CN109147969B - Nuclear reactor molten material core retention passive cooling system - Google Patents
Nuclear reactor molten material core retention passive cooling system Download PDFInfo
- Publication number
- CN109147969B CN109147969B CN201811069319.4A CN201811069319A CN109147969B CN 109147969 B CN109147969 B CN 109147969B CN 201811069319 A CN201811069319 A CN 201811069319A CN 109147969 B CN109147969 B CN 109147969B
- Authority
- CN
- China
- Prior art keywords
- low
- water tank
- pressure
- core
- cooling system
- 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.)
- Active
Links
Images
Classifications
-
- 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
-
- 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
- Physics & Mathematics (AREA)
- 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 invention discloses a nuclear reactor molten material core retention passive cooling system, which carries out core decay heat through a low-pressure safety water injection tank water injection system and a passive water injection cooling system under the serious accident state of a nuclear reactor, realizes that all or most of fuel assembly cladding maintains a rod-shaped structure state, a core supporting plate maintains a lower temperature, can support water in a fuel assembly, a core molten pool and a pressure vessel lower end enclosure and cannot be dried, namely, the molten material core retention is realized, and the condition that the lower end enclosure is melted due to relocation of core molten material in the lower end enclosure is prevented.
Description
Technical Field
The invention relates to the field of nuclear reactor accident safety, in particular to a nuclear reactor molten material core retention passive cooling system.
Background
At present, in the advanced third-generation reactor design at home and abroad, two main strategies are provided for realizing the cooling and detention of reactor core melts for relieving serious accidents: 1. In-Vessel cooling and stagnation (IVR); 2. the melt cools and stagnates outside the pile. The application of the first strategy is represented by AP600/AP 1000. The second strategy requires a special melt catcher to receive the core melt and to cool and retain the melt inside the catcher. Two trap schemes, namely a crucible type trap of VVER-1000 and an extended type trap of EPR-1600, are successfully developed and applied internationally. In the application of the first strategy, taking AP600/AP1000 as an example, after a severe accident of core melting occurs to the reactor, the core melt inevitably migrates and relocates to the lower head of the pressure vessel, and the reactor cavity is flooded by the reactor cavity water injection cooling system to cool the outer surface of the lower head of the reactor pressure vessel, so that melt retention (IVR) in the lower head of the pressure vessel is realized, and the integrity of the pressure vessel is maintained. Pressure vessel failure was proven to be "physically impossible" based on the critical heat flux density (CHF) criterion by analyzing the formation and structure of the lower head melt pool, the heat transfer of the melt pool, and the like. In the first strategy, when a measure of cooling and retaining (IVR) in a lower head of a melt is taken, the melt can melt part of the inner wall surface of the lower head of the pressure vessel, and the lower head of the pressure vessel has the possibility of failure. In order to avoid the melting of the lower head of the pressure vessel by the melt and prevent the relocation of the core melt to the lower head of the pressure vessel, the nuclear reactor melt core retention passive cooling system is provided for a low-power nuclear reactor.
Disclosure of Invention
The invention aims to provide a reactor core retention passive cooling system for molten core of a nuclear reactor, which aims to solve the problem that in the prior art, the lower end socket is easily melted by molten metal because the molten core is relocated to the lower end socket of a pressure vessel in the serious accident state of the nuclear reactor, realize the retention of the molten core, and prevent the molten core from being relocated to the lower end socket.
The invention is realized by the following technical scheme:
the passive cooling system for the reactor core retention of the nuclear reactor molten mass comprises a pressure vessel, a low-pressure safety water injection tank water injection system, a passive water injection cooling system and an in-reactor structure positioned in the pressure vessel;
the pressure container comprises a lower end enclosure, a cylinder body and an upper end enclosure, wherein the upper end enclosure and the lower end enclosure are respectively connected to the upper end and the lower end of the cylinder body; wherein the lower end enclosure is spherical or ellipsoidal,
the in-reactor structure comprises a reactor core supporting plate, a hanging basket, a surrounding barrel and a fuel assembly, wherein the reactor core supporting plate is fixed on the inner wall of a lower end enclosure, the surrounding barrel is fixed on the upper surface of the reactor core supporting plate, the bottom end of the hanging basket is connected with the reactor core supporting plate, the top end of the hanging basket is connected with the top of a barrel body, the surrounding barrel is arranged in the hanging basket, and the fuel assembly is arranged in the surrounding barrel; the reactor core supporting plate is provided with a plurality of through holes;
the low-pressure safety water injection tank water injection system is used for injecting water into the pressure container;
the passive water injection cooling system is used for cooling the outer side wall of the pressure vessel when the temperature of the outlet of the core is higher than 650 ℃.
The invention provides a reactor melt core retention passive cooling system, which aims at solving the problem that in the prior art, the lower end socket is easily melted by melt because the reactor melt is relocated to the lower end socket of a pressure vessel in the severe accident state of a nuclear reactor. This system during operation, when a big breach appears in reactor return circuit, for example when connecting pressure vessel's safety injection pipeline breach, reactor coolant loses in a large number, and the cooling water of reactor core moisturizing case, middling pressure safety injection case etc. also runs off along with the breach, through low pressure safety injection water tank water injection system this moment, through low pressure safety injection water tank to pressure vessel water injection, maintain partial reactor core water level to take out reactor core decay heat. When the outlet temperature of the reactor core is higher than 650 ℃, the passive water injection cooling system injects water to the heat-insulating layer runner to cool the outer side wall of the pressure vessel, so that more heat in the pressure vessel is brought out, and the lower seal head is prevented from being melted due to the fact that the molten material of the reactor core is migrated and relocated in the lower seal head.
Further, low pressure safety water injection water tank water injection system includes low pressure safety water injection water tank, normally open electric stop valve, first check valve, low pressure safety water injection water tank with the barrel links to each other, sets gradually between low pressure safety water injection water tank to the barrel normally open electric stop valve, first check valve.
Further, cooling water and pressurized gas are filled in the low-pressure safety injection water tank, and the pressure of the pressurized gas in the low-pressure safety injection water tank is 0.6-1 MPa in a normal state; when the cooling water in the low-pressure safety injection water tank is exhausted, the pressure of the pressurized gas in the low-pressure safety injection water tank is 0.2-0.4 MPa.
Further, the inner diameter of a pipeline, connected to the barrel, of the low-pressure safety injection water tank is 20-30 mm.
Further, the pressurized gas is nitrogen.
Further, passive active water injection cooling system closes electronic stop valve, second check valve, heat preservation runner, exhaust hole including being located the outside cooling water tank of pressure vessel, normally, the heat preservation is located outside the pressure vessel, forms the heat preservation runner between heat preservation and pressure vessel's the lateral wall, the exhaust hole is located the top of heat preservation runner, cooling water tank links to each other with the heat preservation runner, sets gradually between cooling water tank to the heat preservation runner and closes electronic stop valve, second check valve normally.
Furthermore, the heat-insulating layer is integrally coated on the lower part of the cylinder body and the outer part of the lower end enclosure.
Furthermore, the width of the heat-insulating layer runner is 50-200 mm.
Further, the exhaust hole is covered by a floating plate.
Compared with the prior art, the invention has the following advantages and beneficial effects:
according to the passive cooling system for the reactor core retention of the nuclear reactor melt, in the serious accident state of the nuclear reactor, the core decay heat is brought out through the low-pressure safety water injection tank water injection system and the passive water injection cooling system, all or most of fuel assembly cladding can be kept in a rod-shaped structure state, the reactor core supporting plate is kept at a lower temperature, water in a fuel assembly, a reactor core molten pool and a pressure vessel lower end enclosure can be supported and cannot be dried, namely the melt reactor core retention is realized, and the situation that the lower end enclosure is melted due to the fact that the reactor core melt is relocated in the lower end enclosure is prevented.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic illustration of a nuclear reactor molten core retention configuration according to an embodiment of the present invention;
FIG. 2 is a schematic structural view of a molten core in a stagnant state with fuel assemblies intact according to an embodiment of the present invention;
FIG. 3 is a schematic diagram of a partially collapsed fuel assembly in a molten core retention state according to an embodiment of the present invention.
Reference numbers and corresponding part names in the drawings:
1-lower end socket, 2-barrel, 3-reactor core supporting plate, 4-hanging basket, 5-surrounding barrel, 6-fuel assembly, 7-low-pressure safety injection water tank, 8-normally open electric stop valve, 9-first check valve, 10-cooling water tank, 11-normally closed electric stop valve, 12-second check valve, 13-insulating layer, 14-insulating layer flow passage, 15-floating plate and 16-crevasse.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
The nuclear reactor molten core retention passive cooling system shown in fig. 1 to 3 comprises a pressure vessel, a low-pressure safety water injection tank water injection system, a passive water injection cooling system and an in-core structure positioned in the pressure vessel; the pressure container comprises a lower end enclosure 1, a cylinder body 2 and an upper end enclosure, wherein the upper end enclosure and the lower end enclosure 1 are respectively connected to the upper end and the lower end of the cylinder body 2; the reactor core supporting plate 3 is fixed on the inner wall of the lower end enclosure 1, the enclosure 5 is fixed on the upper surface of the reactor core supporting plate 3, the bottom end of the basket 4 is connected with the reactor core supporting plate 3, the top end of the basket 4 is connected with the top of the barrel 2, the enclosure 5 is arranged in the basket 4, and the fuel assembly 6 is arranged in the enclosure 5; the reactor core supporting plate 3 is provided with a plurality of through holes; the low-pressure safety water injection tank water injection system is used for injecting water into the pressure container; the passive water injection cooling system is used for injecting water to the heat-insulating layer runner and cooling the outer side wall of the pressure vessel when the temperature of the reactor core outlet is higher than 650 ℃.
Low pressure safety water injection water tank water injection system includes two subsystems in this embodiment, and every subsystem all includes low pressure safety water injection water tank, normally open electric stop valve, first check valve 9, low pressure safety water injection water tank 7 with barrel 2 links to each other, and low pressure safety water injection water tank 7 sets gradually between to the barrel 2 normally open electric stop valve 8, first check valve 9.
The low-pressure safety injection water tank 7 is filled with cooling water and pressurized gas, and the pressure of the pressurized gas in the low-pressure safety injection water tank 7 is 0.6-1 MPa in a normal state; when the cooling water in the low-pressure safety injection water tank 7 is exhausted, the pressure of the pressurized gas in the low-pressure safety injection water tank 7 is 0.2-0.4 MPa.
The inner diameter of a pipeline, connected to the barrel body 2, of the low-pressure safety injection water tank 7 is 20-30 mm.
The pressurized gas is nitrogen.
The passive water injection cooling system comprises a cooling water tank 10, a normally closed electric stop valve 11, a second check valve 12, a heat preservation layer 13, a heat preservation layer flow passage 14 and exhaust holes, wherein the cooling water tank 10 is located outside the pressure container, the heat preservation layer flow passage 14 is formed between the heat preservation layer 13 and the outer side wall of the pressure container, the exhaust holes are located at the top end of the heat preservation layer flow passage 14, the cooling water tank 10 is connected with the heat preservation layer flow passage 14, and the normally closed electric stop valve 11 and the second check valve 12 are sequentially arranged between the cooling water tank 10 and the heat preservation layer flow passage 14.
The heat-insulating layer 13 is wholly covered on the lower part of the cylinder body 2 and the outer part of the lower end enclosure 1.
The width of the heat-insulating layer flow channel 14 is 50-200 mm.
The exhaust holes are covered by a floating plate 15.
In this embodiment, when a large break 16 appears in a primary circuit of the reactor, a large amount of reactor coolant is lost, cooling water of the reactor core water replenishing tank, the medium-pressure safety injection tank and the low-pressure safety injection tank also runs off along with the break 16, and when the internal pressure of the pressure vessel is lower than the nitrogen pressure of the low-pressure safety injection tank, nitrogen in the intact low-pressure safety injection tank 7 drives cooling water to enter the pressure vessel. The low-pressure safety injection water tank 7 is provided with a small-inner-diameter water injection pipeline between 20mm and 30mm and a very low injection pressure between 0.5MPa and 0.3MPa, so that the water source of the low-pressure safety injection water tank is ensured to avoid waste caused by directly discharging the water from the pressure container through the crevasse 16. Water injection of the low-pressure safety injection tank maintains part of the water level of the reactor core and brings out decay heat of the reactor core.
Steam generated by the reactor core enters the containment through the pressure vessel crevasse 16, and the steam in the containment is condensed and collected by the cooler and then flows back to the cooling water tank 10 outside the pressure vessel.
When the outlet temperature of the reactor core is higher than 650 ℃, the electric stop valve 11 which is normally closed is opened to be put into the passive water injection cooling system outside the pressure vessel to work, cooling water in the cooling water tank 10 is injected into the heat-insulating layer flow passage 14 by virtue of gravity, and the floating plate 15 covered on the exhaust hole at the top of the heat-insulating layer flow passage 14 is jacked open, so that the outer wall surface of the pressure vessel is submerged. The heat of the coolant in the pressure vessel enters the insulating layer flow passage 14 through the heat convection and heat conduction of the wall surface of the pressure vessel. The cooling water in the insulating layer flow passage 14 has a decreased density due to an increase in temperature, and forms a density difference with the cooling water in the cooling water tank 10 and the water injection pipeline having a lower temperature and a higher density, and the gravity difference and the density difference form together and enhance the natural circulation flow in the insulating layer flow passage 14. The enhanced natural circulation flow in the insulation layer flow passage 14 facilitates cooling of the outer wall surface of the pressure vessel and bringing more heat out of the pressure vessel.
When the cooling water and the vapor in the insulating layer flow passage 14 flow upwards and are discharged from the exhaust hole at the top of the insulating layer flow passage 14, the water returns to the containment pit, the vapor enters the containment, and the vapor in the containment is condensed and collected by the cooler and then flows back to the cooling water tank 10.
In addition, when the water in the low-pressure safety water injection tank 7 is consumed or the pressure is balanced and the pressure vessel cannot be injected with water, the fuel assemblies 6 are exposed again, the cladding temperature rises rapidly, and the low-melting-point materials of the reactor core, such as control rods, the surrounding cylinders 5 and the like, are firstly melted and fall on the reactor core supporting plate 3. The low melting point melt enters the lower head 1 through the passage holes to be cooled by water, and the generated water vapor ascends to cool the core support plate 3 and the fuel assemblies 6, so that a small amount of low melting point melt is accumulated at the bottom of the lower head 1.
After the surrounding cylinder 5 is completely melted, direct radiation heat exchange is realized between the fuel assembly 6 and the hanging basket 4, the radiation heat exchange capacity is enhanced, the temperature of the hanging basket 4 is rapidly increased, and meanwhile, the radiation heat exchange of the hanging basket 4 and the cylinder body 2 is also enhanced. Therefore, the decay heat of the fuel assembly 6 is transferred to the cylinder body 2 from inside to outside through the fuel assembly 6 and the fuel assembly 6, the fuel assembly 6 and the surrounding cylinder 5, the fuel assembly 6 and the hanging basket 4, and the hanging basket 4 and the cylinder body 2 in a radiation heat exchange, convection heat exchange and heat conduction heat exchange mode, and finally enters the cooling water in the heat-insulating layer flow channel 14 through the convection heat exchange and heat conduction heat exchange mode to generate bubbles to form a steam-water mixture or steam, and the bubbles are discharged from the exhaust holes in the top of the heat-insulating layer flow channel 14.
The core is exposed, decay heat in the fuel assemblies 6 is brought out by convection heat exchange and radiation heat exchange, the fuel assemblies 6 in the center of the core are likely to fail due to the fact that the radiation heat exchange is less, the cladding temperature is highest, and therefore, part of the fuel assemblies 6 in the center of the core can be melted and collapsed to form a core molten pool, as shown in the attached figure 2. It is also possible that all fuel assemblies 6 maintain a complete geometry, as shown in fig. 3. In any core state, the core support plate 3 is heated by the decay heat of the fuel assemblies 6 and the core molten pool in a heat conduction mode, when the core support plate 3 is exposed, water is vaporized after the temperature of the core support plate 3 is increased and the water is subjected to radiation heat exchange with the water pool in the lower end socket 1, and water vapor flows upwards to pass through the core fuel assemblies 6 and the outer surface of the core molten pool, so that the core is further cooled. The reactor core supporting plate 3 with the increased temperature also exchanges heat with the inner surface of the exposed lower end socket 1 in a radiation mode, and the heat finally enters flowing cooling water in the heat-insulating layer flow passage 14.
When the decay heat of the reactor core fuel assembly 6 and the reactor core molten pool reaches the balance with the heat brought by the passive water injection cooling system, the temperature of the reactor core fuel assembly 6, the reactor core molten pool, the unmelted shroud barrel 5, the hanging basket 4, the reactor core supporting plate and the inner wall surface of the pressure vessel does not rise any more and reaches the maximum temperature. As the decay heat of the core fuel assemblies 6 and the core melt pool gradually decreases, the temperatures of the core fuel assemblies 6, the core melt pool, the unmelted shroud 5, the gondola 4, the core support plate, and the inner wall surface of the pressure vessel also gradually decrease. The core support plate 3 is relatively cold and is capable of supporting the fuel assemblies 6 and the core melt pool. Meanwhile, cooling water is injected at low pressure of a water injection system of the low-pressure safety water injection tank 7, so that a small amount of water is left in the lower end enclosure 1, and the condition that the interior of the lower end enclosure 1 is not dried is ensured.
In conclusion, in the nuclear reactor molten core retention passive cooling system, in the severe accident state of the nuclear reactor, the core decay heat is brought out through the low-pressure safety water injection tank 7 water injection system and the passive water injection cooling system, all or most of the fuel assemblies 6 can be maintained in the rod-shaped structure state, the core supporting plate 3 is maintained at a lower temperature, water in the fuel assemblies 6, the core molten pool and the pressure vessel lower head 1 can be supported without drying, namely, the molten core retention is realized, and the condition that the lower head 1 is melted due to the fact that the molten core is migrated and relocated in the lower head 1 is prevented.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (7)
1. The passive cooling system for the reactor core retention of the nuclear reactor molten mass is characterized by comprising a pressure vessel, a low-pressure safety water injection tank water injection system, a passive water injection cooling system and an in-reactor structure positioned in the pressure vessel;
the pressure container comprises a lower seal head (1), a cylinder body (2) and an upper seal head, wherein the upper seal head and the lower seal head (1) are respectively connected to the upper end and the lower end of the cylinder body (2); wherein the lower end enclosure (1) is spherical or ellipsoidal;
the in-reactor structure comprises a reactor core supporting plate (3), a hanging basket (4), a surrounding cylinder (5) and fuel assemblies (6), wherein the reactor core supporting plate (3) is fixed on the inner wall of a lower end enclosure (1), the surrounding cylinder (5) is fixed on the upper surface of the reactor core supporting plate (3), the bottom end of the hanging basket (4) is connected with the reactor core supporting plate (3), the top end of the hanging basket (4) is connected with the top of a cylinder body (2), the surrounding cylinder (5) is arranged in the hanging basket (4), and the fuel assemblies (6) are arranged in the surrounding cylinder (5); the reactor core supporting plate (3) is provided with a plurality of through holes;
the low-pressure safety water injection tank water injection system is used for injecting water into the pressure container;
the passive water injection cooling system is used for cooling the outer side wall of the pressure vessel when the temperature of the reactor core outlet is higher than 650 ℃;
the water injection system of the low-pressure safety injection water tank comprises a low-pressure safety injection water tank (7), a normally open electric stop valve (8) and a first check valve (9), wherein the low-pressure safety injection water tank (7) is connected with the barrel (2), and the normally open electric stop valve (8) and the first check valve (9) are sequentially arranged between the low-pressure safety injection water tank (7) and the barrel (2); the low-pressure safety injection water tank (7) is filled with cooling water and pressurized gas, and the pressure of the pressurized gas in the low-pressure safety injection water tank (7) is 0.6-1 MPa in a normal state; when the cooling water in the low-pressure safety injection water tank (7) is exhausted, the pressure of the pressurized gas in the low-pressure safety injection water tank (7) is 0.2-0.4 MPa;
the water injection system of the low-pressure safety injection water tank comprises two subsystems, wherein each subsystem comprises the low-pressure safety injection water tank (7), a normally-open electric stop valve (8) and a first check valve (9).
2. The nuclear reactor molten core retention passive cooling system according to claim 1, wherein the inner diameter of the pipeline connecting the low-pressure safety injection water tank (7) to the barrel (2) is 20-30 mm.
3. The nuclear reactor melt core retention passive cooling system of claim 1, wherein the pressurized gas is nitrogen.
4. The nuclear reactor molten core retention passive cooling system as claimed in claim 1, wherein the passive water injection cooling system comprises a cooling water tank (10), a normally-closed electric stop valve (11), a second check valve (12), a heat insulation layer (13), a heat insulation layer flow channel (14) and an exhaust hole, the heat insulation layer (13) is located outside the pressure vessel, the heat insulation layer flow channel (14) is formed between the heat insulation layer (13) and the outer side wall of the pressure vessel, the exhaust hole is located at the top end of the heat insulation layer flow channel (14), the cooling water tank (10) is connected with the heat insulation layer flow channel (14), and the normally-closed electric stop valve (11) and the second check valve (12) are sequentially arranged between the cooling water tank (10) and the heat insulation layer flow channel (14).
5. The nuclear reactor molten core retention passive cooling system according to claim 4, characterized in that the insulating layer (13) is integrally coated on the lower part of the barrel (2) and the lower head (1).
6. The nuclear reactor molten core retention passive cooling system according to claim 4, wherein the width of the insulating layer flow channel (14) is 50 to 200 mm.
7. The nuclear reactor melt core retention passive cooling system of claim 4, wherein the vent holes are covered by a float plate (15).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811069319.4A CN109147969B (en) | 2018-09-13 | 2018-09-13 | Nuclear reactor molten material core retention passive cooling system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811069319.4A CN109147969B (en) | 2018-09-13 | 2018-09-13 | Nuclear reactor molten material core retention passive cooling system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109147969A CN109147969A (en) | 2019-01-04 |
| CN109147969B true CN109147969B (en) | 2020-02-21 |
Family
ID=64825287
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811069319.4A Active CN109147969B (en) | 2018-09-13 | 2018-09-13 | Nuclear reactor molten material core retention passive cooling system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109147969B (en) |
Families Citing this family (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN110020480B (en) * | 2019-04-09 | 2022-06-17 | 中国核动力研究设计院 | Layered judgment and risk-oriented-based analysis method for structure of lower head inner melting tank |
| CN110415840A (en) * | 2019-08-06 | 2019-11-05 | 中国核动力研究设计院 | A kind of method of adherence pressure external container critical heat flux density |
| CN111503327B (en) * | 2020-03-30 | 2021-11-09 | 中广核研究院有限公司 | Floating valve device, working method thereof and pressure container |
| CN111899901A (en) * | 2020-08-12 | 2020-11-06 | 中国核动力研究设计院 | Passive and active combined molten material in-pile retention cooling system |
| 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 |
| CN111933316B (en) * | 2020-08-12 | 2023-06-02 | 三门核电有限公司 | Method for efficiently cooling reactor cavity area of pressurized water reactor |
| CN112201372B (en) * | 2020-10-16 | 2022-12-02 | 上海核工程研究设计院有限公司 | Method for realizing retention of molten material in reactor core of nuclear reactor |
| CN113205893B (en) * | 2021-04-02 | 2022-03-22 | 中国核电工程有限公司 | Arrangement method and system for reactor core submerged pool of nuclear power station |
| CN114496317A (en) * | 2022-02-18 | 2022-05-13 | 中国核动力研究设计院 | Multifunctional integrated reactor pressure vessel heat preservation device |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103426484A (en) * | 2012-05-25 | 2013-12-04 | 国家核电技术有限公司 | Method used for preventing pressure vessels from melting damages caused by molten materials in reactors, and system used for method |
| CN104051030B (en) * | 2013-09-16 | 2017-02-22 | 国核（北京）科学技术研究院有限公司 | Passive core melt trapping system |
| CN105047235B (en) * | 2015-06-09 | 2017-12-29 | 中国核动力研究设计院 | It is detained passive cooling system under nuclear reactor major accident state in fused mass heap |
| 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 |
-
2018
- 2018-09-13 CN CN201811069319.4A patent/CN109147969B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN109147969A (en) | 2019-01-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109147969B (en) | Nuclear reactor molten material core retention passive cooling system | |
| CA2792108C (en) | Liquid metal cooled nuclear reactor and heat removal method for same | |
| CN105551536B (en) | Reactor core melt catcher with internal cooling capacity | |
| CN102169733B (en) | Passive and active combined special safety system for nuclear power plant | |
| JPH06503885A (en) | Nuclear reactor equipment, its core containment, and emergency cooling methods for nuclear reactor equipment | |
| KR100668048B1 (en) | System for cooling the exterior wall of a reactor vessel and the method thereof | |
| CN105047235A (en) | Melt in-pile retention passive cooling system in nuclear reactor severe accident state | |
| JPH04125495A (en) | Nuclear reactor facility | |
| CN109273109B (en) | type molten material containment vessel retention system | |
| JP2002156485A (en) | Reactor | |
| CN103165199A (en) | Emergency core cooling system (eccs) for nuclear reactor employing closed heat transfer pathways | |
| CN105047236A (en) | Passive cooling system for retention of melts in serious accident state of reactor | |
| JPH0727050B2 (en) | Liquid metal cooled nuclear reactor with passive cooling system | |
| JP3263402B2 (en) | Clearance structure for reactor vessel | |
| CN103377720B (en) | Out-pile fused mass arresting device after a kind of nuclear power plant accident | |
| US10147506B2 (en) | Conformal core cooling and containment structure | |
| JP5279325B2 (en) | Hybrid safety system for boiling water reactors | |
| CN104036833B (en) | In-pile melt retention system with thermal-conductive pile pit outer wall after nuclear power station accident | |
| EP4250315A1 (en) | Safety system and safety control method for preventing molten corium from melting through rpv | |
| CN109102906B (en) | Reactor core catcher system based on built-in refueling water tank | |
| EP0965135B1 (en) | A nuclear plant | |
| WO2022111436A1 (en) | Device for reactor core melt containment in severe accident of nuclear power plant | |
| KR101404954B1 (en) | Method Of Nuclear Corium Cooling Using Liquid Metal Layer, And Nuclear Corium Cooling System Using The Same | |
| JP6670005B2 (en) | Post-Use Nuclear Fuel Passive Cooling System Using Heat Pipe | |
| KR101404955B1 (en) | Method Of Nuclear Corium Cooling Using Liquid Metal in External Reactor Vessel Cooling System, And Nuclear Corium Cooling System Using The Same |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |