CN102163469B - Nuclear power station non-active engineering safety system - Google Patents
Nuclear power station non-active engineering safety system Download PDFInfo
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- CN102163469B CN102163469B CN201110037783.7A CN201110037783A CN102163469B CN 102163469 B CN102163469 B CN 102163469B CN 201110037783 A CN201110037783 A CN 201110037783A CN 102163469 B CN102163469 B CN 102163469B
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
本发明属于核电站安全设备，具体涉及一种核电站非能动专设安全系统。该系统包括二次侧非能动余热排出热交换器、蒸汽冷凝水箱、非能动堆腔注水系统、非能动高压堆芯补水箱和相关的阀门与管道。在核电站发生设计基准事故或超设计基准事故时，通过有步骤的投入一系列的非能动与能动的安全设施，及时和迅速对反应堆一回路和堆芯进行有效冷却，使核电站顺利进入安全的冷停堆状态，抑制或缓解反应堆严重事故后果，降低事故危害，提高核电站的安全性。
The invention belongs to nuclear power plant safety equipment, in particular to a nuclear power plant passive dedicated safety system. The system includes secondary side passive waste heat removal heat exchanger, steam condensate tank, passive reactor cavity water injection system, passive high-pressure core make-up water tank and related valves and pipelines. When a design basis accident or beyond design basis accident occurs in a nuclear power plant, a series of passive and active safety facilities are put in step by step to effectively cool the primary circuit and core of the reactor in a timely and rapid manner, so that the nuclear power plant can enter a safe cold state smoothly. Shutdown state, suppress or mitigate the consequences of severe reactor accidents, reduce accident hazards, and improve the safety of nuclear power plants.
Description
Technical field
The invention belongs to nuclear plant safety equipment, be specifically related to a kind of nuclear power station non-active engineering safety system.
Background technology
Non-ly actively refer to that equipment or system only rely on the modes relevant to spontaneous phenomenon such as gravity, density, Natural Circulation and drive, and without introducing other propulsion system, can greatly reduce the equipment failure probability causing because of power machine fault, improve the reliability of security system.
Nuclear power plant containment shell is nuclear safety tetra-road physical barriers, under some accident conditions, the containment leak tightness that need to prevent the too high initiation of containment internal pressure can lose efficacy, conventionally the method adopting is to spray by pacifying in jet pipe alignment containment space at containment top, and the high-temperature vapor in containment or other gas are carried out to condensation or decrease temperature and pressure.The general employing in existing power station fetched water by material-changing water tank, 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 (San road physical barrier), and especially, under major accident operating mode, after core meltdown, pressure vessel is the visual plant that contains reactor core fused mass.Except the AP1000 of Westinghouse Electric, AP600 has designed outside the Reactor cavity flooding system of being fetched water by built-in material-changing water tank, and other heap types are not yet found to melt the report of the engineered safeguards features design proposal of wearing about prevention major accident operating mode downforce container at present.
Summary of the invention
The object of this invention is to provide a kind of nuclear power station non-active engineering safety system, effectively raise nuclear plant safety system reliability, strengthened the adaptibility to response of security system under nuclear power plant accident operating mode, can effectively prevent the gentle major accident of separating, the risk probability that reduces major accident and extensive radioactivity release, improves nuclear plant safety performance greatly.
Technical scheme of the present invention is as follows: a kind of nuclear power station non-active engineering safety system, comprise some row secondary side passive residual heat removal heat exchangers, on the loop of each reactor, correspondence arranges a row secondary side passive residual heat removal heat exchanger, the heating surface bank of every row secondary side passive residual heat removal heat exchanger is immersed in corresponding steam-condensation water tank, described heating surface bank upstream connects main steam line, and downstream is communicated with steam generator water-supply line.
Further, nuclear power station non-active engineering safety system as above, wherein, described steam-condensation water tank is installed on containment top layer, higher than steam generator position.
Further, nuclear power station non-active engineering safety system as above, wherein, described steam-condensation water tank is also connected with containment spray system with valve by pipeline, as the water source of containment spray system.
Further, nuclear power station non-active engineering safety system as above, wherein, described steam-condensation water tank is loop configuration.
Further, nuclear power station non-active engineering safety system as above, wherein, also comprises non-active Reactor cavity flooding system, and non-active Reactor cavity flooding system is comprised of pipeline and valve, and one end of its pipeline is communicated with steam-condensation water tank, and the other end is communicated with heap chamber.
Further, nuclear power station non-active engineering safety system as above, wherein, also comprise the non-active high pressure Core makeup tank of some row, on the loop of each reactor, correspondence arranges the non-active high pressure Core makeup tank of row, described non-active high pressure Core makeup tank, higher than reactor core setting, is communicated with reactor-loop by Safety Injection pipeline, and Safety Injection pipeline is provided with by a circuit pressure low signal and triggers the valve of opening.
Further, nuclear power station non-active engineering safety system as above, wherein, described Safety Injection pipeline one end connects non-active high pressure Core makeup tank bottom, and the other end is connected with pressure vessel descending branch; The upper end of described non-active high pressure Core makeup tank is connected with cold section of a loop main leg by pressure-equalizing line.
Beneficial effect of the present invention is as follows:
(1) application of secondary side passive residual heat removal heat exchanger in the present invention, guaranteed under accident conditions that secondary side steam and condensate water are contained within containment all the time, reduced the risk that under accidents such as heat-transfer pipe of evaporator fracture (SGTR), secondary side radioactivity is revealed;
(2) the present invention is directed to core meltdown phenomena under major accident, designed non-active Reactor cavity flooding system, utilize the cooling medium of continuous flooding pressure vessel bottom in heap chamber, pressure vessel is carried out to effective cooling, effectively prevent from and alleviated reactor core fused mass melting and wearing pressure vessel, thereby cause the damage sequence of a large amount of radioactivity releases;
(3) subsystem such as the high-pressure safety injection of the present invention to engineered safety system, auxiliary feedwater adopts non-active design proposal, and structure is simplified, and has reduced the quantity of active equipment, has reduced construction cost.
Accompanying drawing explanation
Fig. 1 is the non-active engineered safety system structural representation of the present invention.
In figure, 1. cold section of the non-active Reactor cavity flooding system 9. pressure vessel 10. reactor core 11. main steam line 12. steam generator 13. 1 loop main leg of non-active high pressure Core makeup tank 2. peace note case 3. low pressure safety injection pump 4. material-changing water tank 5. secondary side passive residual heat removal heat exchanger 6. steam-condensation water tank 7. containment spray system 8.
Embodiment
Below in conjunction with drawings and Examples, the present invention will be described in detail.
As shown in Figure 1, a kind of non-active engineered safety system that is directed to pressurized-water reactor nuclear power plant, comprise the non-active high pressure Core makeup tank 1 of the columns some row corresponding with loop number, described non-active high pressure Core makeup tank 1 arranges higher than reactor core 10, by Safety Injection pipeline, be communicated with reactor-loop, inject pipeline and be provided with the valve that is triggered unlatching by a circuit pressure low signal.In addition, described engineered safety system also comprises some row secondary side passive residual heat removal heat exchangers 5 that columns is corresponding with loop number, the heating surface bank of every row secondary side passive residual heat removal heat exchanger 5 is immersed in corresponding steam-condensation water tank 6, described heating surface bank upstream connects main steam line 11, and downstream is communicated with steam generator 12 water-supply lines.Further, described engineered safety system also comprises non-active Reactor cavity flooding system 8, and non-active Reactor cavity flooding system 8 is comprised of pipeline and valve, and one end of its pipeline is communicated with steam-condensation water tank 6, and the other end is communicated with heap chamber.On this basis, described engineered safety system also comprises the containment spray system 7 that existing nuclear power station possesses, and described containment spray system 7 is connected with described steam-condensation water tank 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, in two row systems, realize the corresponding device of identical function, its device structure, safe class and power system capacity are consistent, and the successful startup of the non-active high pressure Core makeup tank of arbitrary row all can meet the demand of the flow to high-pressure safety injection and capacity under design basis accident operating mode.Be different from the design of the AP1000 of Westinghouse Electric Core makeup tank, non-active high pressure Core makeup tank 1 in the present invention is triggered by a circuit pressure signal, the error safety injection of having avoided measuring system to occur voltage stabilizer false water level and to cause, in addition cancel level Four ADS fast pressure relief system, avoided the more artificial introducing of large break of next circuit pressure border of accident conditions.For simplified characterization, the characterization device that the present embodiment is only got in a row system is introduced.
Above-mentioned non-active high pressure Core makeup tank 1 is by Safety Injection pipeline and a circuit communication, long term maintenance high pressure conditions.Safety Injection pipeline one end connects the bottom of non-active high pressure Core makeup tank 1, and the other end is connected with pressure vessel 9 descending brancies; The upper end of described non-active high pressure Core makeup tank 1 is connected for cold section 13 with a loop main leg by pressure-equalizing line.Under accident conditions, be subject 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, produces pressure low signal, and the row of one in the electronic isolation valve of two-column parallel are opened.The gravity head that non-active high pressure Core makeup tank 1 can produce by difference in height, enters pressure vessel descending branch by cooling medium along Safety Injection pipeline, and the water level in compensation one loop declines, and the submergence and the waste heat that maintain reactor core are derived; If a loop is difficult to smooth release under accident conditions, non-active high pressure Core makeup tank 1 can utilize the connection effect of pressure-equalizing line, and total energy keeps certain drive ram, thereby has guaranteed the Safety Injection to a loop under high pressure operating mode.
Above-mentioned secondary side passive residual heat removal heat exchanger 5, heating surface bank is immersed in steam-condensation water tank 6, and heating surface bank upstream connects main steam line 11, and downstream leads to the water-supply line of steam generator 12.Under accident conditions, need to carry out while 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 transmitted to secondary side, make the feedwater boiling of secondary side become steam, because main steam line isolation valve under accident conditions cuts out, steam is subject to the effect of elevated pressures in steam generator, along pipeline, enter secondary side passive residual heat removal heat exchanger 5, the heat-transfer pipe of secondary side passive residual heat removal heat exchanger 5 is immersed in steam-condensation water tank 6, in pipe, be vapour, pipe is outer is water, steam-condensation, condensate water flows out the heat-transfer pipe of secondary side passive residual heat removal heat exchanger 5 under Action of Gravity Field, along pipeline, flow back to the feedwater piping of steam generator 12, reenter steam generator 12, maintain the water level in steam generator 12, secondary side passive residual heat removal heat exchanger 5 Pattern completion circulation according to this, realize the refrigerating function of secondary side to a loop, make a smooth decrease temperature and pressure in loop, and then in reaching, the condition that low pressure peace note drops into, thereby finally make nuclear power station enter the safe condition of cold shut.
Above-mentioned steam-condensation water tank 6, be installed on containment top layer, arrange ringwise, submergence under water has the heating surface bank of secondary side passive residual heat removal heat exchanger 5, when secondary side passive residual heat removal heat exchanger 5 is when carrying out its security function, the interior a large amount of water of steam-condensation water tank 6 can provide hot trap, make steam-condensation in heat-transfer pipe, realize the Natural Circulation of secondary side passive residual heat removal heat interchanger 5, in steam-condensation water tank 6, after near water heat-transfer pipe is heated, density reduces, upwards flowed by buoyancy, after arriving at the water surface, by natural convection with the temperature of mixing of periphery cold water, reduce density increase, gravitate sinks under the water again, go round and begin again, near heating surface bank, form lasting Natural Circulation, continue to take out of heat, facilitate the condensation of vapours in secondary side passive residual heat removal heat interchanger 5 heat-transfer pipes, in addition, steam-condensation water tank 6 also connects by relevant pipeline, as the water source of containment spray system 7 and non-active Reactor cavity flooding system 8, under the material-changing water tank 4 disabled operating modes in water source, water in steam-condensation water tank 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-condensation water tank 6 positions are higher, under major accident operating mode, can be directly by segregation drive, enough power pressure heads are provided, by non-active Reactor cavity flooding system 8, to heap chamber, inject enough cooling flows.
Above-mentioned containment spray system 7, preferentially by material-changing water tank 4, fetched water, its trigger pip is consistent with existing pressurized-water reactor nuclear power plant with safe action implementation, but under the material-changing water tank 4 disabled operating modes in water source, can pass through plugging, by steam-condensation water tank 6, fetched water, by spray pump supercharging, to spraying in containment, still can realize the security function of containment decrease temperature and pressure, the present invention contrasts existing design, is equivalent to increase a row Safety Redundancy in choosing source, has improved security.
Above-mentioned non-active Reactor cavity flooding system 8, under major accident operating mode, by secondary side steam-condensation water tank 6, fetched water, utilize the gravity head of secondary side steam-condensation water tank 6, chilled water is injected to heap chamber, flood pressure vessel bottom, directly cooling to pressure container cylinder and low head, after preventing that reactor core fused mass from falling and fall behind in low head bottom and assemble, concentrated because generating heat, melt and wear end socket, to guarantee the delay of reactor core in pressure vessel, guarantee that San road physical barrier is to a large amount of radioactive containment roles.
Obviously, those skilled in the art can carry out various changes and modification and not depart from the spirit and scope of the present invention the present invention.Like this, if within of the present invention these are revised and modification belongs to the scope of the claims in the present invention and equivalent technology thereof, the present invention is also intended to comprise these changes and modification interior.
Claims (4)
1. a nuclear power station non-active engineering safety system, it is characterized in that: comprise some row secondary side passive residual heat removal heat exchangers (5), on the loop of each reactor, correspondence arranges a row secondary side passive residual heat removal heat exchanger (5), the heating surface bank of every row secondary side passive residual heat removal heat exchanger (5) is immersed in corresponding steam-condensation water tank (6), described heating surface bank upstream connects main steam line (11), and downstream is communicated with steam generator (12) water-supply line; Described steam-condensation water tank (6) is installed on containment top layer, higher than steam generator (12) position; Steam-condensation water tank (6) is also connected with containment spray system (7) with valve by pipeline, as the water source of containment spray system (7); Also comprise non-active Reactor cavity flooding system (8), non-active Reactor cavity flooding system (8) is comprised of pipeline and valve, and one end of its pipeline is communicated with steam-condensation water tank (6), and the other end is communicated with heap chamber.
2. nuclear power station non-active engineering safety system as claimed in claim 1, is characterized in that: described steam-condensation water tank (6) is loop configuration.
3. nuclear power station non-active engineering safety system as claimed in claim 1, it is characterized in that: also comprise the non-active high pressure Core makeup tanks of some row (1), on the loop of each reactor, correspondence arranges the non-active high pressure Core makeup tanks of row (1), described non-active high pressure Core makeup tank (1) arranges higher than reactor core (10), by Safety Injection pipeline, be communicated with reactor-loop, Safety Injection pipeline is provided with by a circuit pressure low signal and triggers the valve of opening.
4. nuclear power station non-active engineering safety system as claimed in claim 3, is characterized in that: described Safety Injection pipeline one end connects non-active high pressure Core makeup tank (1) bottom, and the other end is connected with pressure vessel (9) descending branch; The upper end of described non-active high pressure Core makeup tank (1) is connected by pressure-equalizing line and a loop main leg cold section (13).
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| CN201110037783.7A CN102163469B (en) | 2011-02-14 | 2011-02-14 | Nuclear power station non-active engineering safety system |
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| CN201110037783.7A CN102163469B (en) | 2011-02-14 | 2011-02-14 | Nuclear power station non-active engineering safety system |
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| CN102163469B true CN102163469B (en) | 2014-04-30 |
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Cited By (1)
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| US9423407B2 (en) * | 2011-09-30 | 2016-08-23 | Westinghouse Electric Company Llc | Automated analysis coverage verification (AACV) |
| FR2985842B1 (en) * | 2012-01-18 | 2014-02-21 | Technicatome | SYSTEM FOR EVACUATING THE RESIDUAL POWER OF A PRESSURIZED WATER NUCLEAR REACTOR |
| CN102568622B (en) * | 2012-01-18 | 2015-09-09 | 中科华核电技术研究院有限公司 | For the non-active cooling system of spent nuclear fuel in nuclear power plant cooling |
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| CN102867549B (en) * | 2012-09-27 | 2017-05-10 | 中国核电工程有限公司 | Reactor cavity water injection cooling system with combination of active and passive power |
| KR20140047452A (en) * | 2012-10-12 | 2014-04-22 | 한국수력원자력 주식회사 | Coolant replenishment apparatus for passive auxiliary feedwater system of nuclear power plant |
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| CN105788675A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Long-time containment cooling system of nuclear power station |
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| CN209232422U (en) * | 2018-11-14 | 2019-08-09 | 中广核研究院有限公司 | The coolant of reactor and reactor emergency injected system |
| CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
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