CN103377724A - I-shaped reactor external melt retention device used after nuclear power plant accident - Google Patents
I-shaped reactor external melt retention device used after nuclear power plant accident Download PDFInfo
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- CN103377724A CN103377724A CN2012101270155A CN201210127015A CN103377724A CN 103377724 A CN103377724 A CN 103377724A CN 2012101270155 A CN2012101270155 A CN 2012101270155A CN 201210127015 A CN201210127015 A CN 201210127015A CN 103377724 A CN103377724 A CN 103377724A
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- fused mass
- reactor core
- arresting device
- nuclear power
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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 invention relates to an I-shaped reactor external melt retention device used after a nuclear power plant accident. The I-shaped reactor external melt retention device comprises an inner wall, a steam channel wall fixed at an opening in the bottom of the inner side of the inner wall, a pressure container arranged in the steam channel wall, an outer wall surrounding the inner wall, a reactor core melt retention device fixed at the bottom of the inner wall and a reactor core melt cooling device which is positioned below the reactor core melt retention device and fixed above a base plate, wherein a coolant descending channel is formed between the inner wall and the outer wall; a coolant channel is formed between the inner wall and the reactor core melt retention device; a reactor core melt retention groove is formed in the upper surface of the reactor core melt retention device; the lower surface of the reactor core melt retention device is a plane; the reactor core melt retention device is made of an inorganic non-metal fireproof material. By adopting a melt retention design outside a reactor, melts are accommodated by different materials and are cooled by a coolant loop and the reactor core melt cooling device, and therefore, the safety of a nuclear power plant.
Description
Technical field
The present invention relates to I type out-pile fused mass arresting device behind a kind of nuclear power plant accident, particularly relate to fully non-active Cooling Design of a kind of employing reactor core fused mass, improve behind the nuclear power plant accident of nuclear plant safety fully non-active cooling device of reactor core.
Background technology
Fused mass delay technology be nuclear power for an important mitigation strategy of major accident, can effectively solve radioactivity release, keep the complete of secure border.Present generation Ⅲ nuclear power has all adopted the severe accident relieving measure after the pressure vessel breakage.
AP-1000 adopts the gentle measure of separating serious accident of non-active prevention, comprise that mainly the melting reactor core is set is detained facility (IVR), when reactor core thawing accident occurs, when heap chamber flood system is injected water in the heap, the also space between injection pressure container outer wall and the reactor pit heat insulation layer, fall reactor core fused mass on the pressure vessel low head with cooling from reactor core, guarantee that low head is not by burn through, the reactor core fused mass is remained in the reactor pressure vessel, avoid reactor core fused mass and containment concrete floor generation themopositive reaction, prevent so directly the be heated generation of damaged and vapour explosion of containment base plate.In case it should be noted that reactor core fused mass burn through pressure vessel, then IVR is with helpless.Therefore needing badly provides I type out-pile fused mass arresting device behind a kind of novel nuclear power plant accident.
Summary of the invention
The technical problem to be solved in the present invention provides I type out-pile fused mass arresting device behind a kind of nuclear power plant accident that improves the high full property of nuclear power station.
For solving the problems of the technologies described above, I type out-pile fused mass arresting device behind a kind of nuclear power plant accident of the present invention, closed interior wall around comprising, be fixed in the bottom opening of interior wall inboard the steam channel wall, place the pressure vessel within the steam channel wall, form the steam rising passage between pressure vessel and the steam channel wall, also comprise enclose in outside the interior wall be positioned on the base plate around closed exterior wall, the reactor core fused mass cooling device on the base plate of being fixed in that is fixed in the reactor core fused mass arresting device of interior wall bottom and is positioned at reactor core fused mass arresting device below; Form the cooling medium decline passway between interior wall and the exterior wall, be provided with coolant channel between interior wall and the reactor core fused mass arresting device; The position that reactor core fused mass arresting device upper surface is positioned under the pressure vessel is provided with reactor core fused mass delay groove, and reactor core fused mass arresting device lower surface is the plane; Reactor core fused mass arresting device is made of the inorganic non-metallic fire resistive material.
The inorganic non-metallic fire resistive material is acid refractory, neutral refractory, basic refractory or high-temperature composite material.
Acid refractory is monox.
Neutral refractory is aluminium oxide, chromium oxide or graphite.
Basic refractory is magnesium oxide, calcium oxide, lanthana, beryllia or zirconia.
High-temperature composite material is metallic ceramics or fiber reinforced ceramic.
Reactor core fused mass cooling device comprises the adjacent fixing cooling water pipe of some layers, and every layer of cooling water pipe comprises some crisscross cooling water pipes; The end of every cooling water pipe is the refrigeratory upstream end.
The tube wall of every cooling water pipe is provided with several trickle holes.
Reactor core fused mass cooling device distance from top reactor core fused mass arresting device bottom interval 0.1~0.5m.
The diameter that the reactor core fused mass is detained groove is 4m~8m, and the degree of depth is 1.8m~4m, and reactor core fused mass delay bottom portion of groove is 0.5m~2m apart from the thickness of reactor core fused mass arresting device bottom.
When major accident occurs, behind the core meltdown, because the fused mass retentivity mechanism is complicated in the heap, be difficult to be familiar with fully, therefore there is the possibility of pressure vessel breakage.After the pressure vessel breakage, fused mass flows out, will react with the concrete of former cavity bottom, produce a large amount of inconduces, might make the containment superpressure, simultaneously because the inner constantly generation of fused mass decay heat, if can not get abundant cooling, fused mass can finally directly heat containment by constantly downward burn through, and last one safety curtain of burn through causes radioactivity to leak in a large number.The present invention adopts the fused mass of out-pile to be detained design, contain fused mass with the material different from pressure vessel, with coolant loop and reactor core fused mass cooling device fused mass is cooled off again, guarantee in time to derive the decay heat of fused mass, stop the interaction of fused mass and concrete and containment directly to heat, it is complete to keep safety curtain, prevents that radioactivity from leaking in a large number, has greatly improved the high full property of nuclear power station.
Description of drawings
Fig. 1 is the structural representation of I type out-pile fused mass arresting device behind a kind of nuclear power plant accident provided by the present invention.
Fig. 2 is the vertical view of the reactor core fused mass cooling device of I type out-pile fused mass arresting device behind a kind of nuclear power plant accident provided by the present invention.
Among the figure: 1 is pressure vessel, and 2 is the cooling medium decline passway, and 3 is exterior wall, and 4 is coolant channel, and 5 is reactor core fused mass arresting device, and 6 is reactor core fused mass cooling device, and 7 is the reactor core fused mass, and 8 is the steam rising passage, and 9 is interior wall, and 10 is the steam channel wall.
Embodiment
The present invention is further detailed explanation below in conjunction with drawings and Examples.
The present invention includes pressure vessel 1, exterior wall 3, interior wall 9, reactor core fused mass arresting device 5, reactor core fused mass cooling device 6.
Closure is opened wide up and down around the interior wall 9, the steam channel wall 10 of the bottom opening that interior wall 9 inboards are fixed with by concreting.Pressure vessel 1 places steam channel wall 10 by pipeline support.Form steam rising passage 8 between pressure vessel 1 and the steam channel wall 10.
Reactor core fused mass arresting device 5 is fixed in interior wall 9 bottoms by concreting.Be provided with coolant channel 4 between interior wall 9 and the reactor core fused mass arresting device 5.Reactor core fused mass arresting device 5 is made of the inorganic non-metallic fire resistive material that bears ceiling temperature and be not less than 1580 degrees centigrade, has ability, the coefficient of heat conductivity of preferably heat shock resistance and chemical erosion low and expansion coefficient is low.Inorganic non-metallic fire resistive material inside has many micro-channels coolant vapours can be exported to steam rising passage 8.The inorganic non-metallic fire resistive material can be acid refractory, neutral refractory, basic refractory or high-temperature composite material.Wherein acid refractory is preferably monox.Neutral refractory is preferably aluminium oxide, chromium oxide or graphite.Basic refractory is preferably magnesium oxide, calcium oxide, lanthana, beryllia or zirconia.High-temperature composite material is preferably metallic ceramics or fiber reinforced ceramic.
The position that reactor core fused mass arresting device 5 upper surfaces are positioned under the pressure vessel is provided with reactor core fused mass delay groove, the diameter that the reactor core fused mass is detained groove for 4m~8m to provide enough reactor cores to catch area, depth requirements is greater than 1.8m~4m, to bear the reactor core fused mass.Reactor core fused mass arresting device 5 lower surfaces are the plane.Reactor core fused mass delay bottom portion of groove is 0.5m~2m apart from the thickness of reactor core fused mass arresting device 5 bottoms.
Closed around exterior wall 3 is whole, be fixed on the base plate by concrete, within the exterior wall on the base plate by being welded with reactor core fused mass cooling device 6.Reactor core fused mass cooling device 6 comprises 2~6 layers of adjacent cooling water pipe that is welded and fixed, and every layer of cooling water pipe comprises that some crisscross welding are communicated with fixing cooling water pipe.The two ends of every cooling water pipe all are provided with opening, and the tube wall of every cooling water pipe is provided with several trickle holes.
Interior wall 9 places within the exterior wall 3 with reactor core fused mass arresting device 5 integral body, realizes fixing between interior wall 9 and the exterior wall 3 by some point of fixity.Form cooling medium decline passway 2 between interior wall 9 and the exterior wall 3, reactor core fused mass cooling device 6 is positioned at reactor core fused mass arresting device below, and the bottom of the top of reactor core fused mass cooling device 6 and reactor core fused mass arresting device 5 is at a distance of 0.1~0.5m.
For nuclear power station, in the major accident situation, pressure vessel 1 breaks, core meltdown reactor core fused mass 7, when 7 outflows of reactor core fused mass, out-pile fused mass arresting device 6 is detained reactor core fused mass 7, but the reactor core fused mass can produce decay heat continuously, if the heat meeting burn through base plate untimely with the heat derivation, that reactor core fused mass 7 produces and gathers, cooling medium descends from cooling medium decline passway 2, enter from coolant channel 4, the top of cooling reactor core fused mass 7, cooling medium is downward again, by the entrance of reactor core fused mass cooling device 6, enter in the cooling water pipe, cooling medium goes out by the trickle orifice flow in cooling water pipe simultaneously, and the outer fused mass arresting device 5 of cools stacks is after the refrigerant evaporates, see through out-pile fused mass arresting device 5, enter containment along steam rising passage 8, after in containment, being cooled, become coolant water, entered by cooling medium decline passway 2 again, thereby form circulation.
Claims (10)
1. I type out-pile fused mass arresting device behind the nuclear power plant accident, closed interior wall around comprising, be fixed in the bottom opening of interior wall inboard the steam channel wall, place the pressure vessel within the steam channel wall, form the steam rising passage between described pressure vessel and the steam channel wall, it is characterized in that: also comprise enclose in outside the interior wall be positioned on the base plate around closed exterior wall, the reactor core fused mass cooling device on the base plate of being fixed in that is fixed in the reactor core fused mass arresting device of interior wall bottom and is positioned at described reactor core fused mass arresting device below; Form the cooling medium decline passway between described interior wall and the exterior wall, be provided with coolant channel between described interior wall and the reactor core fused mass arresting device; The position that described reactor core fused mass arresting device upper surface is positioned under the pressure vessel is provided with reactor core fused mass delay groove, and described reactor core fused mass arresting device lower surface is the plane; Described reactor core fused mass arresting device is made of the inorganic non-metallic fire resistive material.
2. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 1, it is characterized in that: described inorganic non-metallic fire resistive material is acid refractory, neutral refractory, basic refractory or high-temperature composite material.
3. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 2, it is characterized in that: described acid refractory is monox.
4. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 2, it is characterized in that: described neutral refractory is aluminium oxide, chromium oxide or graphite.
5. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 2, it is characterized in that: described basic refractory is magnesium oxide, calcium oxide, lanthana, beryllia or zirconia.
6. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 2, it is characterized in that: described high-temperature composite material is metallic ceramics or fiber reinforced ceramic.
7. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 1, it is characterized in that: described reactor core fused mass cooling device comprises the adjacent fixing cooling water pipe of some layers, and described every layer of cooling water pipe comprises some crisscross cooling water pipes; The end of described every cooling water pipe is the refrigeratory upstream end.
8. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 7, it is characterized in that: the tube wall of described every cooling water pipe is provided with several trickle holes.
9. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 1 is characterized in that: the described reactor core fused mass of described reactor core fused mass cooling device distance from top arresting device bottom interval 0.1~0.5m.
10. I type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 1, it is characterized in that: the diameter that described reactor core fused mass is detained groove is 4m~8m, the degree of depth is 1.8m~4m, and the thickness that described reactor core fused mass is detained the described reactor core fused mass arresting device of bottom portion of groove distance bottom is 0.5m~2m.
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CN2012101270155A CN103377724A (en) | 2012-04-27 | 2012-04-27 | I-shaped reactor external melt retention device used after nuclear power plant accident |
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Cited By (3)
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JP2016191559A (en) * | 2015-03-30 | 2016-11-10 | 日立Geニュークリア・エナジー株式会社 | Core Catcher |
CN106525895A (en) * | 2016-11-11 | 2017-03-22 | 西安交通大学 | Device and method for high temperature melt growth choking experiment |
CN107945891A (en) * | 2017-10-19 | 2018-04-20 | 中国核电工程有限公司 | A kind of system for having the function of in reactor core fusant heap to be detained and out-pile is detained |
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
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JP2016191559A (en) * | 2015-03-30 | 2016-11-10 | 日立Geニュークリア・エナジー株式会社 | Core Catcher |
CN106525895A (en) * | 2016-11-11 | 2017-03-22 | 西安交通大学 | Device and method for high temperature melt growth choking experiment |
CN106525895B (en) * | 2016-11-11 | 2018-12-07 | 西安交通大学 | A kind of extension of high-temperature molten is jammed experimental provision and experimental method |
CN107945891A (en) * | 2017-10-19 | 2018-04-20 | 中国核电工程有限公司 | A kind of system for having the function of in reactor core fusant heap to be detained and out-pile is detained |
CN107945891B (en) * | 2017-10-19 | 2021-01-19 | 中国核电工程有限公司 | System with reactor core melt in-reactor detention and out-of-reactor detention functions |
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