containments 13. heat exchangers 14. steam generators 15. main steam lines 16. main feed water pipe roads 17. auxiliary feed-water tanks, 18. pneumatic pumps, 19. electrodynamic pumps, 20. peaces are annotated case 21. non-active Reactor cavity flooding casees
Embodiment
The active reactor core surplus heat with non-active combination of nuclear power station provided by the utility model is discharged system; comprise safety injection system, containment spray system, auxiliary feedwater system, Reactor cavity flooding system, Passive residual heat removal system, passive containment thermal conduction system and relevant valve and pipeline; when occuring, accident realizes three large security functions of control reactivity, discharge reactor core heat, containing radiomaterial, protection of the environment and the public's safety.Above-mentioned each system all by mentioning and using in various degree, still, also exists some defectives and deficiency in the prior art in the design of existing nuclear power station.The utility model is by the reasonably optimization of improvement and system, overcome in the prior art existing defective of above-mentioned each system, simultaneously, with active and the non-many redundancies that actively combine and multifarious mode, make the design of nuclear power station reactor core surplus heat discharge system more safe and effective.
Safety injection system of the present utility model comprises the material-changing water tank that is arranged on containment inside, described material-changing water tank bottom is connected with hot arc with cold section of reactor-loop respectively behind safety injection pump by pipeline, the reactor top is provided with Passive SIT, described peace is annotated case and is connected by with reactor-loop cold section of pipeline, non-active peace is annotated case automatic opens check valve when a circuit system pressure is low, and water is injected reactor core.Because material-changing water tank is positioned at containment, has reduced outside disaster to the impact of material-changing water tank security, improved the reliability at emergent water source after the accident, improved npp safety.In the situation that nuclear power station has an accident, if adopt external material-changing water tank, peace is annotated and spray system need to carry out blocked operation under liquid level gauge cooperates, and postpone does not need to pacify the switching in notes, peace water spray source in the material-changing water tank.Because built-in material-changing water tank will be annotated as the unique active peace after the accident, peace spray source, contingent mistake has been avoided in operation after can the minimizing accident, has reduced the potential risk of system running pattern switching failure, thereby improved the reliability of system, strengthened the security of power plant.
Simultaneously, the utility model is arranged on melt pit position, reactor core below with material-changing water tank, and material-changing water tank is positioned at lowest part, conveniently compiles the water source that brings from container spray, pipeline cut, after compiling in the lump, supply with cooling water via pump to safety injection system, spray system, Reactor cavity flooding system.Built-in material-changing water tank is uniformly as the source, water source of active security system, and combines with the melt pit of original M310 heap type, played the effect of simplified apparatus.
Pipeline one end of containment spray system of the present utility model connects described material-changing water tank bottom, and the other end is connected to the circular spray tube at containment top behind containment spray pump and heat interchanger.Built-in material-changing water tank is directly originated as the water supply of the unique active containment spray system after the accident.
The pipeline upstream of Passive residual heat removal system of the present utility model connects the main steam line of steam generator, behind heat exchanger, the downstream is connected with the main feed water pipe road of steam generator, and described heat exchanger places in the heat-exchanging water tank of containment outside.Because heat-exchanging water tank is positioned at the containment outside, will directly exchange to heat outside the containment.Behind nuclear power plant accident in the safety temperature, pressure very high (145 ℃ 0.52MPa), with the Natural Circulation heat-exchanging loop of the outer heat-exchanging water tank formation of containment, have guaranteed the integrality of containment.
In addition, Passive residual heat removal system of the present utility model and passive containment thermal conduction system share same heat-exchanging water tank.Passive containment thermal conduction system comprises heat interchanger or the heat exchanger package that is arranged on containment inside, and described heat interchanger or heat exchanger package are connected with the heat-exchanging water tank that is arranged on the containment outside by pipeline.Can also be provided with steam-water separator in the heat-exchanging water tank, the heat interchanger of described passive containment thermal conduction system or the tedge of heat exchanger package are connected with steam-water separator.Because above-mentioned two systems share same heat-exchanging water tank, under the prerequisite that guarantees security, simplified system equipment, improved the economy of nuclear power station design.
Auxiliary feedwater system of the present utility model comprises the auxiliary feed-water tank that is arranged on outside the containment, and auxiliary feed-water tank is connected with the main feed water pipe road of steam generator by pipeline, is arranged in parallel pneumatic pump and electrodynamic pump at pipeline.Under accident conditions, when main water work can not be worked, auxiliary feedwater system supplied water to steam generator, and to derive the waste heat in the reactor, the steam of generation enters atmosphere.In nuclear power station design in the past (such as Daya Bay nuclear power plant), usually adopt the form of 2 50% electrodynamic pump+1,100% pneumatic pump, according to single failure criteria, if 1 pneumatic pump maintenance, 1 electrodynamic pump fault will cause cooling power not enough.And the utility model has been taked the allocation plan of 2 50% electrodynamic pump+2,50% pneumatic pumps, and 4 pumps are relation in parallel and arrange, thereby has improved the reliability of auxiliary feedwater, and can satisfy single failure criteria.
Reactor cavity flooding of the present utility model system comprises active injection pipeline and the non-active injection pipeline that is communicated with the heap chamber, described active injection pipeline is connected with fire extinguisher canvas hose with described material-changing water tank respectively, and described non-active injection pipeline is connected with the non-active Reactor cavity flooding case that is arranged at the reactor top.After reactor core damage accident occured, the heap chamber by built-in material-changing water tank or fire water water intaking, was actively injected first by the Reactor cavity flooding system, realizes continuing cooling.When active part is unavailable because station blackout or emergency diesel-oil machine lost efficacy, then rely on gravity the water in the non-active Reactor cavity flooding case to be injected the heap chamber, the injection of realization chilled water.This system can prevent reactor core fused mass burn through pressure vessel, guarantees that the second physical barrier is to a large amount of radioactive containment roles.
Below in conjunction with accompanying drawing and specific embodiment the utility model is described in further detail.
Embodiment
As shown in Figure 1, the active reactor core surplus heat with non-active combination of complete nuclear power station is discharged system, comprises safety injection system, containment spray system, auxiliary feedwater system, Reactor cavity flooding system, Passive residual heat removal system, passive containment thermal conduction system.Wherein, described safety injection system comprises the material-changing water tank 2 that is arranged on melt pit position, inner reactor core 1 below of containment, described material-changing water tank 2 bottoms are connected with cold section of reactor-loop behind safety injection pump 5 by pipeline, simultaneously, can also be by the pipeline (not shown) that behind safety injection pump, is connected with the hot arc of reactor-loop; Reactor top is provided with Passive SIT 20, and described peace is annotated case 20 and is connected by with reactor-loop cold section of pipeline.By material-changing water tank to incipient stage of reactor-loop water filling be cold section injection, until after the long-term cooling, just begin cold and hot section simultaneously injection.
Originally M310 heap type on fill pump and double as simultaneously high-pressure safety injection pump, present embodiment with on fill with the peace pouring functions and separate, cancel high-pressure safety injection pump, set up middle pressure safety injection pump.When former M310 heap type occurred at peace notes signal, pump switched to the peace injection-molded from upper mold filling formula, and this handoff procedure need operate a large amount of valves, will have influence on the reliability of system.Present embodiment arranges after the special-purpose middle pressure safety injection pump, carries out function singleness, can improve the reliability of system.Safety injection pump has reduced injection pressure head (becoming pressure by high pressure), different according to flow, be 600mWC ~ 1100mWC with reference to the pressure head scope, error starting accident in the time of can effectively preventing high-pressure safety injection, avoid a circuit pressure too high, also can alleviate or avoid the too high and steam generator spill-over that may cause of next circuit pressure of steam generator tube rupture accident, thereby reduce under this accident radiomaterial to the possibility of environmental emission.
On peace notes mode, what traditional core power station (such as Daya Bay nuclear power plant) adopted is the direct injection system of pressure vessel; What the utility model then adopted is the cold leg injection system, and takes cold and hot section simultaneously injection mode after entering long-term cooling stage.Daya Bay nuclear power plant has adopted 2 peaces to annotate case, all is that the direct pressure container injects; Be provided with 3 peaces in the present embodiment and annotate case, cold section injection.Secondly, cancelled the dense boron injection tank of high-pressure safety injection after, the indemnifying measure that Daya Bay nuclear power plant adopts is the boron concentration that improves in the material-changing water tank, the utility model then is to be provided with in addition special-purpose dense boron injected system.
Pipeline one end of containment spray system connects described material-changing water tank 2 bottoms, and the other end is connected to the circular spray tube 11 at containment top behind containment spray pump 3 and heat interchanger 4.Safety injection pump, full shell spray pump are to have the ripe equipment of using of power plant now, move by starting under the trigger pip of being correlated with, and jet pipe line all water intaking and realization Safety Injection and spray function from built-in material-changing water tank are annotated, pacified to peace.
The pipeline upstream of Passive residual heat removal system connects the main steam line 15 of steam generator 14, behind heat exchanger 13, the downstream is connected with the main feed water pipe road 16 of steam generator 14, and described heat exchanger 13 places in the heat-exchanging water tank 8 of containment outside.Passive containment thermal conduction system comprises heat interchanger 9 or the heat exchanger package that is arranged on containment 12 inside, and described heat interchanger 9 or heat exchanger package are connected with the heat-exchanging water tank 8 that is arranged on containment 12 outsides with the decline pipeline by the rising pipeline.Passive containment thermal conduction system and Passive residual heat removal system share same heat-exchanging water tank 8, have simplified system equipment, and the height of heat-exchanging water tank is higher than the height of heat interchanger or heat exchanger package, thereby form Natural Circulation.In addition, can also be provided with steam-water separator 10 in that the heat-exchanging water tank 8 of containment outside is interior, the heat interchanger 9 of described passive containment thermal conduction system or the rising pipeline of heat exchanger package are connected with steam-water separator 10.
Under 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 subject to the effect of elevated pressures in the steam generator, enter the Passive residual heat removal system heat exchanger along pipeline, be immersed in the heat exchanger tube of the heat exchanger in the heat-exchanging water tank and be vapour, pipe is outer to be water, steam-condensation, condensate water flows out heat exchanger tube under Action of Gravity Field, flow back to the main feed water pipe road of steam generator along pipeline, reenter steam generator, keep the water level in the steam generator.Thus Pattern completion circulation realizes that secondary side to the refrigerating function in a loop, makes the smooth decrease temperature and pressure in a loop, thereby finally makes nuclear power station enter the safe condition of cold shut.
The passive containment thermal conduction system utilization is built in heat interchanger or the heat exchanger package in the containment, by the convection current of water vapour between the condensation on the heat interchanger, mixed gas and heat interchanger and the cooling of radiation heat transfer realization containment, by flowing of water in the Tube Sheet of Heat Exchanger, continuously the heat in the containment is taken to outside the containment, share same heat-exchanging water tank with Passive residual heat removal system outside containment, the density difference that utilizes the temperature difference of water to cause realizes that non-passive safety shell heat discharges.
Auxiliary feedwater system comprises the auxiliary feed-water tank 17 that is arranged on outside the containment 12, and auxiliary feed-water tank 17 is connected with the main feed water pipe road 16 of steam generator 14 by pipeline, is arranged in parallel pneumatic pump 18 and electrodynamic pump 19 at pipeline.Present embodiment has been taked the allocation plan of two 50% electrodynamic pump+two, 50% pneumatic pumps, thereby has improved the reliability of auxiliary feedwater, and can satisfy single failure criteria.
The Reactor cavity flooding system comprises active injection pipeline and the non-active injection pipeline that is communicated with the heap chamber, described active injection pipeline is connected with fire extinguisher canvas hose with described material-changing water tank 2 respectively and is connected, described non-active injection pipeline is connected with the non-active Reactor cavity flooding case 21 that is arranged at reactor top, is provided with the direct current drive valve of two parallel connections and two reverse checkvalves on the non-active injection pipeline as isolated part.After reactor core damage accident occured, chilled water actively injected the heap chamber first by built-in material-changing water tank 2 or fire extinguisher canvas hose 6 water intakings by injection pump in the Reactor cavity flooding system, realizes continuing cooling.When active part is unavailable because station blackout or emergency diesel-oil machine lost efficacy, then rely on gravity the water in the non-active Reactor cavity flooding case 21 to be injected the heap chamber, the injection of realization chilled water.This system can prevent reactor core fused mass burn through pressure vessel, guarantees that the second physical barrier is to a large amount of radioactive containment roles.
The reactor core surplus heat that present embodiment provides is discharged the global design scheme of system, Safety Injection under the realization nuclear power plant emergency conditions that not only can be complete, the security functions such as Reactor cavity flooding 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 improved 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 reactor core melts probability and extensive radioactivity release, greatly improve the nuclear plant safety performance.
Obviously, those skilled in the art can carry out various changes and modification to the utility model and not break away from spirit and scope of the present utility model.Like this, if of the present utility model these are revised and modification belongs within the scope of the utility model claim and equivalent technology thereof, then the utility model also is intended to comprise these changes and modification interior.
Claims (10)
1. the active reactor core surplus heat with non-active combination of nuclear power station is discharged system, comprise safety injection system, containment spray system, auxiliary feedwater system, Reactor cavity flooding system, Passive residual heat removal system, passive containment thermal conduction system, it is characterized in that: described safety injection system comprises the material-changing water tank (2) that is arranged on melt pit position, the inner reactor core of containment (1) below, and described material-changing water tank (2) bottom is connected with hot arc with cold section of reactor-loop respectively behind safety injection pump by pipeline; Reactor top is provided with Passive SIT (20), and described peace is annotated casees (20) and is connected by with reactor-loop cold section of pipeline.
2. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 1 is discharged system, it is characterized in that: pipeline one end of described containment spray system connects described material-changing water tank (2) bottom, and the other end is connected to the circular spray tube (11) at containment top behind containment spray pump (3) and heat interchanger (4).
3. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 1 or 2 is discharged system, it is characterized in that: the pipeline upstream of described Passive residual heat removal system connects the main steam line (15) of steam generator (14), behind heat exchanger (13), the downstream is connected with the main feed water pipe road (16) of steam generator (14), and described heat exchanger (13) places in the heat-exchanging water tank (8) of containment outside.
4. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 3 is discharged system, it is characterized in that: described passive containment thermal conduction system comprises heat interchanger (9) or the heat exchanger package that is arranged on containment (12) inside, described heat interchanger (9) or heat exchanger package are connected by the pipeline heat-exchanging water tank (8) outside with being arranged on containment (12), and the height of heat-exchanging water tank is higher than the height of heat interchanger or heat exchanger package.
5. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 4 is discharged system, and it is characterized in that: described passive containment thermal conduction system and Passive residual heat removal system share same heat-exchanging water tank (8).
6. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 5 is discharged system, it is characterized in that: be provided with steam-water separator (10) in the heat-exchanging water tank (8) of containment outside, the tedge of the heat interchanger of described passive containment thermal conduction system (9) or heat exchanger package is connected with steam-water separator (10).
7. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 1 or 2 is discharged system, it is characterized in that: described auxiliary feedwater system comprises the auxiliary feed-water tank (17) that is arranged on outside the containment (12), auxiliary feed-water tank (17) is connected with the main feed water pipe road (16) of steam generator (14) by pipeline, is arranged in parallel pneumatic pump (18) and electrodynamic pump (19) at pipeline.
8. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 7 is discharged system, it is characterized in that: be arranged in parallel two pneumatic pumps and two electrodynamic pumps on the pipeline of described auxiliary feedwater system.
9. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 1 or 2 is discharged system, it is characterized in that: described Reactor cavity flooding system comprises active injection pipeline and the non-active injection pipeline that is communicated with the heap chamber, described active injection pipeline is connected 6 with described material-changing water tank (2) with fire extinguisher canvas hose respectively) be connected, described non-active injection pipeline is connected with the non-active Reactor cavity flooding case (21) that is arranged at the reactor top.
10. the active reactor core surplus heat with non-active combination of nuclear power station as claimed in claim 1 is discharged system, it is characterized in that: the safety injection pump on the described safety injection system pipeline is pressed safety injection pump in adopting, and the injection pressure head scope of middle pressure safety injection pump is 600mWC ~ 1100mWC.
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| CN2012205034477U CN202887746U (en) | 2012-08-20 | 2012-09-27 | Active and passive combined reactor core surplus heat discharging system for nuclear power station |
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| CN201210297128 | 2012-08-20 | ||
| CN201210297128.X | 2012-08-20 | ||
| CN2012205034477U CN202887746U (en) | 2012-08-20 | 2012-09-27 | Active and passive combined reactor core surplus heat discharging system for nuclear power station |
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| CN201210374533.7A Active CN102903404B (en) | 2012-08-20 | 2012-09-27 | The reactor core surplus heat of the active and non-active combination of a kind of nuclear power station discharges system |
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| CN201689688U (en) * | 2010-06-04 | 2010-12-29 | 中科华核电技术研究院有限公司 | System for cooling reactor core, filling water in reactor cavity and guiding out heat of containment |
| CN102163469B (en) * | 2011-02-14 | 2014-04-30 | 中国核电工程有限公司 | Nuclear power station non-active engineering safety system |
| CN102169733B (en) * | 2011-02-14 | 2013-10-23 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| CN202887746U (en) * | 2012-08-20 | 2013-04-17 | 中国核电工程有限公司 | Active and passive combined reactor core surplus heat discharging system for nuclear power station |
-
2012
- 2012-09-27 CN CN2012205034477U patent/CN202887746U/en not_active Expired - Fee Related
- 2012-09-27 CN CN201210374533.7A patent/CN102903404B/en active Active
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
| CN102903404B (en) * | 2012-08-20 | 2015-08-19 | 中国核电工程有限公司 | The reactor core surplus heat of the active and non-active combination of a kind of nuclear power station discharges system |
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| CN102903404B (en) | 2015-08-19 |
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