CN104036833B - In-pile melt retention system with thermal-conductive pile pit outer wall after nuclear power station accident - Google Patents
In-pile melt retention system with thermal-conductive pile pit outer wall after nuclear power station accident Download PDFInfo
- Publication number
- CN104036833B CN104036833B CN201410222132.9A CN201410222132A CN104036833B CN 104036833 B CN104036833 B CN 104036833B CN 201410222132 A CN201410222132 A CN 201410222132A CN 104036833 B CN104036833 B CN 104036833B
- Authority
- CN
- China
- Prior art keywords
- ivr
- working medium
- pile
- wall
- exterior wall
- 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
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
Abstract
The invention belongs to the reaction pile design technology and in particular relates to an in-pile melt retention system with a thermal-conductive pile pit outer wall after nuclear power station accident. The in-pile melt retention system comprises a pressure vessel arranged in a pile pit, wherein an IVR (Interactive Voice Response) working medium high-level storage box is arranged outside the pile pit and is higher than the pressure vessel in position, the IVR working medium high-level storage box is connected with the pile pit by an injection pipeline, a water-cooling outer wall is arranged outside the pile pit outer wall with good thermal conductivity, an annular water corridor is formed between the pile pit outer wall and the water-cooling outer wall and is connected with an in containment refueling water storage tank by a circulating pipeline, and the IVR working medium adopted by the system is gallium metal. The in-pile melt retention system can be used for effectively preventing from boiling of the outer wall of the pressure vessel and ensuring that the outer wall of the pressure vessel can not be molten-through by reactor core melts.
Description
Technical field
The invention belongs to reactor designing technique, and in particular to heap after a kind of nuclear power plant accident with heat conduction reactor pit exterior wall
Interior fused mass gaseous-waste holdup system.
Background technology
After Fukushima, Japan nuclear accident, effectively eliminating extensive radioactivity release becomes the important safety mesh of nuclear power station design
Mark.It is an important mitigation strategy of the nuclear power station for major accident that fused mass is detained technology, can effectively eliminate radioactivity and release
Put, maintain the integrity of secure border.At present generation Ⅲ nuclear power station generally employs fused mass delay measure.
AP1000 is main to include arranging melting reactor core delay system using the passive gentle measure for solving major accident of prevention
System (IVR), when there is reactor core thawing accident, it is adiabatic with reactor pit that heap chamber flood system injects water into reactor pressure vessel outer wall
Space between layer, drops into the reactor core fused mass of container low head, it is ensured that low head is not fused, and makes reactor core from outside cooling
Fused mass may remain in inside pressure vessel, it is to avoid the reaction of fused mass and water and containment concrete floor, it is therefore prevented that
Out-pile vapour explosion and the generation of base plate burn through.However, during major accident, lower head of pressure vessel wall heat flux density is very
Greatly, once boiling crisis occurs in container outer wall face, then fused mass is possible to burn through pressure vessel, and now IVR system will fail.Cause
This, needs badly and provides after a kind of new nuclear power plant accident for being avoided existing IVR technical failures fused mass gaseous-waste holdup system in heap.
The content of the invention
Present invention aims to the defect of prior art, there is provided a kind of to avoid existing IVR technical failures
Fused mass gaseous-waste holdup system in heap after nuclear power plant accident, to improve nuclear power plant accident in the case of safety.
Technical scheme is as follows：Fused mass is detained in heap after a kind of nuclear power plant accident with heat conduction reactor pit exterior wall
System, including the pressure vessel being placed in reactor pit, the high-order storage of IVR working medium is provided with outside reactor pit higher than the position of pressure vessel
Case, IVR working medium high position container is connected by injection pipeline with reactor pit, is provided with outside water-cooled outside the good reactor pit exterior wall of heat conductivity
Wall, forms annular water corridor between the reactor pit exterior wall and water-cooled exterior wall, the annular water corridor is by circulation line and reactor
Put material-changing water tank to be connected.
Further, fused mass gaseous-waste holdup system in heap after the nuclear power plant accident with heat conduction reactor pit exterior wall as above, its
In, described circulation line includes the thermally coupled pipeline being connected with the built-in material-changing water tank of reactor respectively and cold connecting pipeline, institute
It is higher than the cold connecting pipeline to state thermally coupled pipeline arrangement absolute altitude.
Further, on the injection pipeline and thermally coupled pipeline, cold connecting pipeline of described IVR working medium high position container
It is respectively equipped with valve.
Further, fused mass gaseous-waste holdup system in heap after nuclear power plant accident as above, wherein, described IVR working medium is high
IVR working medium adopts gallium in the container of position.
Further, fused mass gaseous-waste holdup system in heap after nuclear power plant accident as above, wherein, described IVR working medium is high
The loading amount of IVR working medium should be able in the state of accident flood whole reactor pit in the container of position.
Beneficial effects of the present invention are as follows：The present invention is proposed using novel I VR working medium-gallium for traditional IVR system
, used as the cooling medium of direct cooling pressure container, because the boiling point of novel I VR working medium is far above water, thermal conductivity is high for water, while
Stable chemical nature, therefore the appearance of pressure vessel outer wall boiling crisis can be prevented effectively from, so that it is guaranteed that pressure vessel outer wall
Will not be by reactor core fused mass burn through.Meanwhile, the annular water corridor and its Accessory Members of present invention design can with effectively utilizes water from
So convection current reduces the temperature of IVR working medium in reactor pit, by the heat derives of IVR working medium to built-in material-changing water tank.The present invention can be with
IVR technical failures are effectively avoided, the safety of nuclear power station is improved.
Description of the drawings
Fig. 1 is the structural representation of fused mass gaseous-waste holdup system in heap of the present invention；
Fig. 2 is operation schematic diagram under the accident condition of fused mass gaseous-waste holdup system in heap of the present invention.
Specific embodiment
The present invention is described in detail with reference to the accompanying drawings and examples.
As shown in figure 1, after the nuclear power plant accident that provides of the present invention in heap fused mass gaseous-waste holdup system by pressure vessel 1, reactor pit
Exterior wall 2, water-cooled exterior wall 4, IVR working medium high position container 6, IVR working medium injection pipeline 7, IVR working medium injection pipeline valve 8, reaction
The built-in material-changing water tank 9 of heap, thermally coupled pipeline 10, thermally coupled pipeline valve 11, cold connecting pipeline 12,13 groups of cold connecting pipeline valve
Into.Wherein, reactor pit 3 is formed between the outer wall of pressure vessel 1 and reactor pit exterior wall 2；The material of reactor pit exterior wall 2 be the good steel of heat conductivity or
Other metals；Annular water corridor 5 is formed between reactor pit exterior wall 2 and water-cooled exterior wall 4；Annular water corridor 5 passes through reactor pit exterior wall 2 with reactor pit 3
Separate；The IVR working medium high position arrangement absolute altitude of container 6 is higher than pressure vessel 1 and reactor pit 3, and it is internal equipped with IVR working medium-metal
Gallium, the working medium has that boiling point is very high, thermal conductivity good, under stable chemical nature and room temperature (30 DEG C) for liquid the features such as, its dress
Amount should ensure that floods reactor pit 3 under accident condition；IVR working medium is injected the one end of pipeline 7 and is connected with IVR working medium high position container 6, one end
Opening extend into reactor pit 3；IVR working medium injection pipeline valve 8 is located on IVR working medium injection pipeline 7, nuclear power station normal operating condition
Lower closing, opens under accident condition；The one end of thermally coupled pipeline 10 is connected with annular water corridor 5, and one end open is extend in reactor
Put material-changing water tank 9；Thermally coupled pipeline valve 11 is located on thermally coupled pipeline 10, the nuclear power station normally lower closing of operation, accident condition
Lower unlatching；The one end of cold connecting pipeline 12 is connected with annular water corridor 5, and one end open extend into the built-in material-changing water tank 9 of reactor；Cold company
Pipeline valve 13 is connect in cold connecting pipeline 12, nuclear power station normally operation lower closing is opened under accident condition；Thermally coupled pipeline
10 arrangement absolute altitudes are higher than cold connecting pipeline 12；The built-in material-changing water tank 9 of reactor is equipped with water, and water loading amount should be sufficient under any state
With the opening absolute altitude that submerged heat connecting pipeline 10 stretches into built-in material-changing water tank 9.
System operation is as shown in Figure 2 under nuclear power plant accident state.When there is accident in nuclear power station, IVR working medium injection pipeline
Valve 8, thermally coupled pipeline valve 11 and cold connecting pipeline valve 13 are opened；Under gravity, IVR working medium high position container 6
In liquid IVR working medium pipeline 7 injected by IVR working medium be injected into reactor pit 3, the water of the built-in material-changing water tank 9 of reactor is by warm
Connecting pipeline 10 and cold connecting pipeline 12 are injected into annular water corridor 5；Reactor core fused mass in pressure vessel 1 passes through pressure vessel 1
Outer wall transfers heat to the IVR working medium in reactor pit 3；IVR working medium in reactor pit 3 transfers heat to ring by reactor pit exterior wall 2
Water in shape water corridor 5；Under by thermogenetic Effect of Nature Convection, the hot water in annular water corridor 5 is entered by thermally coupled pipeline 10
Enter material-changing water tank 9 built-in to reactor, the relatively low water of relative temperature is entered into by cold connecting pipeline 12 in built-in material-changing water tank 9
Annular water corridor 5, forms the closed circuit of a water.
Obviously, those skilled in the art can carry out the essence of various changes and modification without deviating from the present invention to the present invention
God and scope.So, if these modifications and modification to the present invention belong to the model of the claims in the present invention and its equivalent technology
Within enclosing, then the present invention is also intended to comprising these changes and modification.
Claims (4)
1. fused mass gaseous-waste holdup system in heap after a kind of nuclear power plant accident with heat conduction reactor pit exterior wall, including being placed in reactor pit (3)
Pressure vessel (1), it is characterised in that：IVR working medium high position container is provided with outside reactor pit higher than the position of pressure vessel (1)
(6) the IVR working medium in, described IVR working medium high position container (6) adopts gallium, IVR working medium high position container (6) to pass through
Injection pipeline (7) is connected with reactor pit (3), and outside the good reactor pit exterior wall (2) of heat conductivity water-cooled exterior wall (4), the reactor pit are provided with
Annular water corridor (5) is formed between exterior wall (2) and water-cooled exterior wall (4), the annular water corridor (5) is by circulation line and reactor
Put material-changing water tank (9) to be connected.
2. fused mass gaseous-waste holdup system in heap after the nuclear power plant accident with heat conduction reactor pit exterior wall as claimed in claim 1, it is special
Levy and be：Described circulation line includes the thermally coupled pipeline (10) that is connected with the built-in material-changing water tank of reactor (9) respectively and cold
Connecting pipeline (12), thermally coupled pipeline (10) the arrangement absolute altitude is higher than the cold connecting pipeline (12).
3. fused mass gaseous-waste holdup system in heap after the nuclear power plant accident with heat conduction reactor pit exterior wall as claimed in claim 2, it is special
Levy and be：In the injection pipeline (7) and thermally coupled pipeline (10), cold connecting pipeline (12) of described IVR working medium high position container
On be respectively equipped with valve (8,11,13).
4. fused mass is stagnant in heap after the nuclear power plant accident with heat conduction reactor pit exterior wall as described in any one in claim 1-3
Stay system, it is characterised in that：The loading amount of the described interior IVR working medium of IVR working medium high position container (6) should be able to flood in the state of accident
Not whole reactor pit.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410222132.9A CN104036833B (en) | 2014-05-23 | 2014-05-23 | In-pile melt retention system with thermal-conductive pile pit outer wall after nuclear power station accident |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410222132.9A CN104036833B (en) | 2014-05-23 | 2014-05-23 | In-pile melt retention system with thermal-conductive pile pit outer wall after nuclear power station accident |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104036833A CN104036833A (en) | 2014-09-10 |
| CN104036833B true CN104036833B (en) | 2017-05-10 |
Family
ID=51467572
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410222132.9A Active CN104036833B (en) | 2014-05-23 | 2014-05-23 | In-pile melt retention system with thermal-conductive pile pit outer wall after nuclear power station accident |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104036833B (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN108010591B (en) * | 2017-12-18 | 2024-01-19 | 中广核研究院有限公司 | Multifunctional pressure vessel pit stacking structure and reactor containment structure |
| RU2726226C1 (en) | 2019-12-30 | 2020-07-10 | Акционерное Общество "Научно-Исследовательский И Проектно-Конструкторский Институт Энергетических Технологий "Атомпроект" | Melt retention system in reactor housing |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN203950555U (en) * | 2014-05-23 | 2014-11-19 | 中国核电工程有限公司 | There is after the nuclear power plant accident of heat conduction reactor pit exterior wall fused mass gaseous-waste holdup system in heap |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BRPI0807366A2 (en) * | 2007-02-14 | 2014-05-13 | Heleos Technology Gmbh | PROCESS AND APPARATUS FOR TRANSFERING HEAT FROM A FIRST MEDIUM TO A SECOND MEDIUM |
| CN201570286U (en) * | 2009-11-25 | 2010-09-01 | 中科华核电技术研究院有限公司 | Reactor cavity injection system for nuclear power system |
| CN201689688U (en) * | 2010-06-04 | 2010-12-29 | 中科华核电技术研究院有限公司 | System for cooling reactor core, filling water in reactor cavity and guiding out heat of containment |
| CN202582287U (en) * | 2012-04-01 | 2012-12-05 | 合肥科烨电物理设备制造有限公司 | Two-stage gradient heat transfer heat exchanger |
-
2014
- 2014-05-23 CN CN201410222132.9A patent/CN104036833B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN203950555U (en) * | 2014-05-23 | 2014-11-19 | 中国核电工程有限公司 | There is after the nuclear power plant accident of heat conduction reactor pit exterior wall fused mass gaseous-waste holdup system in heap |
Also Published As
| Publication number | Publication date |
|---|---|
| CN104036833A (en) | 2014-09-10 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104021824B (en) | In-pile melts retention system after nuclear power station accident | |
| CN201689688U (en) | System for cooling reactor core, filling water in reactor cavity and guiding out heat of containment | |
| KR101242743B1 (en) | Integrated nuclear power plants using integral passive safety tank | |
| CN105810257B (en) | A kind of passive nuclear power station pressure release condensation heat exchange system | |
| CN105513649B (en) | A kind of grouping of reactor core fusant is detained and cooling system | |
| CN105047235A (en) | Melt in-pile retention passive cooling system in nuclear reactor severe accident state | |
| CN104361914A (en) | Passive safe cooling system | |
| CN105047236A (en) | Passive cooling system for retention of melts in serious accident state of reactor | |
| CN103632736B (en) | A kind of nuclear power station Reactor cavity flooding cooling system | |
| CN102623072A (en) | Compound accident residual heat removal system for accelerator-driven sub-critical reactor | |
| CN109147969A (en) | Nuclear reactor fusant reactor core is detained passive cooling system | |
| CN107331424B (en) | A kind of reactor cavity water filling cooling system and its operating method | |
| CN104269194A (en) | Temperature-triggered passive accident residual heat removal system for pool type reactor | |
| WO2014048290A1 (en) | Combined active and passive reactor cavity water injection cooling system | |
| CN110459333A (en) | A kind of double crucible reactor core fusant capturing device with internal cooling tube | |
| CN106328223B (en) | A kind of novel passive containment energy management system | |
| CN104036833B (en) | In-pile melt retention system with thermal-conductive pile pit outer wall after nuclear power station accident | |
| CN103928069B (en) | Containment built-in spent fuel pool | |
| WO2015010399A1 (en) | Reactor cavity water injection system and method for nuclear power plant | |
| CN109545401A (en) | A kind of lead base fast reactor out-pile passive residual heat removal system | |
| CN105551539A (en) | Reactor melt out-of-core retention system | |
| CN102568624A (en) | High-temperature supercritical nuclear reactor | |
| CN205451786U (en) | Reactor core melts trap with rib structure water -cooling wall | |
| CN105551541A (en) | Core melt grouping trapping and cooling system | |
| CN203950555U (en) | There is after the nuclear power plant accident of heat conduction reactor pit exterior wall fused mass gaseous-waste holdup system in heap |
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 |