CN107622803A - A kind of cold drop runner that can effectively lift pool Lead cooled fast breeder reactor security - Google Patents
A kind of cold drop runner that can effectively lift pool Lead cooled fast breeder reactor security Download PDFInfo
- Publication number
- CN107622803A CN107622803A CN201710946849.1A CN201710946849A CN107622803A CN 107622803 A CN107622803 A CN 107622803A CN 201710946849 A CN201710946849 A CN 201710946849A CN 107622803 A CN107622803 A CN 107622803A
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- CN
- China
- Prior art keywords
- cold drop
- orifice plate
- lead
- fast breeder
- cooled fast
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- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Classifications
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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
Abstract
The present invention provides a kind of cold drop runner that can effectively lift pool Lead cooled fast breeder reactor security, relies primarily on the secondary orifice plate that separates of cold drop and realizes.The secondary orifice plate that separates of cold drop is made up of horizontal segment orifice plate and vertical section orifice plate, and its thickness is identical with hot demarcation strip.The secondary delay for separating orifice plate to Lead coolant when horizontal segment perforate is to prevent that free surface from declining.It is circumferentially distributed to adjust the perforate of vertical section outlet port orifice plate, makes equably to flow out in lead circumference, allows the more lead of cold drop to participate in overall flow, plays lead pond thermal inertia security advantages to a greater degree, further lifts the passive safety of Lead cooled fast breeder reactor.When cut occurs in main heat exchanger heat exchanger tube, new cold drop runner design causes cold drop to have the more time to carry out gas-liquid separation, reduces to a greater degree by lead entrainment into the water vapour amount of reactor core, avoids excessive positive reactivity from introducing.A kind of structure maltilevel security function of the present invention, simplifies Lead cooled fast breeder reactor system design, can effectively improve Lead cooled fast breeder reactor security and economy.
Description
Technical field
The invention belongs to Lead cooled fast breeder reactor design field, and in particular to one kind can effectively lift pool Lead cooled fast breeder reactor safety
Property cold drop runner, purpose of design be improve pool Lead cooled fast breeder reactor coolant flowpaths, improve pool Lead cooled fast breeder reactor non-energy
Dynamic security, ensure security of the Lead cooled fast breeder reactor in accident conditions (after especially main heat exchanger heat exchanger tube cut occurs).
Background technology
As one of six kinds of typical heap-type of the 4th generation of technology such as nuclear energy system, Lead cooled fast breeder reactor is because it is in terms of security and economy
Outstanding advantage, be one of main focus of international Advanced Nuclear Energy Systems research.Moreover, Lead cooled fast breeder reactor was in forth generation core in 2013
It can be chosen as most being hopeful at first into the forth generation reactor heap-type of demonstration phase in system forum renewal route map.Lead is cold fast
Heap generally use pool arranges that primary Ioops key equipment is arranged in reactor coolant, simple in construction, is farthest subtracted
Number of conduits is lacked, the possibility lost cold accident and occurred even is eliminated so as to dramatically reduce.
Typical pool Lead cooled fast breeder reactor can be divided into four main regions：Core region, Re Chi, heat exchanger zones and cold drop.Allusion quotation
Type pool Lead cooled fast breeder reactor can be divided into Natural Circulation Lead cooled fast breeder reactor and forced circulation Lead cooled fast breeder reactor two types by endless form.Force
Circulating Lead cooled fast breeder reactor is flowed under the common driving effect of pump and Natural Circulation drive ram, and Natural Circulation Lead cooled fast breeder reactor is then
Fully rely on Natural Circulation drive ram and realize flowing.
Compared to water-water reactor, the melting temperature of the pure lead of Lead cooled fast breeder reactor primary Ioops is higher.Therefore in order to leave more than enough safety
Amount, the temperature of main heat exchanger secondary side entrance subcooled water is sufficiently high, so as to prevent Lead coolant from solidifying.This is required two times
Road water saturation temperature is sufficiently high, i.e., Lead cooled fast breeder reactor secondary coolant circuit system pressure is sufficiently high.It is main at present in order to reach this requirement
Lead cooled fast breeder reactor secondary side water loop system running pressure design load is flowed in 18MPa or so.Simultaneously as Lead coolant boiling point is very
Height, Lead cooled fast breeder reactor primary Ioops system running pressure design load are generally near atmospheric pressure (0.1MPa or so).Primary Ioops and secondary circuit
Operating pressure difference is so big, once cut occurs in main heat exchanger heat exchanger tube, a large amount of secondary circuit water under high pressures can quickly enter one
Loop.The water under high pressure or high-pressure water vapor of secondary circuit can be depressured heating and are changed into gaseous state after entering primary Ioops, may be by lead
Cooling agent entrainment enters reactor core by main pump (forced circulation Lead cooled fast breeder reactor), introduces positive reactivity to reactor core so as to cause accident to be sent out
It is raw.
Certainly, Lead coolant has good physical property and chemical property, can effectively alleviate main heat exchanger heat exchanger tube
The accident that cut triggers.For example Lead coolant density is more much bigger than aqueous water, and lead chemical property torpescence.Therefore, exist
During water vapour is carried secretly by lead, due to lead water (water vapour) density contrast formed buoyancy can make it that water vapour is quick on
Rise, eventually enter into the blanket gas space on the free surface of lead pond.But from heat exchanger primary side export to reactor core entrance away from
From very short (as shown in Figure 1), do not ensure that the vapor of Lead coolant entrained with can be before Lead coolant enters reactor core
It is effectively separated away.It is therefore desirable to set a structure that can strengthen primary Ioops cold drop gas-liquid separation ability or portion
Part, reduce the consequence that accident occurs, while optimization (should not at least deteriorate) primary Ioops flowing heat transfer characteristic as far as possible.
Another performance deficiency of pool Lead cooled fast breeder reactor typical scenario cold drop structure is：Lead coolant is from heat exchanger outlet
To between core inlet, it, which is not flowed, by cold drop part is influenceed, and exports to reactor core from heat exchanger primary side
The distance of entrance is very short, thus the cooling agent flowing in cold drop is only limited to from heat exchanger exit to reactor core entrance very small part area
Domain.In this case, in cold drop region there is a large amount of low flow velocity regions, many cooling agents in cold drop are not effectively
Participate in primary Ioops cooling agent flowing heat transfer.That is, the thermal inertia corresponding to primary Ioops lead loading amount can not be by effective profit
With this will be highly detrimental to the security of Lead cooled fast breeder reactor.
Therefore the flow passage structure of primary Ioops cold drop is improved, strengthens the utilization to lead loading amount thermal inertia advantage, it is cold fast to improve lead
The security in accident conditions (especially after main heat exchanger heat exchanger tube cut) is piled up, is that very important technological innovation considers
Point.
The content of the invention
The technical problem to be solved in the present invention is：Overcome the shortcomings of existing Lead cooled fast breeder reactor design, there is provided one kind can be carried effectively
Rise the cold drop runner design of pool Lead cooled fast breeder reactor security.By improving and optimizating cold drop runner design, optimize in normal conditions
Coolant flow speed is distributed, and cold drop low flow velocity region is reduced, so as to optimize performance of the reactor in coolant purification etc..Just
Under normal shutdown condition and ordinary accident operating mode, the security advantages that primary Ioops lead loading amount is brought greatly are played to a greater degree, using more
More effective thermal inertias (effectively refer to the limitation because coolant flow field distribution, total heat corresponding to reactor coolant gross mass
Inertia can only partly be used effectively), so as to slow down accident transient process to a greater degree, further optimize reactor safety
Characteristic.When the accident for including main heat exchanger heat exchanger tube cut occurs, by increasing flowing time of the cooling agent in cold drop
And flow-path-length, it is cold by lead so as to reduce to a greater degree so as to effectively strengthen gas (water) liquid (lead) separation in cold drop
But agent entrainment avoids main heat exchanger heat exchanger tube cut, to avoid positive reactivity from introducing then as far as possible into the quantity of steam of reactor core
Trigger major accident.
The present invention solve the technical scheme that uses of above-mentioned technical problem for：One kind can effectively lift pool Lead cooled fast breeder reactor safety
Property cold drop runner, cold drop runner rely primarily on newly-increased cold drop it is secondary separate orifice plate realize, cold drop it is secondary separate orifice plate by water
Flat sector hole plate and vertical section orifice plate composition, the thickness of orifice plate and use material and hot demarcation strip all same, and the secondary separation orifice plate of cold drop exists
It is used to separate heat exchanger outlet and cooling agent core inlet in cold drop, so as to form new cold drop coolant flow passages, cooling agent
After heat exchanger outflow, reactor core entrance is no longer flowed directly into, but flow straight up along the secondary orifice plate elder generation that separates of cold drop
It is dynamic, flowed straight down in the secondary circular passage separated between orifice plate and reactor vessel of cold drop cold drop afterwards, Ran Houcai
Into reactor core.
Wherein, opening diameter and the equal very little of number on the horizontal segment orifice plate, can be neglected relative to vertical section coolant outlet
Slightly disregard.
Wherein, opening diameter and number gradually increase the vertical section orifice plate from top to bottom, vertical section generally cylinder,
The generally more cylindrical sections of hot demarcation strip, and vertical section diameter is identical with hot demarcation strip maximum gauge.
Wherein, the vertical section coolant outlet position is still AND DEWATERING FOR ORIFICE STRUCTURE, and the circumferentially upper number of aperture mesh in outlet port and
Diameter distribution can ensure relatively evenly to flow out from outlet port in cooling agent circumference.
The present invention compared with prior art the advantages of be：
(1), compared with existing lead heap designs, the present invention is arranged to lift reactor passive safety and alleviate master and changed
The structure member of hot device heat exchanger tube cut accident, improve the security of reactor.
(2), one aspect of the present invention can more play lead pond thermal inertia security advantages, on the other hand can effectively add
Strong gas-liquid separation, reactor system design can be simplified, improve system reliability, reduce construction cost, improve the economy of reactor
Property.
Brief description of the drawings
Fig. 1 is Lead cooled fast breeder reactor typical scenario reactor general arrangement；
Fig. 2 is Lead cooled fast breeder reactor improvement project reactor general arrangement.
Reference implication is in figure：1 is reactor core, and 2 be main heat exchanger, and 3 be main pump, and 4 be hot demarcation strip, and 5 be cold drop two
Secondary separation orifice plate.
Embodiment
The present invention is further illustrated with reference to the accompanying drawings and detailed description.
As shown in Fig. 2 the present invention provides a kind of cold drop runner design that can effectively lift pool Lead cooled fast breeder reactor security.
The secondary orifice plate 5 that separates of increased cold drop has redesigned cold drop runner on the basis of typical scenario design (as shown in Figure 1).
The cold drop secondary projected life for separating orifice plate 5 using the phase in reactor longevity as reference, need not be changed within the phase in reactor longevity.
The secondary orifice plate 5 that separates of cold drop is used to separate the outlet of main heat exchanger 2 and the import of cooling agent reactor core 1 in cold drop, so as to
Form new cold drop coolant flow passages.Cooling agent no longer flows directly into reactor core entrance after heat exchanger outflow, but along
The secondary orifice plate 5 that separates of cold drop first flows straight up, afterwards between the secondary separation orifice plate 5 of cold drop cold drop and reactor vessel
Flowed straight down in circular passage, then just enter reactor core 1.Which adds flow path of the cooling agent in cold drop,
The more cooling agents of cold drop are forced to participate in the overall flow and Heat transmission of reactor.Meanwhile increase cooling agent in cold drop
In flow path, flowing time of the cooling agent in cold drop can be increased, further strengthen the heat exchanger tube of main heat exchanger 2 there is cut
The gas-liquid separation of cold drop afterwards, reduce as far as possible by Lead coolant entrainment into the steam vapour amount of reactor core 1, avoid positive reactivity from introducing
Accident occurs.
Compared with existing lead heap designs (as shown in Figure 1), the newly-installed secondary separation orifice plate 5 of cold drop both can more effective land productivity
With lead pond thermal inertia advantage, reactor passive safety is lifted, the accident of the heat exchanger tube cut of main heat exchanger 2 initiation can be alleviated again
Consequence, simplify reactor system design, improve the security and economy of reactor.
The secondary orifice plate 5 that separates of cold drop is AND DEWATERING FOR ORIFICE STRUCTURE.Consider the secondary lead corrosion environment separated residing for orifice plate 5 of cold drop and remote
From the neutron irradiation environment of reactor core, its material can select with the hot identical material of demarcation strip 4, such as 316L stainless steels.Orifice plate is thick
Degree is also identical with hot demarcation strip 4.
The secondary orifice plate 5 that separates of cold drop is made up of horizontal segment orifice plate and vertical section orifice plate.Cold drop is secondary to separate the horizontal segment of orifice plate 5
The equal very little of number and diameter in hole, reactor core 1 is flowed directly into by the secondary horizontal segment of orifice plate 5 that separates of cold drop to limit cooling agent
Amount, while the secondary orifice plate that separates of cold drop is avoided when cold drop Lead coolant free surface declines (under nominal situation/accident conditions)
Delay to Lead coolant.(hot demarcation strip is overall with the hot maximum gauge of demarcation strip 4 for vertical section diameter (vertical section generally cylinder)
For more cylindrical sections) it is identical.Perforate number and opening diameter in vertical section gradually increase from top to bottom, and vertical section cooling agent goes out
Mouth is unsuitable too high, need to ensure that the new type of flow of Lead coolant will not produce ill effect to cold drop free surface, i.e., will not
Cause serious free surface to rock, rocked so as to reduce free surface under accident conditions as far as possible to reactor structural material
Influence.
Vertical section coolant outlet is by increasing the secondary aperture separated on the vertical section relevant position of orifice plate 5 of cold drop and reality
Existing, it is integral AND DEWATERING FOR ORIFICE STRUCTURE to ensure whole vertical section, consequently facilitating cold drop separates the connection between orifice plate 5 and hot demarcation strip 4
Connect fixation.Vertical section coolant outlet is in the circumferential by suitably adjusting opening diameter and number distribution, so that cooling agent
More equably it can be flowed out from vertical section coolant outlet, it is whole so as to ensure to have more cold drop cooling agents to participate in reactor
Body flowing heat transfer.So contribute to the flow velocity (mass flow is constant) of reduction cold drop cooling agent, so as to which main heat exchanger 2 be changed
Steam caused by heat pipe cut spatially more dispersedly carries out gas-liquid separation, strengthens separating effect, while can disperse to steam
Vapour causes dynamic load of the Lead coolant to cold drop dependency structure when rising in cold drop.Cold drop is secondary to separate the vertical section of orifice plate 5
The drum diameter surrounded is identical with the Upper vertical section of hot demarcation strip 4, so as to the convenient fixation for separating orifice plate 5 to cold drop.
What the present invention did not elaborated partly belongs to techniques well known.
Although the illustrative embodiment of the present invention is described above, in order to the technology of the art
Personnel understand the present invention, it should be apparent that the invention is not restricted to the scope of embodiment, to the common skill of the art
For art personnel, if various change in the spirit and scope of the present invention that appended claim limits and determines, these
Change is it will be apparent that all utilize the innovation and creation of present inventive concept in the row of protection.
Claims (4)
- A kind of 1. cold drop runner that can effectively lift pool Lead cooled fast breeder reactor security, it is characterised in that：Cold drop runner relies primarily on The secondary orifice plate that separates of newly-increased cold drop realizes that the secondary orifice plate that separates of cold drop is made up of horizontal segment orifice plate and vertical section orifice plate, orifice plate Thickness and with material and hot demarcation strip all same, cold drop is secondary to be separated orifice plate and is used to separating heat exchanger outlet and cold in cold drop But agent core inlet, so as to form new cold drop coolant flow passages, cooling agent no longer flows directly into after heat exchanger outflow Reactor core entrance, but along cold drop it is secondary separate orifice plate first flow straight up, afterwards cold drop cold drop it is secondary separate orifice plate and Flowed straight down in circular passage between reactor vessel, then just enter reactor core.
- 2. the cold drop runner according to claim 1 that can effectively lift pool Lead cooled fast breeder reactor security, it is characterised in that：Institute Opening diameter and the equal very little of number on horizontal segment orifice plate are stated, can be neglected relative to vertical section coolant outlet.
- 3. the cold drop runner according to claim 1 that can effectively lift pool Lead cooled fast breeder reactor security, it is characterised in that：Institute Stating vertical section orifice plate, opening diameter and number gradually increase from top to bottom, and vertical section generally cylinder, hot demarcation strip is generally More cylindrical sections, and vertical section diameter is identical with hot demarcation strip maximum gauge.
- 4. the cold drop runner according to claim 3 that can effectively lift pool Lead cooled fast breeder reactor security, it is characterised in that：Institute It is still AND DEWATERING FOR ORIFICE STRUCTURE to state vertical section coolant outlet position, and the circumferentially upper number of aperture mesh in outlet port and diameter distribution can ensure it is cold But relatively evenly flowed out in agent circumference from outlet port.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710946849.1A CN107622803A (en) | 2017-10-12 | 2017-10-12 | A kind of cold drop runner that can effectively lift pool Lead cooled fast breeder reactor security |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710946849.1A CN107622803A (en) | 2017-10-12 | 2017-10-12 | A kind of cold drop runner that can effectively lift pool Lead cooled fast breeder reactor security |
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| CN107622803A true CN107622803A (en) | 2018-01-23 |
Family
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|---|---|---|---|
| CN201710946849.1A Pending CN107622803A (en) | 2017-10-12 | 2017-10-12 | A kind of cold drop runner that can effectively lift pool Lead cooled fast breeder reactor security |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108665981A (en) * | 2018-07-03 | 2018-10-16 | 启迪新核（北京）能源科技有限公司 | The natural circulation cooling system and well formula normal pressure process heat reactor of well formula normal pressure process heat reactor |
| CN109887623A (en) * | 2019-01-25 | 2019-06-14 | 中广核研究院有限公司 | A kind of pool lead base fast reactor with labyrinth path |
| CN109883237A (en) * | 2019-03-15 | 2019-06-14 | 中国原子能科学研究院 | A kind of independent heat exchanger of pool type sodium cooled fast reactor accident afterheat discharge system |
| CN111503327A (en) * | 2020-03-30 | 2020-08-07 | 中广核研究院有限公司 | Floating valve device, working method thereof and pressure container |
| CN116230264A (en) * | 2023-03-09 | 2023-06-06 | 中国原子能科学研究院 | Reactor and method for operating the same |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN108665981A (en) * | 2018-07-03 | 2018-10-16 | 启迪新核（北京）能源科技有限公司 | The natural circulation cooling system and well formula normal pressure process heat reactor of well formula normal pressure process heat reactor |
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| CN109883237A (en) * | 2019-03-15 | 2019-06-14 | 中国原子能科学研究院 | A kind of independent heat exchanger of pool type sodium cooled fast reactor accident afterheat discharge system |
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| CN111503327A (en) * | 2020-03-30 | 2020-08-07 | 中广核研究院有限公司 | Floating valve device, working method thereof and pressure container |
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| CN116230264A (en) * | 2023-03-09 | 2023-06-06 | 中国原子能科学研究院 | Reactor and method for operating the same |
| CN116230264B (en) * | 2023-03-09 | 2023-10-27 | 中国原子能科学研究院 | Reactor and method for operating the same |
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