CN103377722A - V-shaped reactor external melt retention device used after nuclear power plant accident - Google Patents
V-shaped reactor external melt retention device used after nuclear power plant accident Download PDFInfo
- Publication number
- CN103377722A CN103377722A CN2012101270117A CN201210127011A CN103377722A CN 103377722 A CN103377722 A CN 103377722A CN 2012101270117 A CN2012101270117 A CN 2012101270117A CN 201210127011 A CN201210127011 A CN 201210127011A CN 103377722 A CN103377722 A CN 103377722A
- Authority
- CN
- China
- Prior art keywords
- fused mass
- reactor core
- arresting device
- wall
- nuclear power
- Prior art date
- 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.)
- Granted
Links
Images
Classifications
-
- 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
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention relates to a V-shaped reactor external melt retention device used after a nuclear power plant accident. The V-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 in tight contact with the bottom of the reactor core melt retention device, 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 under the pressure container; 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 V-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 V-type out-pile fused mass arresting device behind the nuclear power plant accident of nuclear plant safety.
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 V-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 V-type out-pile fused mass arresting device behind a kind of nuclear power plant accident, the interior wall of closure around comprising, be fixed in the steam channel wall of the bottom opening of interior wall inboard, 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, be fixed in the reactor core fused mass arresting device of interior wall bottom, and with the reactor core fused mass cooling device that is fixed in exterior wall of reactor core fused mass arresting device bottom close contact; 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 successively some layers of heat pipe of contact, and every layer of heat pipe comprises some crisscross heat pipes; The sealing of the end of every heat pipe is inserted among the exterior wall.
Reactor core fused mass cooling device comprises successively some layers of thermoelectric conversion device of contact, and every layer of thermoelectric conversion device comprises some crisscross thermoelectric conversion devices; The sealing of the end of every thermoelectric conversion device is inserted among the exterior wall.
The number of plies of heat pipe or thermoelectric conversion device is 1～5 layer.
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 V-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 V-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 1～5 layer of successively heat pipe of contact, and every layer of hot and cold tube comprises that some crisscross welding are communicated with fixing heat pipe.Insert among the exterior wall 3 at the two ends of every heat pipe, and fixing with exterior wall 3 sealings.The preferred of heat pipe is high-temperature heat pipe, with receive or water as actuating medium, inwall is provided with capillary structure.Reactor core fused mass cooling device 6 can also be made of some alkaline metal electricity-heat converters, and concrete structure is consistent with heat pipe.
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 reactor core fused mass 7 flows out, out-pile fused mass arresting device 6, be detained reactor core fused mass 7, but the reactor core fused mass can produce decay heat continuously, if untimely heat is derived, the heat meeting burn through base plate 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, entrance by reactor core fused mass cooling device 6, flow out from the gap of reactor core fused mass cooling device 6, 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, reactor core fused mass cooling device 6 also can be led heat to exterior wall 3 by the mechanism of heat pipe or thermoelectric conversion device at the same time, plays the effect of the outer fused mass arresting device 5 of cools stacks.
Claims (10)
1. V-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, be fixed in the interior wall bottom reactor core fused mass arresting device and with the reactor core fused mass cooling device that is fixed in exterior wall of described reactor core fused mass arresting device bottom close contact; 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. V-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. V-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. V-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. V-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. V-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. V-type out-pile fused mass arresting device behind a kind of nuclear power plant accident according to claim 1 is characterized in that: described reactor core fused mass cooling device comprises successively some layers of heat pipe of contact, and described every layer of heat pipe comprises some crisscross heat pipes; The sealing of the end of described every heat pipe is inserted among the exterior wall.
8. V-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 successively some layers of thermoelectric conversion device of contact, and described every layer of thermoelectric conversion device comprises some crisscross thermoelectric conversion devices; The sealing of the end of described every thermoelectric conversion device is inserted among the exterior wall.
9. V-type out-pile fused mass arresting device according to claim 7 or behind 8 described a kind of nuclear power plant accidents, it is characterized in that: the number of plies of described heat pipe or thermoelectric conversion device is 1～5 layer.
10. V-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.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210127011.7A CN103377722B (en) | 2012-04-27 | 2012-04-27 | Out-pile fused mass arresting device after a kind of nuclear power plant accident |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210127011.7A CN103377722B (en) | 2012-04-27 | 2012-04-27 | Out-pile fused mass arresting device after a kind of nuclear power plant accident |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103377722A true CN103377722A (en) | 2013-10-30 |
| CN103377722B CN103377722B (en) | 2017-05-31 |
Family
ID=49462719
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210127011.7A Active CN103377722B (en) | 2012-04-27 | 2012-04-27 | Out-pile fused mass arresting device after a kind of nuclear power plant accident |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103377722B (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105513649A (en) * | 2016-01-14 | 2016-04-20 | 中国核电工程有限公司 | Reactor core molten debris grouping retention and cooling system |
| WO2017045159A1 (en) * | 2015-09-16 | 2017-03-23 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shielding wall combination structure |
| CN107978378A (en) * | 2017-10-19 | 2018-05-01 | 中国核电工程有限公司 | A kind of reactor core melts capturing device |
| CN109346196A (en) * | 2018-11-13 | 2019-02-15 | 中国核动力研究设计院 | Gaseous-waste holdup system in the fusant heap that a kind of active and passive cooling combines |
| CN111883269A (en) * | 2020-08-12 | 2020-11-03 | 中国核动力研究设计院 | System and method for cooling stagnant passive in molten material reactor of floating nuclear power station |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN85100182A (en) * | 1985-04-01 | 1986-08-20 | 清华大学 | Adopt the nuclear power station light water reactor of double pressure shell |
| CN101390170A (en) * | 2006-02-22 | 2009-03-18 | 株式会社东芝 | Core catcher and its manufacturing method, and reactor container and its modifying method |
| JP2009145135A (en) * | 2007-12-12 | 2009-07-02 | Toshiba Corp | Reactor container, and leakage-detecting floor |
| CN202102730U (en) * | 2011-05-09 | 2012-01-04 | 中科华核电技术研究院有限公司 | Out-of-pile cooling and curing device of reactor core fusant in reactor severe accident and system |
-
2012
- 2012-04-27 CN CN201210127011.7A patent/CN103377722B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN85100182A (en) * | 1985-04-01 | 1986-08-20 | 清华大学 | Adopt the nuclear power station light water reactor of double pressure shell |
| CN101390170A (en) * | 2006-02-22 | 2009-03-18 | 株式会社东芝 | Core catcher and its manufacturing method, and reactor container and its modifying method |
| JP2009145135A (en) * | 2007-12-12 | 2009-07-02 | Toshiba Corp | Reactor container, and leakage-detecting floor |
| US20100239061A1 (en) * | 2007-12-12 | 2010-09-23 | Kabushiki Kaisha Toshiba | Reactor containment vessel and water leak detection floor |
| CN202102730U (en) * | 2011-05-09 | 2012-01-04 | 中科华核电技术研究院有限公司 | Out-of-pile cooling and curing device of reactor core fusant in reactor severe accident and system |
Non-Patent Citations (1)
| Title |
|---|
| 冉刻，等: "核电站堆芯熔融物的处理措施", 《华电技术》, vol. 33, no. 10, 31 October 2011 (2011-10-31), pages 79 * |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2017045159A1 (en) * | 2015-09-16 | 2017-03-23 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shielding wall combination structure |
| CN105513649A (en) * | 2016-01-14 | 2016-04-20 | 中国核电工程有限公司 | Reactor core molten debris grouping retention and cooling system |
| CN105513649B (en) * | 2016-01-14 | 2019-10-29 | 中国核电工程有限公司 | A kind of grouping of reactor core fusant is detained and cooling system |
| CN107978378A (en) * | 2017-10-19 | 2018-05-01 | 中国核电工程有限公司 | A kind of reactor core melts capturing device |
| CN107978378B (en) * | 2017-10-19 | 2021-06-25 | 中国核电工程有限公司 | Reactor core melt trapping device |
| CN109346196A (en) * | 2018-11-13 | 2019-02-15 | 中国核动力研究设计院 | Gaseous-waste holdup system in the fusant heap that a kind of active and passive cooling combines |
| CN109346196B (en) * | 2018-11-13 | 2022-04-15 | 中国核动力研究设计院 | Active and passive cooling combined molten material in-pile retention system |
| CN111883269A (en) * | 2020-08-12 | 2020-11-03 | 中国核动力研究设计院 | System and method for cooling stagnant passive in molten material reactor of floating nuclear power station |
| CN111883269B (en) * | 2020-08-12 | 2022-04-22 | 中国核动力研究设计院 | System and method for cooling stagnant passive in molten material reactor of floating nuclear power station |
Also Published As
| Publication number | Publication date |
|---|---|
| CN103377722B (en) | 2017-05-31 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105047236B (en) | Under reactor disaster state, fused mass is detained passive cooling system | |
| CN103377722A (en) | V-shaped reactor external melt retention device used after nuclear power plant accident | |
| CN104269194B (en) | The passive accident afterheat of pool reactor of a kind of temperature triggered discharges system | |
| CN107210070B (en) | The cooling and closed system of water cooling, water-moderated reactor reactor core fusant | |
| CN103377720B (en) | Out-pile fused mass arresting device after a kind of nuclear power plant accident | |
| CN107251153B (en) | Nuclear reactor core melt cooling and containment system | |
| US11189384B2 (en) | Systems and methods for enhancing isolation of high-temperature reactor containments | |
| WO2007099698A1 (en) | Core catcher and its manufacturing method, and reactor container and its modifying method | |
| CN104051030B (en) | Passive core melt trapping system | |
| CN110459333B (en) | Double-layer crucible reactor core melt trapping device with internal cooling pipe | |
| CN104103325B (en) | Heat derivation system for long-term passive containment | |
| CN105047235A (en) | Melt in-pile retention passive cooling system in nuclear reactor severe accident state | |
| EP3291242B1 (en) | Passively operating cooling device for ex-vessel corium | |
| CN105427900A (en) | Out-of-pile retention system for reaction pile melt after occurrence of severe accident | |
| CN103377724A (en) | I-shaped reactor external melt retention device used after nuclear power plant accident | |
| CN105551538B (en) | Molten core catcher with function of guiding layered extension of molten material | |
| CN203444767U (en) | Passive core smelt catching system | |
| CN105551539A (en) | Reactor melt out-of-core retention system | |
| CN108028081A (en) | Nuclear reactor passive protective device | |
| WO2007136261A1 (en) | A nuclear reactor | |
| CN103377723A (en) | Type-III out-of-core melt retention device after nuclear power station accidents | |
| CN104021824A (en) | In-pile melts retention system after nuclear power station accident | |
| CN202332312U (en) | Emergency protection device for preventing reactor pressure vessel from being melted through by utilizing passive heat exchange | |
| WO2014015740A1 (en) | Spherical fuel reactor | |
| CN205451786U (en) | Reactor core melts trap with rib structure water -cooling wall |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: Shanghai Nuclear Engineering Research & Design Institute |
|
| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
|
| CP01 | Change in the name or title of a patent holder |