CN101149990A - Non-kinetic inherently safe tube-pool type reactor - Google Patents
Non-kinetic inherently safe tube-pool type reactor Download PDFInfo
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- CN101149990A CN101149990A CNA2007101662856A CN200710166285A CN101149990A CN 101149990 A CN101149990 A CN 101149990A CN A2007101662856 A CNA2007101662856 A CN A2007101662856A CN 200710166285 A CN200710166285 A CN 200710166285A CN 101149990 A CN101149990 A CN 101149990A
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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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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to an inherent safety tube-pool type nuclear reactor for research. The cooling-water main pump and the after-heat deriving pump of the reactor are set at back of the main heat-exchanger and connected in parallel in the main circuit room. The after-heat heat-exchanger is fitted in the water pool of the reactor. The main circuit room is provided at upper part of the water pool and at the bottom of the main circuit room there is a pipeline communicated to the under-water part of the water pool. At the inlet and the outlet of the reactor core is respectively provided with a hydraulic control open-close valve communicated with the water pool of the reactor. When the main pipeline occurs water-loss fault, water in the main circuit room can return to the water pool. At same time, as the pressure in the reactor container is low, the hydraulic control open-close valves at inlet and outlet of the reactor core automatically opens. When the after-heat deriving pump occurs fault, the inlet-outlet hydraulic control open-close valve is opened by a signal of high reactor-core temperature to make the reactor core and the water pool form a natural circulation to derive the after heat of reactor core into the water pool of the reactor.
Description
Technical field
The present invention relates to a kind of nuclear reactor, be specifically related to the instrument heap of a kind of multi-functional research reactor and fuel, material test usefulness.
Background technology
Instrument heap for multi-functional research reactor and fuel, material test usefulness will take into full account inherently safe and passive safety system.For the research tube-pool type reactor of having built, require from existing safety standard, perfect inadequately place is all arranged.All go up in vain downwards as the ATR of the JMTR of Japan, the U.S. and the HFETR of China and the reactor core water (flow) direction of CARR research reactor, reactor core has a flow Umklapp process after stopping; There is not the second cover reactor shut-off system; The waste heat guiding system is the energy dynamic formula, and reliable source of power fault or waste heat are derived pump startup and do not got up to cause serious consequence; At primary pipe rupture's loss of-coolant accident (LOCA) (before the main pump outlet non-return valve), when voltage stabilizer fails to cut out with heap container communicating valve, gas can be pressed in the heap in the voltage stabilizer, cause the reactor core dehydration to quicken, especially cutout back main pump outlet non-return valve is closed automatically, gas is not run out of from the heap induction pipe, and air pressure presses reactor core water to dirty, might cause the reactor core dehydration.Fuel assembly bears the research reactor of high pressure and fuel in the world, material test instrument heap all fails well to address the above problem.
Be the security of pursuing multiduty research reactor and piling, must adopt inherent safety and reliable passive safety system, to satisfy the nuclear safety requirement of research tube-pool type reactor based on the instrument of fuel material test.
Summary of the invention
The object of the present invention is to provide a kind of inherently safe tube-pool type reactor with passive safety system.
Technical scheme of the present invention is as follows:
A kind of non-active inherently safe tube-pool type reactor, comprise reactor pit, be arranged in the reactor pressure vessel of reactor pit and be arranged in the reactor core of reactor pressure vessel, reactor pressure vessel top is communicated with main heat exchanger by the reactor coolant water outlet; Main heat exchanger is communicated with the reactor coolant water induction pipe by two parallel pipelines, wherein a pipeline is provided with reactor coolant water main pump, main pump outlet non-return valve, another pipeline is provided with waste heat and derives pump, waste heat derivation pump discharge non-return valve, afterheat heat exchanger, and afterheat heat exchanger is arranged in the pond; The reactor coolant water induction pipe is communicated with the reactor pressure vessel bottom; Be connected with voltage stabilizer in the bypass of reactor coolant water outlet.
Described reactor coolant water outlet (5) bypass is provided with waste heat and derives outlet valve (4), reactor coolant water induction pipe (6) bypass is provided with waste heat and derives inlet valve (15), both are hydraulic control valve, the other end of valve communicates with reactor pit (2), and hydraulic control valve comprises the piston sleeve (26) in the valve body (20), positive chamber piston (25) and negative chamber piston (19); Positive chamber piston (25) communicates with the logical high pressure water valve (24) of logical reactor pit valve (23) in positive chamber and positive chamber; Negative chamber piston (19) communicates with the logical high pressure water valve (22) of logical reactor pit valve (21) in negative chamber and negative chamber.
Described waste heat derive outlet valve (4) and waste heat derivation inlet valve (15) can waste heat derive that pump (10) stops and the chain signal of reactor core (1) temperature height " with door " under open.
The top of described reactor pit (2) is provided with (11) between major loop, main heat exchanger (8), main pump (9), waste heat are derived pump (10) and are placed (11) between major loop, and the bottom of (11) has a drain pipe (12) to pass reactor pit wall (14) to communicate below the water surface with reactor pit (2) between major loop.
The invention has the advantages that: 1. because afterheat heat exchanger is placed on the back of main heat exchanger, when the temperature of water in the reactor pit is identical with the main heat exchanger outlet temperature with regard to heat transfer water that can not be in reactor pit.Have only not heat conduction of main heat exchanger (main pump out of service or secondary side discharge stop), when the main heat exchanger outlet temperature raise, afterheat heat exchanger made reactor have inherent safety just to the pond heat transfer water; 3. when waste heat derivation pump breaks down, open waste heat by the high signal of core temperature and derive outlet valve and waste heat derivation inlet valve, reactor core and reactor pit form Natural Circulation, and the waste heat of deriving reactor core has ensured the safety of reactor core to reactor pit; 2. owing to be arranged in the top of reactor pit between major loop, water seal is arranged when normal operation, to isolate with space above the reactor pond between major loop, water can be got back to the heap pond when trunk line generation loss of-coolant accident (LOCA), because reactor vessel pressure is low, open reactor core automatically and import and export waterpower gauge tap valve, make reactor core and reactor pit form Natural Circulation, the waste heat of deriving reactor core makes reactor have reliable passive safety system to reactor pit.
Description of drawings
Fig. 1 is a kind of structural representation of tube-pool type reactor.
Fig. 2 is a kind of structural representation of hydraulic control valve.
Among the figure:,
1. reactor core 2. reactor pits 3. water pipe quick detach joints
4. waste heat is derived outlet valve 5. reactor coolant water outlets 6. reactor coolant water induction pipes
7. voltage stabilizer 8. main heat exchangers 9. main pumps
10. waste heat is derived 12. drain pipes between pump 11. major loops
13. afterheat heat exchanger 14. reactor pit walls 15. waste heats are derived inlet valve
16. reactor pressure vessel 17. main pump outlet non-return valves 18. waste heats are derived the pump discharge non-return valve
19. the logical reactor pit valve in negative piston 20. hydraulic control valve valve bodies 21. negative chambeies, chamber
22. the logical high pressure water valve in logical reactor pit valve 24. positive chambeies, logical high pressure water valve 23. positive chambeies, negative chamber
25. positive chamber piston 26. piston sleeves
Embodiment
Tube-pool type reactor as shown in Figure 1, reactor pressure vessel 16 are installed in the reactor pit 2, and reactor core 1 is installed in the reactor pressure vessel 16, and reactor pressure vessel 16 tops are communicated with main heat exchanger 8 by reactor coolant water outlet 5; Main heat exchanger 8 is communicated with reactor coolant water induction pipe 6 by two parallel pipelines, wherein be connected with reactor coolant water main pump 9, main pump outlet non-return valve 17 in turn on a pipeline, be connected with waste heat on another pipeline in turn and derive pump 10, waste heat derivation pump discharge non-return valve 18, afterheat heat exchanger 13, afterheat heat exchanger 13 is arranged in pond 2; Reactor coolant water induction pipe 6 is communicated with reactor pressure vessel 16 bottoms; Be connected with voltage stabilizer 7 in 5 bypasses of reactor coolant water outlet; Waste heat is installed in 5 bypasses of reactor coolant water outlet derives outlet valve 4, waste heat is installed in 6 bypasses of reactor coolant water induction pipe derives inlet valve 15, both are hydraulic control valve, and the other end of valve communicates with reactor pit 2; Above reactor pit 2, be provided with between major loop 11, main heat exchanger 8, main pump 9, waste heat are derived pump 10, main pump outlet non-return valve 17, waste heat and are derived the pump discharge non-return valve and place between major loop 11,11 bottom has a drain pipe 12 to pass reactor pit wall 14 and communicate below reactor pit 2 waters surface between major loop, and drain pipe 12 has one " several " oxbow.
The loop that reactor coolant water flows through has constituted a loop of reactor, i.e. major loop.
Fig. 2 has represented the structure of hydraulic control valve, and hydraulic control valve comprises the piston sleeve 26 in valve body 20, the valve body 20, positive chamber piston 25 and negative chamber piston 19; Positive chamber piston 25 communicates with the logical high pressure water valve 24 of logical reactor pit valve 23 in positive chamber and positive chamber; Negative chamber piston 19 communicates with the logical high pressure water valve 22 of logical reactor pit valve 21 in negative chamber and negative chamber.Waste heat derive outlet valve 4 and waste heat derive inlet valve 15 can waste heat derive pump 10 stop with the chain signal of reactor core 1 temperature height " with door " under open.
In this embodiment of the present invention, reactor core 1 is a sleeve pipe pressure-bearing annular reactor core, reloads for convenience, water pipe quick detach joint 3 is installed on reactor pressure vessel cooling water outlet pipe 5, when reloading, water pipe quick detach joint 3 is taken apart, the loam cake of reactor core 1 container of slinging reloads.For reactor core 1 is whole honeycomb annular reactor core 1 embodiment such as grade, does not need to install water pipe quick detach joint 3.
During reactor operation, reactor coolant water main pump 9 is derived pump 10 with waste heat and is moved simultaneously, the hot water of reactor core 1 heating in reactor vessel is by reactor coolant water outlet 5, through voltage stabilizer 7 voltage stabilizings, flow into main heat exchanger 8, derive pump 10, afterheat heat exchanger 13 through reactor coolant water main pump 9 in parallel and waste heat again, after reactor coolant water induction pipe 6 get back in the reactor core 1.Afterheat heat exchanger 13 is placed on the back of main heat exchanger 8, just can not be to the pond heat transfer water when the temperature of water in the reactor pit 2 is identical with main heat exchanger 8 outlet temperatures.Have only main heat exchanger 8 not heat conduction situations such as (main heat exchanger 8 secondary side discharges under) stopping, when main heat exchanger 8 outlet temperatures raise, afterheat heat exchanger 13 was just to the pond heat transfer water.
Waste heat is derived pump 10 by the reliable source of power power supply, and the water pump characteristic is a software feature, and when pump capacity was zero, its lift was a bit larger tham main pump 9 working point lifts.When main pump 9 was out of service, waste heat was derived pump 10 and is continued operation, and this moment, SR descended, and waste heat is derived pump 10 flows and increased, and waste heat is directed at reactor pit 2.
The course of work of above-mentioned hydraulic control valve is: positive chamber piston 16 is logical high pressure water valve 19 logical water under high pressures through positive chamber, and negative chamber piston 17 is logical reactor pit valve 21 logical reactor pits 2 through negative chamber, by the pressure of water with closure of check ring.After a heap and a loop boosted to rated pressure, positive chamber piston 16 was by the loop water pressurization after boosting, and then, to reactor pit 2 pressure releases, negative chamber piston 17 adds definite value hydraulic pressure through the logical high pressure water valve 22 in negative chamber through the logical reactor pit valve 18 in positive chamber.Definite value hydraulic pressure * negative cavity area=hydrostatic circuit when waterpower gauge tap valve is opened * positive cavity area.This moment, waterpower gauge tap valve cut out when reactor startup moves, when pressure is low to moderate setting valve, automatically open during waterpower gauge tap valve, adjust the negative cavity area of waterpower gauge tap valve, open waste heat when realizing loss of-coolant accident (LOCA) earlier and derive outlet valve 4, discharge the gas in the voltage stabilizer, and then open waste heat and derive inlet valve 15, the water level of reactor core just can not descend.At this moment, reactor core in the reactor vessel 1 and reactor pit 2 form Natural Circulation, and the waste heat of deriving reactor core is to reactor pit 2.
Under the situation that waste heat derivation pump 10 also breaks down, waste heat is derived pump 10 and is stopped to derive outlet valve 4, waste heat derivation inlet valve 15 with the chain waste heat of opening of high two signals of reactor core 1 temperature " with door ", reactor core 1 in the reactor vessel forms Natural Circulation with reactor pit 2, derives reactor core 1 waste heat to reactor pit 2.
When normal reactor operation, the " warp architecture of the water-supply-pipe 12 of bottom forms water seal between major loop, makes between major loop 11 to isolate with space above the reactor pit 2; When loss of-coolant accident (LOCA) took place, the water of leakage can flow back to pond 2 by water-supply-pipe 12, if major loop temperature height is mingled with steam in the dehydration, and when then steam is from drain pipe 12 effusions, the very fast condensation in 2 underwaters in the pond.
Claims (4)
1. non-active inherently safe tube-pool type reactor, comprise reactor pit (2), be arranged in the reactor pressure vessel (16) of reactor pit (2), reactor core (1) in the reactor pressure vessel (16), reactor pressure vessel (16) top is communicated with main heat exchanger (8) by reactor coolant water outlet (5), be connected with voltage stabilizer (7) in reactor coolant water outlet (5) bypass, it is characterized in that: main heat exchanger (8) is communicated with reactor coolant water induction pipe (6) by two parallel pipelines, wherein be provided with reactor coolant water main pump (9) successively on a pipeline, main pump outlet non-return valve (17), be provided with waste heat on another pipeline successively and derive pump (10), waste heat is derived pump discharge non-return valve (18), afterheat heat exchanger (13), afterheat heat exchanger (13) is arranged in pond (2); Reactor coolant water induction pipe (6) is communicated with reactor pressure vessel (16) bottom.
2. non-active inherently safe tube-pool type reactor as claimed in claim 1, it is characterized in that: described reactor coolant water outlet (5) bypass is provided with waste heat and derives outlet valve (4), reactor coolant water induction pipe (6) bypass is provided with waste heat and derives inlet valve (15), both are hydraulic control valve, the other end of valve communicates with reactor pit (2), and hydraulic control valve comprises the piston sleeve (26) in the valve body (20), positive chamber piston (25) and negative chamber piston (19); Positive chamber piston (25) communicates with the logical high pressure water valve (24) of logical reactor pit valve (23) in positive chamber and positive chamber; Negative chamber piston (19) communicates with the logical high pressure water valve (22) of logical reactor pit valve (21) in negative chamber and negative chamber.
3. non-active inherently safe tube-pool type reactor as claimed in claim 2 is characterized in that: waste heat derive outlet valve (4) and waste heat derivation inlet valve (15) can waste heat derive that pump (10) stops and the chain signal of reactor core (1) temperature height " with door " under open.
4. as claim 1 or 2 or 3 described non-active inherently safe tube-pool type reactors, it is characterized in that: be provided with (11) between major loop in the top of reactor pit (2), main heat exchanger (8), main pump (9), waste heat are derived pump (10) and are placed (11) between major loop, and the bottom of (11) has a drain pipe (12) to pass reactor pit wall (14) to communicate below the water surface with reactor pit (2) between major loop.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200710166285A CN100578683C (en) | 2007-11-09 | 2007-11-09 | Non-kinetic inherently safe tube-pool type reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200710166285A CN100578683C (en) | 2007-11-09 | 2007-11-09 | Non-kinetic inherently safe tube-pool type reactor |
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| CN101149990A true CN101149990A (en) | 2008-03-26 |
| CN100578683C CN100578683C (en) | 2010-01-06 |
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Cited By (18)
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| CN101826370A (en) * | 2010-03-15 | 2010-09-08 | 中国原子能科学研究院 | Vertical channel for monitoring irradiation of pool reactor material |
| CN101719386B (en) * | 2009-12-21 | 2012-07-04 | 肖宏才 | Entire passive shutdown safe cooling device of advanced pressurized water reactor nuclear power plant and operation program thereof |
| CN102667954A (en) * | 2009-09-25 | 2012-09-12 | 希尔莱特有限责任公司 | A heat exchanger, methods therefor and a nuclear fission reactor system |
| CN102903402A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Advanced secondary side core heat lead-out device |
| CN103165200A (en) * | 2013-01-14 | 2013-06-19 | 上海核工程研究设计院 | Decay heat removal system of reactor |
| CN103383865A (en) * | 2007-11-15 | 2013-11-06 | 由俄勒冈州高等教育管理委员会代表的俄勒冈州立大学 | Passive emergency feedwater system |
| CN103778974A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Kinetic and non-kinetic combined waste heat discharging system |
| WO2014090100A1 (en) * | 2012-12-10 | 2014-06-19 | 中国核动力研究设计院 | Inlet pipeline structure of residual heat removal system capable of avoiding phenomenon of "dead pipeline" |
| CN104143360A (en) * | 2013-05-08 | 2014-11-12 | 韩国原子力研究院 | Cooling system of emergency cooling tank and nuclear power plant having the same |
| CN104269194A (en) * | 2014-10-13 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Temperature-triggered passive accident residual heat removal system for pool type reactor |
| US9221093B2 (en) | 2009-09-25 | 2015-12-29 | Terrapower, Llc | Heat exchanger, methods therefor and a nuclear fission reactor system |
| US9275760B2 (en) | 2009-09-25 | 2016-03-01 | Terrapower, Llc | Heat exchanger, methods therefor and a nuclear fission reactor system |
| CN106128527A (en) * | 2016-07-05 | 2016-11-16 | 中国核动力研究设计院 | The initial operating mode of passive experiment sets up aid system and using method thereof |
| CN107293338A (en) * | 2016-04-12 | 2017-10-24 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety system |
| CN107492400A (en) * | 2016-06-13 | 2017-12-19 | 国家电投集团科学技术研究院有限公司 | Dry type reactor heating system |
| US9984777B2 (en) | 2007-11-15 | 2018-05-29 | Nuscale Power, Llc | Passive emergency feedwater system |
| CN110444301A (en) * | 2019-08-13 | 2019-11-12 | 中国核动力研究设计院 | Simulate supercritical pressure transient condition experimental provision and experimental method |
| CN111883270A (en) * | 2020-08-26 | 2020-11-03 | 中国原子能科学研究院 | Heat removal system, pool reactor, and pool reactor heat removal method |
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2007
- 2007-11-09 CN CN200710166285A patent/CN100578683C/en active Active
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| CN103383865A (en) * | 2007-11-15 | 2013-11-06 | 由俄勒冈州高等教育管理委员会代表的俄勒冈州立大学 | Passive emergency feedwater system |
| US9984777B2 (en) | 2007-11-15 | 2018-05-29 | Nuscale Power, Llc | Passive emergency feedwater system |
| US9221093B2 (en) | 2009-09-25 | 2015-12-29 | Terrapower, Llc | Heat exchanger, methods therefor and a nuclear fission reactor system |
| CN102667954A (en) * | 2009-09-25 | 2012-09-12 | 希尔莱特有限责任公司 | A heat exchanger, methods therefor and a nuclear fission reactor system |
| US9275760B2 (en) | 2009-09-25 | 2016-03-01 | Terrapower, Llc | Heat exchanger, methods therefor and a nuclear fission reactor system |
| CN101719386B (en) * | 2009-12-21 | 2012-07-04 | 肖宏才 | Entire passive shutdown safe cooling device of advanced pressurized water reactor nuclear power plant and operation program thereof |
| CN101826370B (en) * | 2010-03-15 | 2012-10-17 | 中国原子能科学研究院 | Vertical channel for monitoring irradiation of pool reactor material |
| CN101826370A (en) * | 2010-03-15 | 2010-09-08 | 中国原子能科学研究院 | Vertical channel for monitoring irradiation of pool reactor material |
| CN102903402A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Advanced secondary side core heat lead-out device |
| CN103778974B (en) * | 2012-10-22 | 2016-08-31 | 中国核动力研究设计院 | A kind of active and passive residual heat removal system combined |
| CN103778974A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Kinetic and non-kinetic combined waste heat discharging system |
| WO2014090100A1 (en) * | 2012-12-10 | 2014-06-19 | 中国核动力研究设计院 | Inlet pipeline structure of residual heat removal system capable of avoiding phenomenon of "dead pipeline" |
| CN103165200B (en) * | 2013-01-14 | 2016-01-27 | 上海核工程研究设计院 | A kind of decay heat removal system of reactor |
| CN103165200A (en) * | 2013-01-14 | 2013-06-19 | 上海核工程研究设计院 | Decay heat removal system of reactor |
| US10229762B2 (en) | 2013-05-08 | 2019-03-12 | Korea Atomic Energy Research Institute | Cooling system of emergency cooling tank and nuclear power plant having the same |
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| CN104269194A (en) * | 2014-10-13 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Temperature-triggered passive accident residual heat removal system for pool type reactor |
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| CN107492400A (en) * | 2016-06-13 | 2017-12-19 | 国家电投集团科学技术研究院有限公司 | Dry type reactor heating system |
| CN107492400B (en) * | 2016-06-13 | 2023-11-03 | 国家电投集团科学技术研究院有限公司 | Dry reactor heating system |
| CN106128527A (en) * | 2016-07-05 | 2016-11-16 | 中国核动力研究设计院 | The initial operating mode of passive experiment sets up aid system and using method thereof |
| CN110444301B (en) * | 2019-08-13 | 2022-07-01 | 中国核动力研究设计院 | Experimental device and experimental method for simulating supercritical pressure transient working condition |
| CN110444301A (en) * | 2019-08-13 | 2019-11-12 | 中国核动力研究设计院 | Simulate supercritical pressure transient condition experimental provision and experimental method |
| CN111883270A (en) * | 2020-08-26 | 2020-11-03 | 中国原子能科学研究院 | Heat removal system, pool reactor, and pool reactor heat removal method |
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