CN105427900B - Reactor fusant out-pile gaseous-waste holdup system after a kind of major accident - Google Patents
Reactor fusant out-pile gaseous-waste holdup system after a kind of major accident Download PDFInfo
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- CN105427900B CN105427900B CN201510918964.9A CN201510918964A CN105427900B CN 105427900 B CN105427900 B CN 105427900B CN 201510918964 A CN201510918964 A CN 201510918964A CN 105427900 B CN105427900 B CN 105427900B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- 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
-
- 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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
-
- 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)
Abstract
The present invention relates to reactor safety system designing techniques, and in particular to reactor fusant out-pile gaseous-waste holdup system after a kind of major accident.Its structure includes fusant arresting device and cooling line, the fusant arresting device being located at below pressure vessel as key equipment, including the porous sacrificial layer and high-temperature crucible construction package for allowing fusant layering diffusion and coolant to pass through, high temperature resistant support column is distributed between each layer as support;Cooling line can continue the cooling water in supplement reactor pit, guarantee flooding and persistently cooling down completely for fusant.When nuclear power station generation reactor core melts the major accident ruined, the present invention can be realized reactor core fusant utmostly and quickly and effectively dispersion cooling, so that reactor pit bottom burn through risk is reduced, the safety under raising reactor disaster.
Description
Technical field
The present invention relates to reactor safety system designing techniques, and in particular to reactor fusant heap after a kind of major accident
Outer gaseous-waste holdup system.
Background technique
China is being built and in running large-scale two generations modified nuclear power plant at present, most not set effective out-piles meltings
Object gaseous-waste holdup system.After Fukushima, Japan accident, nuclear plant safety problem is more urgent especially for the prevention and alleviation of major accident
It cuts.At present under major accident, the cooling of reactor core fusant and delay strategy can be divided mainly into two kinds: 1) melting in pressure vessel
Cooling and holding (IVR) for melting object are applied in the AP-1000 type design of US Westinghouse company;2) outside pressure vessel
Fusant is cooling and collects (EVR), in the advanced pressurized water reactor EPR that the VVER-1000 type and France ANP of Russia's design design
It is applied in type.For out-pile cooling strategy, it is non-that Russian VVER-1000 " crucible " formula trap combines AP600
The design feature and European advanced pressurized water reactor reactor core catcher of the cooling fusant inclusion body metal surface of active water supply pass through sacrifice
Material improves fusant characteristic and reduces the technical characterstic of heat flow density;The design of ANP " extension " formula reactor core catcher of France
Thinking is to flow directly into fusant in reactor pit, fusant and reactor pit sacrifice concrete under high temperature action
Reaction is learned, sacrificial concrete is gradually melted, reaches preliminary function that is cooling, collecting fusant, and entire chemical reaction process exists
The protection of reactor pit protective layer is lower to be carried out, it is ensured that fusant will not penetrate reactor pit and enter structural concrete, to control nuclear radiation diffusion.
The country also has related patents to appear in the newspapers about the research of reactor core catcher, such as I, II, IV type bottom of Shanghai Institute of Nuclear Engineering
It is open jet chimney wall type reactor core melt retention device (CN103377724A, CN103377723A, CN103377720A), tool
There are the reactor core catcher (CN103081023A) of integrated cooling duct, the external cooling large-scale passive nuclear power of bottom water injection superposition
Factory's reactor core catcher (CN103177778A) and the large-scale passive PWR nuclear power plant reactor core trapping for having fusant propagation chamber
Device (CN103165198A) etc..
But technology disclosed in the above patent application is all designed without reference to the permeable delay disk of coolant, also without real
Existing fusant successively shares cooling design under controlled condition, thus can research and develop cooling capacity based on above-mentioned thinking
Stronger, safety is detained more efficient reactor core melt retention technology.
Summary of the invention
It is an object of the invention to the needs for nuclear plant safety design, and reactor melts after providing a kind of major accident
Object out-pile gaseous-waste holdup system, nuclear power station occur reactor core melt the major accident ruined when, can be realized reactor core fusant utmostly and
Quickly and effectively dispersion cooling improves the safety under reactor accident to reduce reactor pit bottom burn through risk.
Technical scheme is as follows: reactor fusant out-pile gaseous-waste holdup system after a kind of major accident, including setting
The fusant arresting device of reactor pit bottom and the cooling line from stand-by water source, described below reactor pressure vessel
Fusant arresting device can accept all fusant jet streams fallen in reactor pressure vessel drop shadow spread, wherein described
Fusant arresting device include high-temperature crucible that multilayer allows fusant and coolant to penetrate, on every layer of high-temperature crucible
Equipped with the porous sacrificial layer that can be melted object burn through.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein adjacent two layers is resistance to
The high temperature resistant support column of connection and supporting role has been equipped between high-temperature crucibles.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein adjacent two layers
There are the free spaces that height is 40-60cm between high-temperature crucible.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein in addition to the bottom
Every layer of high-temperature crucible be equipped with array be distributed and the staggered recirculation hole of interlayer, the porous sacrificial layer is with 20-
The thickness of 30cm is laid in the upper surface of every layer of high-temperature crucible.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein the resistance to height
Warm crucible is disk-like structure, and middle part is smooth collecting region, and outer rim tilts 10-30 degree and forms shield weir, the recirculation hole setting
Recirculation hole on the middle part collecting region of high-temperature crucible, adjacent two layers high-temperature crucible, which misplaces, to be arranged.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein described is porous sacrificial
Domestic animal layer is the cavernous structure being process by sintering process, porosity 0.1-0.3;Battle array is equipped at the middle part of porous sacrificial layer
The delay hole and delay hole of column distribution.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein described is porous sacrificial
The fusion temperature of domestic animal layer is 1500-2000 DEG C, and the fusion temperature of the high-temperature crucible and high temperature resistant support column is at 2800 DEG C
More than.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein the cooling tube
Two column are arranged altogether and are equipped with pump valve for line, respectively waterflood-transmission line in out-pile waterflood-transmission line and heap;The out-pile waterflood-transmission line
Outlet is located at reactor pit bottom, for supplying water into reactor pit;The outlet of waterflood-transmission line is connected with pressure vessel in the heap, is used for
It supplies water into reactor pressure vessel.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein the cooling tube
The coolant flow that line provides through fusant arresting device, coolant rapid osmotic enter among the gap of porous sacrificial layer realize it is cold
But function.
Further, reactor fusant out-pile gaseous-waste holdup system after major accident as described above, wherein when occurring in reactor pit
Fusant and coolant interact, when temperature and pressure are more than certain threshold value, the reactor pit ventilating system superpressure explosion dress of configuration
It sets automatic-explosion pressure release, prevents reactor pit concrete partition from damaging.
Beneficial effects of the present invention are as follows: (1) the plate-like high-temperature crucible that the present invention designs, can be by the high-temperature fusion of undertaking
Object is made thinner, to increase heat exchange area, and successively shares cooling, reduces the risk that hot-fluid is concentrated;(2) present invention uses multilayer earthenware
The design of crucible through-hole dislocation arrangement can effectively carry out fusant shunting and three-dimensional distribution;(3) present invention passes through two column cooling lines
It cools down in heap with the fusant of out-pile, to reactor fusant out-pile arresting device, while realizing from bottom to top simultaneously
Flood with two kinds of types of cooling of top-down spray, increase the reliability of system.
Detailed description of the invention
Fig. 1 is reactor fusant out-pile gaseous-waste holdup system layout drawing;
Fig. 2 is fusant arresting device structural schematic diagram;
Fig. 3 is fusant arresting device sectional view (sacrificial layer, high-temperature crucible lead to the hole site schematic diagram).
Specific embodiment
The present invention is described in detail below with reference to the accompanying drawings and embodiments.
The present invention provides reactor fusant out-pile gaseous-waste holdup system after a kind of major accident, arragement construction such as Fig. 1 institutes
Show, arranges including the fusant arresting device of 7 bottom of reactor pit and two below reactor pressure vessel 5 is arranged in from stand-by water source
Cooling line 1,2.Fusant arresting device include multilayer allow fusant and coolant to penetrate high-temperature crucible 9 (most
Except bottom 11), the components such as porous sacrificial layer 8 and high temperature resistant support column 10 are set on high-temperature crucible 9, are arranged in reactor
Immediately below pressure vessel 5, all fusant jet streams fallen in reactor pressure vessel drop shadow spread can be accepted.Two column coolings
Pipeline is equipped with pump valve, fetches water from the stand-by water source that power station is provided for oneself, under emergency conditions, water injection pipe in out-pile waterflood-transmission line 2 and heap
Line 1 supplies water into reactor pit 7 and reactor pressure vessel 5 respectively, out-pile waterflood-transmission line 2 by water from 7 bottom of reactor pit inject, for by
Gradually flood fusant arresting device;Waterflood-transmission line 1 injects water directly into reactor pressure vessel 5 in heap, for cool down reactor core with
And the methods for cooling to the similar spray of offer at the top of fusant arresting device.When generation fusant and cooling water phase interaction in reactor pit
With when temperature and pressure are more than certain threshold value, the reactor pit ventilating system superpressure demolition set 3 of configuration prevents automatic-explosion pressure release
Only reactor pit concrete partition 4 damages.
Fusant arresting device provided by the present invention is multilayered structure, as shown in Figure 2 and Figure 3, between every layer of structural unit
It is connected and supported by high temperature resistant support column 10, there are the free spaces of 40-60cm between adjacent two layers structural unit.Porous sacrifice
The fusion temperature 1500-2000 degree of layer 8, and high-temperature crucible 9,11 upper surfaces are laid in the thickness of 20-30cm;Described is resistance to
High-temperature ceramic materials can be used at 2800 degree or more in high-temperature crucibles 8 and the fusion temperature of high temperature resistant support column 10.Except the bottom with
The high-temperature crucible 9 of outer every layer is equipped with array distribution and the staggered recirculation hole 12 of interlayer, adjacent two layers high temperature resistant earthenware
Recirculation hole 12 on crucible, which misplaces, to be arranged, the high-temperature crucible positioned at bottommost is non-porous crucible.High-temperature crucible and thereon more
Hole sacrificial layer body shape is disk-like structure, and outer rim tilts 10-30 degree and forms shield weir, and middle part is smooth collecting region, described
The middle part collecting region of high-temperature crucible is just arranged in recirculation hole 12.What the middle part of the porous sacrificial layer was distributed there are array
It is detained hole 13 and is detained hole 14.Porous sacrificial layer is process by sintering process, is porous cavernous structure, porosity
0.1-0.3, can permit coolant rapid osmotic into porous sacrificial layer cavernous structure gap among realize refrigerating function.
Nuclear plant severe accident occurs for reactor fusant out-pile gaseous-waste holdup system after major accident provided by the present invention
When, according to the instruction of operator, cooling system operation can be to fusant by way of respectively into heap with out-pile water filling
The dual-cooled from upper and lower part is formed, promotes it to solidify and is detained and final long-term cooling.
As shown in Figure 1, falling into the top layer of reactor fusant out-pile arresting device after reactor core fusant burn through lower head 6
It is detained unit, high-temperature molten under the effect of gravity, can make thinner in the catching device of plate-like, to increase heat exchange area, make
It obtains cooling effect and solidification is detained function and is easier to efficiently reach.
As shown in Fig. 2, what is contacted first is porous sacrificial layer 8 when a large amount of high-temperature molten initially falls into arresting device,
On the one hand, the cooling water permeated in spongiform porous sacrificial layer 8 can effectively cool down to fusant, promote its solidification knot
On the other hand shell has the regional area of excessive high-temperature molten in accumulation, sacrificial layer material (such as iron oxide or aluminium oxide or
The mixture of the two) can by fuse itself absorb amount of heat, and ensure temperature lower than high-temperature crucible design temperature with
It is interior, it is ensured that the integrality of its structural strength and device geometric format.
As shown in figure 3, the excess molten object of corresponding position will pass through burn through when the sacrificial layer 8 when top is fused
Duct flows on the sacrificial layer of next layer unit structure, is shakeout and is cooled down for the second time.Since the porous sacrificial layer of lower layer is set
Delay hole 13 and delay hole 14 in respect of array arrangement, fusant is by the controlled top for being assigned to this layer of high-temperature crucible 9, such as
Fruit still has the fusant of regional area that cannot be adequately cooled and be detained in this layer, then the fusant for corresponding to share can be after
Continuous burn through sacrificial layer 8, and migrated along the preset recirculation hole 12 of high-temperature crucible 9 to next layer of expansion structure.Pass through rational design
Through-hole opens up position and diameter on the cladding thickness and high-temperature crucible of sacrificial layer, by the through-hole arrangement side to misplace up and down
Controllable is all shared the design being detained to next layer, this multilayer, both extended by formula, the fusant that each layer heap product is excessively concentrated
Residence time, and uniformly redistributed for the three-dimensional space of heat source and provide feasible way, in this way, it can will finally melt
Melt object safely and efficiently to solidify delay and long-term cooling is provided.
In addition, the high-temperature crucible 11 that the structural unit of the bottom is equipped with is non-porous design in multilayer arresting device, with
Ensure in extreme circumstances, even if fusant can break through heavy barrier and reach the last layer retention structure unit, remains to by whole
It is included among designed fusant arresting device, interacts without the concrete floor with containment, generates
More security risks.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
Mind and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention
Within enclosing, then the present invention is also intended to include these modifications and variations.
Claims (9)
1. reactor fusant out-pile gaseous-waste holdup system after a kind of major accident, including setting is below reactor pressure vessel (5)
The fusant arresting device of reactor pit (7) bottom and cooling line from stand-by water source, the fusant arresting device energy
Enough accept all fusant jet streams fallen in reactor pressure vessel (5) drop shadow spread, it is characterised in that: the fusant
Arresting device includes the high-temperature crucible (9,11) that multilayer allows fusant and coolant to penetrate, two layers adjacent of high-temperature crucible
Between be equipped with connection and supporting role high temperature resistant support column (10), on every layer of high-temperature crucible be equipped with can be melted object
The porous sacrificial layer (8) of burn through, the porous sacrificial layer (8) are the cavernous structure being process by sintering process.
2. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: adjacent two
There are the free spaces that height is 40-60cm between layer high-temperature crucible.
3. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: remove the bottom
The every layer in addition high-temperature crucible (9) is equipped with array distribution and the staggered recirculation hole of interlayer (12), and described is porous
Sacrificial layer is laid in the upper surface of every layer of high-temperature crucible with the thickness of 20-30cm.
4. reactor fusant out-pile gaseous-waste holdup system after major accident as claimed in claim 3, it is characterised in that: described is resistance to
High-temperature crucibles (9,11) are disk-like structure, and middle part is smooth collecting region, and outer rim tilts 10-30 degree and forms shield weir, the stream
The middle part collecting region in high-temperature crucible (9) is arranged in through-hole (12), recirculation hole (12) dislocation on adjacent two layers high-temperature crucible
Arrangement.
5. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: described is more
The porosity of hole sacrificial layer (8) is 0.1-0.3;The delay hole (13) of array distribution is equipped at the middle part of porous sacrificial layer (8)
(14) are cheated with being detained.
6. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: described is more
The fusion temperature of hole sacrificial layer (8) is 1500-2000 DEG C, the high-temperature crucible (9,11) and high temperature resistant support column (10)
Fusion temperature is at 2800 DEG C or more.
7. reactor fusant out-pile gaseous-waste holdup system, feature exist after major accident as claimed in any one of claims 1 to 6
In: two column are arranged altogether and are equipped with pump valve for the cooling line, respectively waterflood-transmission line (1) in out-pile waterflood-transmission line (2) and heap;
The outlet of the out-pile waterflood-transmission line (2) is located at reactor pit (7) bottom, for supplying water into reactor pit (7);Water filling in the heap
The outlet of pipeline (1) is connected with pressure vessel (5), for supplying water into reactor pressure vessel (5).
8. reactor fusant out-pile gaseous-waste holdup system after major accident as claimed in claim 7, it is characterised in that: the cooling
Through fusant arresting device, coolant rapid osmotic enters among the gap of porous sacrificial layer to be realized the coolant flow that pipeline provides
Refrigerating function.
9. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: work as reactor pit
(7) fusant occurs in and coolant interacts, when temperature and pressure are more than certain threshold value, the reactor pit ventilating system of configuration is super
It presses demolition set (3) by automatic-explosion pressure release, prevents reactor pit concrete partition (4) from damaging.
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Families Citing this family (11)
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JP6727690B2 (en) * | 2016-11-17 | 2020-07-22 | 日立Geニュークリア・エナジー株式会社 | Core melt holding device |
CN108053895B (en) * | 2017-11-06 | 2021-06-25 | 中国核电工程有限公司 | Reactor core melt trapping device for split-charging enhanced cooling |
CN108538411B (en) * | 2018-03-08 | 2021-06-25 | 中国核电工程有限公司 | Reactor core melt trapping device for direct pit retention |
CN108550406B (en) * | 2018-03-16 | 2020-05-05 | 中国核电工程有限公司 | Reactor core melt trapping device |
RU2696612C1 (en) * | 2018-12-26 | 2019-08-05 | Акционерное Общество "Атомэнергопроект" | Melt localization device |
CN109948296A (en) * | 2019-04-09 | 2019-06-28 | 中国核动力研究设计院 | Fusant is cooling in a kind of lower head is detained efficiency evaluation method |
CN110391030B (en) * | 2019-06-27 | 2023-12-15 | 中国核电工程有限公司 | Partitioned crucible melt out-of-pile catcher |
CN112700892B (en) * | 2020-12-15 | 2023-11-14 | 中国核电工程有限公司 | Multiple defence and refrigerated reactor core catcher |
CN113506646B (en) * | 2021-05-25 | 2022-08-23 | 上海交通大学 | Method and device for judging geometric structure of reactor core node in reactor core melting process |
CN114005555B (en) * | 2021-10-22 | 2024-02-20 | 中国原子能科学研究院 | Reactor and reactor core melt collecting device thereof |
CN115662662B (en) * | 2022-09-09 | 2023-06-13 | 中国核动力研究设计院 | Reactor core melt trapping cooler and parameter calculation method thereof |
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