CN201741419U - Main water supply flow control system of nuclear power plant - Google Patents
Main water supply flow control system of nuclear power plant Download PDFInfo
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- CN201741419U CN201741419U CN2010202685316U CN201020268531U CN201741419U CN 201741419 U CN201741419 U CN 201741419U CN 2010202685316 U CN2010202685316 U CN 2010202685316U CN 201020268531 U CN201020268531 U CN 201020268531U CN 201741419 U CN201741419 U CN 201741419U
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- nuclear power
- containment
- valve
- flow control
- control system
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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
Abstract
The utility model relates to a main water supply flow control system of a nuclear power plant, comprising a steam generator which is arranged in a reactor and a main water supply system which is arranged outside the reactor; the main water supply system and the steam generator are connected through a steam pipeline which passes through a reactor containment and is provided with a valve; a check valve is arranged at a position on the steam pipeline which is arranged in the containment and is close to the same; and wherein, an isolation valve is arranged at a position on the steam pipeline which is arranged outside the containment and is close to the same. The isolation valve is arranged outside the containment of the main water supply flow control system of the nuclear power plant and starts to act after receiving a safety-level control signal from a main control room, thereby effectively cut main water supply from two directions, ensuring to effectively isolate main water supply under the working conditions of accidents, preventing the steam generator from overflowing, reducing the overvoltage risk of the containment, and improving the safety of the nuclear power plant.
Description
Technical field
The utility model relates to the nuclear power technology field, more specifically, relates in particular to a kind of nuclear power factory owner feedwater flow control system.
Background technology
Nuclear power factory owner feedwater flow control system principle as shown in Figure 1 at present, this system comprises steam generator (the Steam Generator that is positioned at reactor inside, SG), auxiliary feedwater system (Auxiliary Feed-water System, AFS), and the main feed system that is positioned at the reactor outside.Wherein, steam generator in the reactor propulsion system that adopt indirect cyclic process reactor coolant from the heat energy that reactor core obtains, pass to secondary circuit working medium, make heat energy become the heat-exchange apparatus of steam.Be connected by the jet chimney that passes containment vessel and be provided with a plurality of valves between main feed system and the steam generator, be positioned on the jet chimney containment and near the position of containment and on jet chimney, be positioned at containment outside and the position of close containment be provided with simple non-return valve (One-way Valve, VL).
As shown in Figure 1, the boundary of nuclear island and conventional island is provided with flow-through orifice (being the 101KD shown in Fig. 1,102KD and 103KD), also is the separation of safe level and non-safe level, and wherein 101KD, 102KD and 103KD turn left and be conventional island, turn right to be nuclear island.
Main feed system isolation valve group (is that 051～062VL) shown in Fig. 1 and feed-regulating valve (are that 031～033VL) shown in Fig. 1 is positioned at the conventional island factory building.Because the conventional island plant designing standard at place is general antidetonation structures, do not carry out seismic design, so under the situation of stack seismic events, the isolation valve group may lose efficacy, influence the realization of its function, cause the main uncontrollably steam in jection generator that feeds water, and enter reactor building, cause containment superpressure risk by containment internal steam pipe road cut.When needs are isolated main feed system, realize by closing main feed system isolation valve group, and these valves all are non-safe level, can not consider to be used to alleviate accident harm under accident conditions.Therefore, the inside and outside non-return valve of safety isolation main dependence containment of main feed system (is 037～042VL) shown in Fig. 1.
According to system design of 900MWe PWR nuclear power plant and the regulation of building 2.1.3.3.3 in the standard (RCC-P (1991) nineteen ninety-five translate): simple non-return valve can not be as the outer automatic isolating valve of containment, and therefore above prior art can not satisfy safety standard.And variable valve in the prior art scheme and main feed system isolation valve group are positioned at the conventional island factory building, consider from the angle of determining opinion, can not consider the favourable action of non-safe level equipment under accident conditions, so the reliability of prior art scheme are lower.
The utility model content
The technical problems to be solved in the utility model is, at the above-mentioned defective of prior art, provides a kind of nuclear power factory owner feedwater flow control system, to guarantee effectively to isolate main feedwater under accident conditions, prevents the steam generator spill-over, reduces containment superpressure risk.
The technical scheme that its technical matters that solves the utility model adopts is:
Construct a kind of nuclear power factory owner feedwater flow control system, comprise the steam generator that is positioned at reactor inside, and the main feed system that is positioned at the reactor outside, be connected by passing containment vessel and valvular jet chimney being set between described main feed system and the described steam generator, be positioned at described containment on the described jet chimney and be provided with non-return valve near the position of described containment; Wherein, it is outer and be provided with isolation valve near the position of described containment to be positioned at described containment on the described jet chimney.
Nuclear power factory owner feedwater flow control system described in the utility model, wherein, described isolation valve is nuclear level isolation valve.
Nuclear power factory owner feedwater flow control system described in the utility model, wherein, described nuclear level isolation valve is gas-liquid linked isolation valve.
Nuclear power factory owner feedwater flow control system described in the utility model, wherein, described nuclear level isolation valve is electronic isolation valve.
Nuclear power factory owner feedwater flow control system described in the utility model wherein, is connected with emergency power pack on the described electronic isolation valve.
Nuclear power factory owner feedwater flow control system described in the utility model wherein, is connected with auxiliary feedwater system on the described steam generator.
Nuclear power factory owner feedwater flow control system described in the utility model, wherein, the position that described jet chimney is positioned at the outer and close described main feed system of described containment is provided with the valve group that comprises feedwater isolation valve.
Nuclear power factory owner feedwater flow control system described in the utility model, wherein, described valve group also comprises feed-regulating valve.
Nuclear power factory owner feedwater flow control system described in the utility model, wherein, the jet chimney between described valve group and the described nuclear level isolation valve is provided with flow-through orifice.
Nuclear power factory owner of the present utility model gives the flow control water system by isolation valve is set outside containment, isolation valve begins action after the safe level control signal that receives from master-control room, cut off main feedwater from both direction effectively, guaranteed under accident conditions, effectively isolate main feedwater, prevent the steam generator spill-over and reduce containment superpressure risk, improve the security of nuclear power plant.
Description of drawings
The utility model is described in further detail below in conjunction with drawings and Examples, in the accompanying drawing:
Fig. 1 is the nuclear power factory owner feedwater flow control system schematic diagram of prior art;
Fig. 2 is a nuclear power factory owner feedwater flow control system schematic diagram of the present utility model.
Embodiment
Below in conjunction with diagram, preferred embodiment of the present utility model is described in detail.
The nuclear power factory owner feedwater flow control system schematic diagram of the utility model preferred embodiment as shown in Figure 2, it comprises the steam generator SG that is positioned at reactor inside, and the main feed system MFS2 that is positioned at the reactor outside.Be connected by passing containment vessel 9 and valvular jet chimney 3 being set between main feed system 2 and the steam generator 1, be positioned at containment 9 on the jet chimney 3 and be provided with non-return valve 4 near the position of containment 9.The position that is positioned at close containment 9 outside the containment 9 on jet chimney 3 is provided with isolation valve 6.
Wherein, the isolation valve 6 preferred nuclear level isolation valves that adopt.Generally speaking, nuclear grade valve comprises nuclear level isolation valve, compares with the conventional power plant valve, except that all features that possess the conventional power plant valve, also has following characteristics:
1, Yan Ge technical requirement.Because rib level valve has many specific (special) requirements, require the technical conditions of having worked out a series of designs, manufacturing, test and examination specially about nuclear grade valve according to these.Gu this, the requirement of nuclear grade valve each side is all complicated and strict than conventional power plant valve.Such as aspect the design load except considering working pressure, outside the working temperature, also should consider seismic (seismal and other load.Aspect operation characteristic, also to satisfy the requirement of the various operating conditions of nuclear power station, as disturbance operating mode, emergency work condition, accident conditions, operating condition of test etc.
2, anti-radiation property.The metal material that nuclear grade valve is selected except must satisfying the requirement of actuating medium, is also answered anti-irradiation, and its usability should not change after promptly material was subjected to irradiation.Nonmetallic materials (as various O-ring seals, pad, fill out volume, barrier film etc.) more should have certain radiation-resistant property.They should be able to finish the function that it is fulfiled at least in a complete time between overhauls(TBO).Gu this this with regard to requiring the selected nonmetallic materials of nuclear grade valve are done resistance to radiation test.
3, Yan Ge seal request.Sealing and external seal in the sealing of valve generally comprises.The outside seal requirement of nuclear grade valve is very strict, requires not have to leak outside, and middle flange seal should be safe and reliable, can adopt the sealing flange weldering.Leak outside in order to guarantee that valve skewer place does not have, can adopt sylphon seal and centre to draw the leakage mode on the structure.The interior sealing of nuclear grade valve is also strict than the conventional power plant valve.
4, filler special and pad.Nuclear grade valve and coupled pipeline and miscellaneous equipment great majority are stainless steel, because fluorine ion, chlorion and sulphion can destroy matter forever, may cause valve rod, the corrosion of flap even miscellaneous equipment.Be stranded this, the filler, the fluorine ion in the pad, chlorion and the sulphion content that require nuclear grade valve to use should be respectively less than certain standards.
5, architectural feature.Because nuclear grade valve environment of living in has certain irradiation dose, require the speed of mounting or dismounting maintenance valve fast, valve mechanism should be tried one's best simply.
With outside containment 9, adopt simple non-return valve (seeing also (037/038/039VL) shown in Fig. 1) in the prior art and compare, adopt isolation valve 6 can better play the effect of isolating main water, under accident conditions, to prevent steam generator 1 spill-over, reduce containment 9 superpressure risks.Isolation valve 6 begins action after the safe level control signal that receives from the nuclear power station master-control room, cut off main feedwater from both direction effectively, promptly no matter have an accident operating modes in the containment 9 or outside the containment 9, can both adopt isolation valve 6 to cut off main feedwater, guarantee the integrality of containment 9 and the security of nuclear power station.Simple non-return valve (seeing also (037/038/039VL) shown in Fig. 1) is set outside containment can only realizes that then folk prescription is to cutting off main feedwater.
Among the above embodiment, isolation valve 6 adopts the electronic isolation valve of making the nuclear level of driving energy with electric energy.Preferably, when adopting electronic isolation valve, can on electronic isolation valve, connect emergency power pack (not shown),, overcome safe level electric energy undersupply so that give electronic isolation valve power supply.Electronic isolation valve can cut out after the safe level control signal that receives from the nuclear power station master-control room at short notice, as 20 seconds, cuts off main feedwater from both direction effectively, guarantees the integrality of containment and the security of nuclear power station.
More preferably, the isolation valve 6 preferred gas-liquid linked isolation valves that adopt the nuclear level, gas-liquid linked isolation valve is after the safe level control signal that receives from master-control room, can close at short notice, as 10 seconds, cut off main feedwater from both direction effectively, guarantee the integrality of containment 9 and the security of nuclear power station.
Wherein, because electronic isolation valve is in when action, the motor rotation needs certain hour, and gas-liquid linked isolation valve is very snap action then, and therefore gas-liquid linked isolation valve has than electronic isolation valve reaction velocity faster.Therefore, when having an accident operating mode, adopt gas-liquid linked isolation valve can significantly reduce water percolating capacity, further guarantee the integrality of containment and the security of nuclear power station.
In a further embodiment, as shown in Figure 2, contiguous steam generator 1 is provided with auxiliary feedwater system 7; Outside jet chimney 3 is positioned at containment 9 and near the position of main feed system 2, be provided with the valve group 8 that comprises feedwater isolation valve and feed-regulating valve; Jet chimney 3 between this valve group 8 and the isolation valve 6 is provided with flow-through orifice 5, and flow-through orifice 5 places wherein are boundarys of nuclear island and conventional island, also are the separations of safe level and non-safe level.
As shown in Figure 2, feedwater enters feed main from the high-pressure heater system, is divided into 3 parallel jet chimneys 3 again and delivers to 3 steam generators 1 respectively.Main feed system 2 feeds water by jet chimney 3 supplies to steam generator 1, and the water level of steam generator 1 secondary side is maintained one with on the steam turbine load variation institute predetermined reference value; Main feed system also triggers steam generator liquid level protection action simultaneously; make the feedwater isolation valve quick closedown; make feedwater main inlet control valve and the quick closedown of feed water by-pass variable valve, and start feed pump, main feed pump tripping operation, to failing the protection of anticipated transient of emergency shut-down.
Owing to increased isolation valve 6, under accident conditions, isolation valve 6 begins action after receiving safe level control signal from the nuclear power station master-control room, cut off main feedwater from both direction effectively, guaranteed under accident conditions, effectively isolate main feedwater, prevent steam generator 1 spill-over and reduce containment 9 superpressure risks, improve the security of nuclear power plant.
Should be understood that, for those of ordinary skills, can be improved according to the above description or conversion, and all these improvement and conversion all should belong to the protection domain of the utility model claims.
Claims (9)
1. nuclear power factory owner feedwater flow control system, comprise the steam generator that is positioned at reactor inside, and the main feed system that is positioned at the reactor outside, be connected by passing containment vessel and valvular jet chimney being set between described main feed system and the described steam generator, the position that is positioned at described containment and close described containment on the described jet chimney is provided with non-return valve, it is characterized in that the position that is positioned at the outer and close described containment of described containment on the described jet chimney is provided with isolation valve.
2. nuclear power factory owner feedwater flow control system according to claim 1 is characterized in that, described isolation valve is nuclear level isolation valve.
3. nuclear power factory owner feedwater flow control system according to claim 2 is characterized in that, described nuclear level isolation valve is gas-liquid linked isolation valve.
4. nuclear power factory owner feedwater flow control system according to claim 2 is characterized in that, described nuclear level isolation valve is electronic isolation valve.
5. nuclear power factory owner feedwater flow control system according to claim 3 is characterized in that, is connected with emergency power pack on the described electronic isolation valve.
6. according to each described nuclear power factory owner feedwater flow control system among the claim 1-5, it is characterized in that, be connected with auxiliary feedwater system on the described steam generator.
7. nuclear power factory owner feedwater flow control system according to claim 6 is characterized in that, the position that described jet chimney is positioned at the outer and close described main feed system of described containment is provided with the valve group that comprises feedwater isolation valve.
8. nuclear power factory owner feedwater flow control system according to claim 7 is characterized in that described valve group also comprises feed-regulating valve.
9. nuclear power factory owner feedwater flow control system according to claim 8 is characterized in that, the jet chimney between described valve group and the described nuclear level isolation valve is provided with flow-through orifice.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010202685316U CN201741419U (en) | 2010-07-22 | 2010-07-22 | Main water supply flow control system of nuclear power plant |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010202685316U CN201741419U (en) | 2010-07-22 | 2010-07-22 | Main water supply flow control system of nuclear power plant |
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| CN201741419U true CN201741419U (en) | 2011-02-09 |
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| CN2010202685316U Expired - Lifetime CN201741419U (en) | 2010-07-22 | 2010-07-22 | Main water supply flow control system of nuclear power plant |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103050161A (en) * | 2012-12-11 | 2013-04-17 | 中国核电工程有限公司 | Method for automatically isolating auxiliary water supply pipeline |
| CN103187110A (en) * | 2012-01-03 | 2013-07-03 | 陈光焕 | Nuclear energy steam self-compression water adding rod |
| CN103474117A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safety supply method of auxiliary water supply system through adding of by-pass pipelines |
| CN103514312A (en) * | 2012-06-28 | 2014-01-15 | 中国核电工程有限公司 | Method for analyzing loss and consequences of compression air system |
| CN103778979A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Secondary circuit coolant supply system and method for nuclear power station |
| WO2015014046A1 (en) * | 2013-07-30 | 2015-02-05 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
| CN104343753A (en) * | 2013-07-26 | 2015-02-11 | 中核核电运行管理有限公司 | Quick-closing hydraulic system of main steam isolation valve executing mechanism capable of automatically relieving pressure |
| CN107145175A (en) * | 2017-05-26 | 2017-09-08 | 中国核动力研究设计院 | A kind of steam generator feed temperature controls simulation system |
-
2010
- 2010-07-22 CN CN2010202685316U patent/CN201741419U/en not_active Expired - Lifetime
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103187110A (en) * | 2012-01-03 | 2013-07-03 | 陈光焕 | Nuclear energy steam self-compression water adding rod |
| CN103187110B (en) * | 2012-01-03 | 2015-11-25 | 陈光焕 | Nuclear steam dead weight water-adding rod |
| CN103514312A (en) * | 2012-06-28 | 2014-01-15 | 中国核电工程有限公司 | Method for analyzing loss and consequences of compression air system |
| CN103514312B (en) * | 2012-06-28 | 2017-07-07 | 中国核电工程有限公司 | A kind of compressed air system forfeiture and the analysis method of consequence |
| CN103778979A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Secondary circuit coolant supply system and method for nuclear power station |
| CN103050161A (en) * | 2012-12-11 | 2013-04-17 | 中国核电工程有限公司 | Method for automatically isolating auxiliary water supply pipeline |
| CN103050161B (en) * | 2012-12-11 | 2016-03-30 | 中国核电工程有限公司 | The method of auxiliary feedwater pipeline automatism isolation |
| CN104343753A (en) * | 2013-07-26 | 2015-02-11 | 中核核电运行管理有限公司 | Quick-closing hydraulic system of main steam isolation valve executing mechanism capable of automatically relieving pressure |
| WO2015014046A1 (en) * | 2013-07-30 | 2015-02-05 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
| CN103474117A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safety supply method of auxiliary water supply system through adding of by-pass pipelines |
| CN103474117B (en) * | 2013-09-03 | 2016-08-17 | 中国核电工程有限公司 | A kind of safe replenishing method of auxiliary feedwater system increasing bypass line |
| CN107145175A (en) * | 2017-05-26 | 2017-09-08 | 中国核动力研究设计院 | A kind of steam generator feed temperature controls simulation system |
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Granted publication date: 20110209 |
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| CX01 | Expiry of patent term |