CN104575635B - A kind of accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement - Google Patents
A kind of accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement Download PDFInfo
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- CN104575635B CN104575635B CN201410767394.3A CN201410767394A CN104575635B CN 104575635 B CN104575635 B CN 104575635B CN 201410767394 A CN201410767394 A CN 201410767394A CN 104575635 B CN104575635 B CN 104575635B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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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
- Y02E30/30—Nuclear fission reactors
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
The present invention relates to a kind of accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement, including be arranged in hot sodium pond independent heat exchanger, be arranged between cold and hot plenums and run through heat exchanger, described independent heat exchanger and connect the sodium air heat exchanger for being arranged on out-of-pile by pipeline respectively through heat exchanger, the position of described sodium air heat exchanger is higher than the independent heat exchanger and through heat exchanger；When occurring accident, described independent heat exchanger and the inlet baffle opening through heat exchanger, hot sodium enters independent heat exchanger and through heat exchanger, and the sodium for flowing through independent heat exchanger is sunk in the gap of fuel assembly in hot sodium pond, forms flowing between box；The sodium flowed through through heat exchanger forms path in the box of fuel assembly, is formed in box and flowed.The present invention realizes the discharge of residual heat of nuclear core using passive operation principle, effectively alleviates accident process, it is ensured that the safety of reactor.
Description
Technical field
The invention belongs to sodium-cooled fast reactor designing technique, and in particular to one kind is used for large-scale pool type natrium cold fast reactor asymmetric arrangement
Accident afterheat discharge system.
Background technology
Accident afterheat discharge system is one of most important engineered safeguards features of pool type natrium cold fast reactor, is to realize that reactor exists
The Main Means of the security function of Residual heat removal under accident conditions, it to keep heap each barrier integrality, it is to avoid radioactivity
Material has important effect to surrounding environment release.Under reactor accident operating mode, the mode of residual heat of nuclear core discharge is more, such as
Active form and passive form, from the path analysis of Residual heat removal, also have in more selection, such as pool fast reactor
Primary Ioops arrangement, arrangement of secondary circuit etc..To improve the reliability design of system, the safe operation of reactor is improved, it is passive
System design and arrangement be an important developing direction.
Develop the country of fast reactor technology, such as Russia, France, India, South Korea, all to large-scale fast reactor in the world at present
Accident afterheat discharge system device has carried out particular study, it is proposed that various method for arranging, is introduced one by one below.
The BN-800 fast reactors of the newest research and development of Russia, its reactor accident residual heat removal system does not use independent heat exchange
Device, and the function of independent heat exchanger is realized by intermediate heat exchanger in accident.It has 3 cooling loops in secondary circuit,
Each loop has a passive residual heat removal loop and a steam generator.Its Heat Discharging System of Chinese includes three
Individual independent Heat transmission loop, the heat removal capacity for having 100% per primary Ioops.Probabilistic safety analysis result shows core disassembly accident
The frequency of generation is less than 7 × 10-6/ year.Strictly speaking, its residual heat removal system is not passive, because each waste heat
There are two electromagnetic pumps powered by reliable source of power in discharge loop, strengthens circulation heat removal capacity, this is the main of the system design
Shortcoming.
The prototype fast reactor PFBR of India has 4 completely self-contained safe level residual heat removal systems, directly can be discharged from hot pond
Heat.Each system includes an independent heat exchanger being arranged in hot pond, a sodium-air heat exchanger and corresponding
The equipment such as pipeline.The air inlet and outlet in three loops are provided with air door, and using driven by power, remaining is entirely passive sets
It is standby, by Natural Circulation by heat from reactor core band to ultimate heat sink air.The design of the device is with the existing Residual heat removals of CEFR
The arrangement of system is similar, although residual heat of nuclear core can be discharged by the way of passive, under accidental conditions, the dress
The operation put can take away partial heat, and the economy to reactor has a certain impact.
France designs Residual heat removal by the way of secondary circuit combination altogether in newly developed ASTRID reactors
System.First, apply upper in system, when normal heat-transfer system fails, residual heat of nuclear core can be first by positioned at secondary circuit
Four sodium-air heat exchangers on bypass duct are discharged, and now secondary circuit can still be provided by forced circulation.Secondly, exist
Under accident conditions, the surface radiating of evaporator is also a utilizable important low-temperature receiver, by designing corresponding natural air exhaust
To discharge heat.Meanwhile, the reactor is also the same with SUPERPHENIX, is provided with similar heap vessel cooling system as auxiliary
Help cooling.If this set system in effective, waste heat still can be taken out of by the independent heat exchanger in primary Ioops pond.This
Set system has four loops, and each loop includes a sodium-sodium heat converter, electromagnetic pump and a sodium-air heat exchanger
Deng.The power of Residual heat removal can be adjusted by the air dampers on sodium-air heat exchanger.Under normal operation,
The operation of system can be maintained by the forced circulation of electromagnetic pump, under accident conditions, can be discharged by the Natural Circulation of system
Residual heat of nuclear core.So, for raft, the safety of residual heat of nuclear core discharge, body are ensure that by the way of these four are different
The diversity of system design is showed.But, so various design ensure that the security of reactor, but considerably increase reaction
The construction of heap and operating cost.
The KALIMA600 of prototype reactor in Korean Design, is used as the engineered safeguards features of heap, accident afterheat discharge system one
As be made up of 2 or 3 completely self-contained loops, can by Natural Circulation by decay heat from hot pond discharge out-pile.Each
Loop has a sodium-sodium heat converter (DHX), a sodium-air heat exchanger (AHX), and middle sodium loop connection, and in
Between not arrangement active component-mechanical pump or electromagnetic pump on sodium loop.The independent heat that is mainly characterized by of the design of South Korea is handed over
Parallel operation is arranged in the buffering area of cold and hot plenums, in reactor normal processes, and independent heat exchanger does not have sodium circulation, thus not
Heat can be conveyed to air heat exchanger, it is ensured that the economy of operation；And under accident conditions, the sodium of high temperature can flow in hot pond
Sodium dividing plate is crossed, makes the sodium insertion of the cold and hot plenums in buffering area, so that independent heat exchanger plays cooling effect.The waste heat is arranged
Go out the economy that scheme both ensure that reactor under accidental conditions, in turn ensure that the nuclear reactor safety under accident conditions,
But the program was never run on reactor, also in the presence of many uncertainties.
As can be seen that on the problem of solving residual heat removal system device, various countries are proposed difference from described above
Scheme, some use enabling fashions, some passive modes of use, or several ways combination, but all exist anti-
Answer the operating cost of heap higher, do not take into account the function etc. of the economical operation under nominal situation and the Residual heat removal under accident conditions
Problem.
The content of the invention
It is an object of the invention to provide the waste heat under a kind of economical operation that can be taken into account under nominal situation and accident conditions
Large-scale pool type natrium cold fast reactor residual heat removal system that is discharging and realizing passive operation.
Technical scheme is as follows：A kind of accident afterheat for large-scale pool type natrium cold fast reactor asymmetric arrangement is discharged
System, including independent heat exchanger, the heat exchanger that runs through that is arranged between cold and hot plenums being arranged in hot sodium pond, it is described
Independent heat exchanger and the sodium-air heat exchanger for being arranged on out-of-pile by pipeline connection respectively through heat exchanger, institute
The position for the sodium-air heat exchanger stated is higher than the independent heat exchanger and through heat exchanger；It is described when occurring accident
Independent heat exchanger and opened through the inlet baffle of heat exchanger, hot sodium enters independent heat exchanger and through heat exchange
Device, the sodium for flowing through independent heat exchanger is sunk in the gap of fuel assembly in hot sodium pond, forms flowing between box；Flow through and run through
The sodium of heat exchanger forms path in the box of fuel assembly, is formed in box and flowed.
Further, accident afterheat discharge system as described above for large-scale pool type natrium cold fast reactor asymmetric arrangement, its
In, the front end of the sodium import of described sodium-air heat exchanger is provided with sodium surge tank.
Further, accident afterheat discharge system as described above for large-scale pool type natrium cold fast reactor asymmetric arrangement, its
In, described independent heat exchanger and respectively there are two respectively through heat exchanger.
Further, accident afterheat discharge system as described above for large-scale pool type natrium cold fast reactor asymmetric arrangement, its
In, described independent heat exchanger and it is respectively positioned on through heat exchanger in the sodium pond of the reator body of pool fast reactor.
Further, accident afterheat discharge system as described above for large-scale pool type natrium cold fast reactor asymmetric arrangement, its
In, the outside of described sodium-air heat exchanger, which is provided with, pulls out wind and smoke chimney.
Beneficial effects of the present invention are as follows：The present invention is important passive ad hoc as being used for one of large-scale pool fast reactor
Safety devices, are arranged in the reator body of reactor, and the closure of residual heat removal loop is realized by a variety of paths.The present invention is adopted
The discharge of residual heat of nuclear core is realized with passive operation principle, effectively alleviates accident process, it is ensured that the safety of reactor.
Brief description of the drawings
Fig. 1 is the structural representation of the accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement；
Fig. 2 is independent heat exchanger and the arrangement schematic diagram through heat exchanger.
Embodiment
The present invention is described in detail with reference to the accompanying drawings and examples.
Accident afterheat discharge system provided by the present invention is arranged in fast reactor primary Ioops system, and residual heat removal system is main
By the independent heat exchanger in hot sodium pond, between cold and hot plenums run through heat exchanger, intermediate loop pipeline and
Sodium-air heat exchanger composition outside reator body.As shown in figure 1, independent heat exchanger 1 and distinguishing through heat exchanger 4
The sodium-air heat exchanger 5 for being arranged on out-of-pile is connected by pipeline, the position of described sodium-air heat exchanger 5 is higher than
The independent heat exchanger 1 and through heat exchanger 4, the front end of the sodium import of sodium-air heat exchanger 5 is provided with sodium surge tank 6,
The outside of sodium-air heat exchanger 5 is provided with and pulls out wind and smoke chimney 7.
Under accidental conditions, independent heat exchanger in hot sodium pond, the entry design through heat exchanger are normally closed
Formula, sodium has a small amount of sodium to enter import in hot sodium pond, so, due to the effect of the huge temperature difference inside and outside heap, intermediate loop
Inside still there are some flows, but it is very faint, it is ensured that and the major heat in sodium pond is used for the power generation of reactor, embodies normal
The economy of operation.
And under accident conditions, the device will realize reactor core heat to the transmission in hot sodium pond, hot sodium pond passes through independent heat
The carry out heat transfer of air heat exchanger of the exchanger to outside reactor, and final heat is to the transmission of ultimate heat sink-air
Process.Independent heat exchanger and heated sodium is carried out in the heat exchange of sodium-sodium, heat exchanger tube respectively in heat exchanger through piping
Into sodium-air heat exchanger, sodium-air heat exchange is carried out in sodium-air heat exchanger (i.e. air cooler).Asymmetric arrangement
The setting of residual heat removal system device, will automatically carry out under accident conditions, and flow and have in the box by reactor fuel component
Flowed between the box of effect, discharge residual heat of nuclear core, effectively alleviate accident process, it is ensured that the safety of reactor.
Accident afterheat discharge system is made up of four sets of independent cooling loops, and every suit is by the independence in hot sodium pond
Heat exchanger or sodium-air heat exchanger, connecting pipe and corresponding accessory system outside heat exchanger, containment
Composition.Every suit system includes sodium loop, secondary sodium loop (intermediate loop) and air loop, and they are all to rely on nature
Circulate, residual heat of nuclear core is discharged to ultimate heat sink-atmospheric environment.As shown in Figure 1.
Independent heat exchanger is arranged on the external zones in hot sodium pond.The flowing road of the primary Ioops sodium of accident afterheat discharge system
Footpath, the sodium exported from independent heat exchanger is first had to through the perforate on biological shielding support tube, and thereafter, part sodium sinks
To the ring cavity of bottom biological shielding, this part sodium continues to flow downward until ring cavity bottom.Then, it is horizontally through successively in ring cavity
Shielding cylinder, small screen gap, finally flow through from fuel assembly box gap, enter hot sodium from reactor core top (fuel assembly head)
Pond.Into the sodium through heat exchanger, cold drop is reached after cooling, and reactor fuel component is entered by size grid plate header
In box.After being cooled down in box, finally hot sodium pond is entered through fuel assembly head outlet.Such one of accident afterheat discharge system
Secondary sodium constitutes open type, circulation route with two parallel branches.
Accident afterheat discharge system secondary circuit is a loop, it by independent heat exchanger or through heat exchanger,
Sodium-air heat exchanger and return (the being divided into heat pipe section and cold leg) composition for connecting them.Go out from independent heat exchanger
The secondary sodium (hot sodium) of mouth arrives air cooler expansion tank through heat pipe section, each heat-transfer pipe is then tapped off, heat-transfer pipe comes out to air cooler
Lower header, then converged by header and return to independent heat exchanger into cold leg and constitute a closed circuit.More than accident
There is no the active components such as pump or control valve in the runner of first and second sodium loop of hot discharge system.Three loops are open circuits,
Air is entered by sodium-air heat exchanger inlet damper, by ligament, the export the breeze door of conducting heat, is finally discharged to by pulling out wind and smoke chimney
Air.
In the present invention, so-called asymmetric arrangement, the immersion for referring mainly to arrange in 4 loops of pool fast reactor is changed
Hot device, two of which is arranged in hot pond, and two other is arranged between cold and hot pond.As shown in Figure 2.
The core element of the system be mounted in independent heat exchanger in reator body and arrangement between cold and hot plenums
Through heat exchanger, two of which, which is arranged on, to be specially arranged in hot sodium pond, and two other is arranged between cold and hot plenums
's.
When occurring accident, the inlet baffle through heat exchanger between cold and hot plenums of independent heat exchanger and arrangement
Open, hot sodium enters heat exchanger.The sodium for wherein flowing through independent heat exchanger sinks to the gap of fuel assembly in hot sodium pond
It is interior, form flowing between box；The sodium in heat exchanger that runs through flowed through between cold and hot plenums forms path in the box of fuel assembly, is formed
Flowed in box.Between box the cooling being collectively forming to fuel assembly is flowed in flowing and box.So, the cooling of both fuel assemblies
Mode can be realized in the present invention, can ensure the safety of reactor to greatest extent.
Obviously, those skilled in the art can carry out the essence of various changes and modification without departing from the present invention to the present invention
God and scope.So, if these modifications and variations to the present invention belong to the model of the claims in the present invention and its equivalent technology
Within enclosing, then the present invention is also intended to comprising including these changes and modification.
Claims (4)
1. a kind of accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement, including be arranged in hot sodium pond
Independent heat exchanger (1), be arranged between cold and hot plenums and run through heat exchanger (4), described independent heat exchanger (1) and
Connect the sodium-air heat exchanger (5) for being arranged on out-of-pile, described sodium-sky by pipeline respectively through heat exchanger (4)
The position of gas-heat exchanger (5) is higher than the independent heat exchanger (1) and through heat exchanger (4)；Under accidental conditions,
Independent heat exchanger in hot sodium pond, the entry design through heat exchanger are normally closed type；When occurring accident, described is only
Vertical heat exchanger (1) and the inlet baffle opening through heat exchanger (4), hot sodium enter independent heat exchanger (1) and penetration heat
Exchanger (4), the sodium for flowing through independent heat exchanger is sunk in the gap of fuel assembly in hot sodium pond, forms flowing between box；
The sodium flowed through through heat exchanger forms path in the box of fuel assembly, is formed in box and flowed.
2. being used for the accident afterheat discharge system of large-scale pool type natrium cold fast reactor asymmetric arrangement as claimed in claim 1, it is special
Levy and be：The front end of the sodium import of described sodium-air heat exchanger (5) is provided with sodium surge tank (6).
3. being used for the accident afterheat discharge system of large-scale pool type natrium cold fast reactor asymmetric arrangement as claimed in claim 1, it is special
Levy and be：Described independent heat exchanger (1) and respectively there are two respectively through heat exchanger (4).
4. being used for the accident afterheat discharge system of large-scale pool type natrium cold fast reactor asymmetric arrangement as claimed in claim 1, it is special
Levy and be：The outside of described sodium-air heat exchanger (5) is provided with and pulls out wind and smoke chimney (7).
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| CN201410767394.3A CN104575635B (en) | 2014-12-12 | 2014-12-12 | A kind of accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement |
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| CN201410767394.3A CN104575635B (en) | 2014-12-12 | 2014-12-12 | A kind of accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement |
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| CN107516550A (en) * | 2016-06-16 | 2017-12-26 | 泰拉能源有限责任公司 | Reactor lid |
| CN109637683A (en) * | 2018-10-31 | 2019-04-16 | 中国核电工程有限公司 | A kind of three circuit system of fast reactor nuclear power plant |
| CN109817355B (en) * | 2018-12-29 | 2020-12-11 | 中核霞浦核电有限公司 | Cylinder sodium-gas integrated heat exchanger |
| CN109830316A (en) * | 2019-02-22 | 2019-05-31 | 华北电力大学 | A kind of passive accident afterheat discharge system of sodium-cooled fast reactor intermediate loop |
| CN109883237B (en) * | 2019-03-15 | 2020-03-24 | 中国原子能科学研究院 | Independent heat exchanger of pool type sodium-cooled fast reactor accident waste heat discharge system |
| CN110517796A (en) * | 2019-07-08 | 2019-11-29 | 华北电力大学 | A kind of improved passive residual heat removal system |
| CN111128410B (en) * | 2019-12-31 | 2022-07-26 | 中国核动力研究设计院 | Heat pipe reactor system and energy conversion mode thereof |
| CN113539529B (en) * | 2021-06-17 | 2023-11-14 | 中国核电工程有限公司 | Pool type reactor waste heat discharging system and method |
| CN113674882A (en) * | 2021-07-15 | 2021-11-19 | 中国核动力研究设计院 | Immersion type passive waste heat discharging system and method for lead bismuth pile |
| CN116344074B (en) * | 2023-01-03 | 2023-10-27 | 中国原子能科学研究院 | Top shield structure for reactor |
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