CN203456100U - Device for improving critical heat flux density of outer wall surface of pressure vessel - Google Patents
Device for improving critical heat flux density of outer wall surface of pressure vessel Download PDFInfo
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- CN203456100U CN203456100U CN201320510717.1U CN201320510717U CN203456100U CN 203456100 U CN203456100 U CN 203456100U CN 201320510717 U CN201320510717 U CN 201320510717U CN 203456100 U CN203456100 U CN 203456100U
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- pressure vessel
- jut
- wall surface
- insulation layer
- heat
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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
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Abstract
The utility model discloses a device for improving the critical heat flux density of an outer wall surface of a pressure vessel. The device comprises the reactor pressure vessel and a thermal insulating layer wrapping the reactor pressure vessel, wherein a flow channel is formed between the outer wall surface of the reactor pressure vessel and the thermal insulating layer, and a plurality of projections fixed on the inner wall surface of the thermal insulating layer are arranged in the flow channel, are not in contact with one another and are arranged in the circumferential direction or in a stagger manner. According to the device disclosed by the utility model, the projections are arranged in a stagger manner to reinforce the roiling of fluid in the flow process, change the steam bubble accumulation in the outer wall surface of the reactor pressure vessel, enhance the heat exchange ability of the fluid and improve the critical heat flux density of the fluid at a corresponding position on the outer wall surface of the reactor pressure vessel, so that a measure of melt retention in a reactor of a nuclear power plant is carried out, and the safety of the nuclear power plant under an accident condition is improved. The device disclosed by the utility model is simple in structure, low in manufacturing cost, small in introduction resistance and high in system reliability.
Description
Technical field
The utility model relates to delay measure in nuclear power plant's fused mass heap, relates in particular to a kind of device that improves the outside critical heat flux density of pressure vessel.
Background technology
The WASH-1400 delivering for 1975 is reported in nuclear power plant is carried out pointing out after PRA analysis: the risk of nuclear power plant is not mainly from design basis accident, but from core melt down accident.For this reason, each main nuclear power country of the world all requires industry to carry out major accident research, seeks major accident countermeasure, to improve nuclear power plant, tackles major accident ability.
At present, according to major accident evolution feature, the strategy of many reply major accidents has been proposed in the world.Wherein, under nuclear plant severe accident, reactor core fused mass caves in to low head, may cause pressure vessel to lose efficacy, threaten containment integrity, thereby cause the serious consequence that occurs that radiomaterial leaks, so to keep pressure vessel integrality, reactor core molten product is remained in pressure vessel be one of emphasis of current severe accident relieving Study on Measures.A kind of important means as severe accident relieving measure, the strategy that reactor core fused mass is remained on to (In-Vessel Retention, IVR) in pressure vessel is adopted by the nuclear power station of many existing operations and many novel pressurized-water reactor nuclear power plants designing.
IVR measure refers to that nuclear power plant occurs, after major accident, by adopting a series of strategies or means, reactor core fused mass to be trapped in pressure vessel, to keep the integrality of pressure vessel, thereby major accident consequence is limited in a border, loop.Wherein the measure of a kind of IVR of realization is exactly pressure vessel external refrigeration, its specific strategy is: under the condition having an accident in nuclear power plant, water piii reactor is piled to chamber, reactor pressure vessel is dipped in water, water enters the coolant flow channel between pressure vessel and heat-insulation layer, cooling pressure container wall, take reactor core decay heat out of, avoided the inefficacy of pressure vessel, prevent further developing and worsening of major accident.Wherein, guarantee that it is that the actual heat flow density of pressure vessel wall must be less than local critical heat flux density that IVR measure successfully needs one of satisfied condition.That is to say, the critical heat flux density that improves reactor pressure vessel outside wall surface is vital for realizing IVR measure.
Therefore, those skilled in the art is devoted to develop a kind of device that improves the outside critical heat flux density of pressure vessel, for strengthening the validity of the interior delay measure of fused mass heap under major accident condition, to improve nuclear power plant's reply major accident ability.
Utility model content
Because the above-mentioned defect of prior art, a kind of device of stiring and make muddy fluid and increasing fluid flow-disturbing is provided in the outer coolant flow channel of technical problem to be solved in the utility model Shi nuclear power plant pressure vessel, the critical heat flux density of pressure vessel outside wall surface is improved, thereby strengthens the validity of the interior delay measure of fused mass heap under major accident condition.
For achieving the above object, the utility model provides a kind of device that improves pressure vessel outside wall surface critical heat flux density, comprises reactor pressure vessel, heat-insulation layer;
Heat-insulation layer is coated on the outside of reactor pressure vessel, and forms runner between reactor pressure vessel outside wall surface; Wherein,
Runner inside has jut, and described jut is located on heat-insulation layer internal face.
Preferably, the longitudinal section of jut is arc line shaped, and the contact jaw of jut and heat-insulation layer internal face is first end, and jut is the second end towards the end of pressure vessel outside wall surface;
First direction is along jut at the tangent line at first end place and point to the second end;
The straight-line segment region of the tangent line of the position that second direction contacts with jut along heat-insulation layer internal face and sensing heat-insulation layer internal face;
The angle of first direction and second direction is 5 °～80 °.
Preferably, the longitudinal section of jut is linear, and the contact jaw of jut and heat-insulation layer internal face is first end, and jut is the second end towards the end of pressure vessel outside wall surface;
First direction along jut at first end radial finger to the second end;
The straight-line segment region of the tangent line of the position that second direction contacts with jut along heat-insulation layer internal face and sensing heat-insulation layer internal face;
The angle of first direction and second direction is 5 °～80 °.
Further, the number of jut is at least one.
Further, between a plurality of juts, be not in contact with one another.
Further, a plurality of juts are along the circumferential distribution of heat-insulation layer internal face.
Further, a plurality of juts, in the circumferential distribution of described heat-insulation layer internal face, form a row or multi-row jut, and the arrangement mode of described many row's juts is arranged side by side or Heterogeneous Permutation.
Preferably, by being welded and fixed mode, adhering fixed mode, securing member fixed form or riveted joint fixed form, jut is fixedly installed on heat-insulation layer internal face.
Preferably, jut and heat-insulation layer are one-body molded.
Preferably, jut is fin.
In preferred embodiments of the present utility model, a kind of device that improves pressure vessel outside wall surface critical heat flux density is provided, comprise reactor pressure vessel and the heat-insulation layer that is coated on reactor pressure vessel outside, between reactor pressure vessel outside wall surface and heat-insulation layer, form runner, the inside of runner is provided with a plurality of juts that are fixed on heat-insulation layer internal face, the angle of the tangential direction of the tangential direction of the first end of jut and place heat-insulation layer internal face is 5 °～80 °, does not contact mutually, is circumferential array or Heterogeneous Permutation between a plurality of juts.
As can be seen here, the device of the outside critical heat flux density of raising nuclear power plant's pressure vessel of the present utility model, by being provided with the jut being fixed on heat-insulation layer internal face in the runner between pressure vessel outside wall surface and heat-insulation layer, forms certain angle with carrying out flow path direction.When fluid is flowed through jut, at jut first end or downstream area, form eddy current, thereby stiring and make muddy in can enhance fluid flow process, the cold and hot layering of fluid that destruction causes due to flow channel shape and fluid heating mode, the arrangement mode that is particularly dislocation, further strengthened stiring and make muddy of fluid, changed the accumulation phenomena of steam bubble in pressure vessel outside wall surface, the exchange capability of heat of enhance fluid, improve fluid at the critical heat flux density of pressure vessel outside wall surface corresponding position, thereby be conducive to implement fused mass in nuclear power plant's heap and be detained measure, improve the security of nuclear power plant under accident conditions.
In addition, the device of the outside critical heat flux density of raising nuclear power plant's pressure vessel of the present utility model, jut can be fixed on heat-insulation layer internal face by being welded and fixed the modes such as mode, adhering fixed mode, securing member fixed form, riveted joint fixed form or impact briquetting, also can be one-body molded with heat-insulation layer internal face, there is simple in structure, low cost of manufacture, the high feature of introducing resistance reliability little, apparatus system.
Below with reference to accompanying drawing, the technique effect of design of the present utility model, concrete structure and generation is described further, to understand fully the purpose of this utility model, feature and effect.
Accompanying drawing explanation
Fig. 1 is in a preferred embodiment, the longitudinal section of the structure of the device of the outside critical heat flux density of raising pressure vessel of the present utility model;
Fig. 2 has shown the position relationship between heat-insulation layer and jut in a preferred embodiment shown in Fig. 1;
Fig. 3 has shown the position relationship between heat-insulation layer and jut in another preferred embodiment shown in Fig. 1;
Fig. 4 is the stereographic map of the device of the outside critical heat flux density of raising pressure vessel of the present utility model;
Fig. 5 is the top view of the device of the outside critical heat flux density of the raising pressure vessel shown in Fig. 4.
Embodiment
As shown in Figure 1, a kind of device that improves the outside critical heat flux density of nuclear power plant's pressure vessel, comprises reactor pressure vessel 1 and the heat-insulation layer 2 that is coated on reactor pressure vessel outside, between reactor pressure vessel 1 outside wall surface and heat-insulation layer 2, forms runner 3.Wherein, the interface that we define 3 of reactor pressure vessel 1 and runners is pressure vessel 1 outside wall surface.
Runner 3 inside are provided with the jut 4 being fixed on heat-insulation layer 2 internal faces.Equally, definition heat-insulation layer 2 internal faces are the interface of 3 of heat-insulation layer 2 and runners.
The number of jut 4 is at least one, is fixedly installed on the segmental arc region of heat-insulation layer 2 internal faces, also can be fixedly installed near the internal face of the segmental arc internal face of heat-insulation layer 2 and the join domain of straight-line segment internal face.
As shown in Figure 2, shown the position relationship between heat-insulation layer 2 and jut 4 in a preferred embodiment shown in Fig. 1, the longitudinal section of jut can be linear.We are defined on view, and jut 4 is first end 5 with the contact jaw of heat-insulation layer 2 internal faces, and jut 4 is the second end 6 towards the end of pressure vessel outside wall surface.The first end 5 of definition jut 4 is first direction 7 along the radial direction of straight line, points to the second end 6 of jut 4; The tangential direction of the heat-insulation layer internal face location point that definition contacts with jut 4 is second direction 8, points to the straight-line segment region of heat-insulation layer internal face.First direction 7 is 5 °～80 ° with the angle β of second direction 8.The direction of arrow represents the flow path direction that comes of fluid.
As shown in Figure 3, shown the position relationship between heat-insulation layer 2 and jut 41 in another preferred embodiment shown in Fig. 1, the longitudinal section of jut can be arc line shaped.Equally, we are defined on view, and jut 41 is first end 5 with the contact jaw of heat-insulation layer 2 internal faces, and jut 41 is the second end 6 towards the end of pressure vessel outside wall surface.The tangential direction of the first end 5 of definition jut 41 is first direction 7, points to the second end 6 of jut 4; The tangential direction of the heat-insulation layer internal face location point that definition contacts with jut 41 is second direction 8, points to the straight-line segment region of heat-insulation layer internal face.First direction 7 is 5 °～80 ° with the angle β of second direction 8.The direction of arrow represents the flow path direction that comes of fluid.
As shown in Figure 4 and Figure 5, be respectively stereographic map and the top view of the device of the outside critical heat flux density of raising pressure vessel of the present utility model.Can see, jut 42 can distribute and be circumferential array along heat-insulation layer 2 internal faces, between a plurality of juts 42, does not mutually contact.In addition, the circumferential array of jut 42 on heat-insulation layer 2 internal faces can be a row, also can be many row's arrangement modes.Many row's arrangement modes can be the arrangement that (do not misplace) side by side, can be also Heterogeneous Permutation.Wherein, described Heterogeneous Permutation comprises two kinds of situations: the first, and for any two juts 42, the angle of first direction and second direction is different; The second, along circumferential any two row's juts 42 not on same longitudinal section.Certainly, described Heterogeneous Permutation can be also the combination of above-mentioned two kinds of modes.
Jut 4 is fixed on the technique of heat-insulation layer 2 internal faces can be for being welded and fixed mode, can be for being adhesively fixed, securing member is fixed or rivet the modes such as fixing, and can be also jut 4 and the one-body molded mode of heat-insulation layer 2, but be not limited to this.
Preferably, can be referring to Fig. 2, jut 4 can, for being the fin of flat triangle, be fixedly installed on the segmental arc region of heat-insulation layer 2 internal faces.The direction of arrow represents the flow path direction that comes of fluid.The number of fin 4 is at least one, along heat-insulation layer 2 internal faces, distributes and is circumferential array, between a plurality of fins 4, is not in contact with one another.Fin 4 is arranged being upwards many rows the week of heat-insulation layer 2 internal faces, and arrangement mode is for side by side or Heterogeneous Permutation (can referring to Figure 4 and 5).The first direction of fin 42 is 5 °～80 ° with the angle β of the second direction at be fixedly connected with heat-insulation layer 2 internal face places.
The material of fin 4 and the selection of structure, guarantee that shape does not change or subtle change only occurs under normal running environment condition (as hot environment).The technique for fixing of fin 4 and described heat-insulation layer 2 internal faces can be for being welded and fixed mode, can be for being adhesively fixed, securing member is fixed or rivet the modes such as fixing, and can be also jut 4 and the one-body molded mode of heat-insulation layer 2, but be not limited to this.
The device of the outside critical heat flux density of raising nuclear power plant's pressure vessel of the present utility model, by being provided with the flat shaped tabs portion 4 being fixed on heat-insulation layer 2 internal faces in the runner 3 between pressure vessel 1 outside wall surface and heat-insulation layer 2, forms certain angle with carrying out flow path direction.When there is major accident in nuclear power plant, core meltdown and caving in, fused mass is gathered in pressure vessel 1 low head gradually, between pressure vessel 1 outside wall surface and heat-insulation layer 2, form runner, fluid this runner of flowing through, absorption of fluids pressure vessel 1 heat, cooling pressure container 1.When fluid is flowed through jut 4, at jut 4 downstream areas, form eddy current, thereby stiring and make muddy in can enhance fluid flow process, the cold and hot layering of fluid that destruction causes due to flow channel shape and fluid heating mode, changed the phenomenon that the outside steam bubble of pressure vessel 1 gathers, particularly jut 4 of the present utility model is when being flat, and each jut 4 is not in contact with one another, reduced resistance to flow, each is arranged jut 4 and is dislocation layout, fluid is stired and make muddy and is further enhanced, thereby the critical heat flux density of pressure vessel 1 outside wall surface corresponding position is improved, be conducive to implement fused mass in nuclear power plant's heap and be detained measure, thereby improve the security of nuclear power plant under accident conditions.
What it will be appreciated by those skilled in the art that is, the shape of jut 4 is except being the triangle of flat, can also be quadrilateral, circular arc or other shapes, also can be cone-shaped, the geomery of the first end that jut 2 is connected with heat-insulation layer 4 internal faces is greater than the geomery etc. at the top of jut 2, in this no limit, only need reach in the utility model when the fluid jut of flowing through, realize the effect of disturbing and stiring and make muddy fluid.
The material of jut 4 can be identical with heat-insulation layer 2, can be for stainless steel material, also can be other material etc., in this no limit, only need guarantee that the shape of jut 4 does not change or subtle change only occurs under normal running environment condition (as hot environment).
Jut 4 with the technique for fixing of described heat-insulation layer 2 internal faces for being welded and fixed mode or impact briquetting mode, also can for jut 4 and heat-insulation layer 2 one-body molded, but be not limited to this.Can find out, jut 4 is in the fixing and fixed form of heat-insulation layer 2 internal faces, and simple in structure, low cost of manufacture, introducing resistance is little, system reliability is high.
More than describe preferred embodiment of the present utility model in detail.The ordinary skill that should be appreciated that this area just can be made many modifications and variations according to design of the present utility model without creative work.Therefore, all technician in the art comply with design of the present utility model on the basis of existing technology by the available technical scheme of logical analysis, reasoning, or a limited experiment, all should be in the determined protection domain by claims.
Claims (10)
1. improve a device for pressure vessel outside wall surface critical heat flux density, comprise reactor pressure vessel, heat-insulation layer;
Described heat-insulation layer is coated on the outside of described reactor pressure vessel, and forms runner between described reactor pressure vessel outside wall surface;
It is characterized in that,
Described runner inside has jut, and described jut is located on heat-insulation layer internal face.
2. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 1, wherein, the longitudinal section of described jut is arc line shaped, the contact jaw of described jut and described heat-insulation layer internal face is first end, and described jut is the second end towards the end of described pressure vessel outside wall surface;
First direction is along described jut at the tangent line at described first end place and point to described the second end;
The tangent line of the position that second direction contacts with described jut along described heat-insulation layer internal face and point to the straight-line segment region of described heat-insulation layer internal face;
The angle of described first direction and described second direction is 5 °～80 °.
3. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 1, wherein, the longitudinal section of described jut is linear, the contact jaw of described jut and described heat-insulation layer internal face is first end, and described jut is the second end towards the end of described pressure vessel outside wall surface;
First direction along described jut at described first end radial finger to described the second end;
The tangent line of the position that second direction contacts with described jut along described heat-insulation layer internal face and point to the straight-line segment region of described heat-insulation layer internal face;
The angle of described first direction and described second direction is 5 °～80 °.
4. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 1, wherein, the number of described jut is at least one.
5. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 4, comprising a plurality of described juts, is not in contact with one another between described a plurality of juts.
6. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 5, wherein, described a plurality of juts are along the circumferential distribution of described heat-insulation layer internal face.
7. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 5, wherein, described a plurality of jut, in the circumferential distribution of described heat-insulation layer internal face, forms a row or multi-row jut, and the arrangement mode of described many row's juts is arranged side by side or Heterogeneous Permutation.
8. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 1, wherein, by being welded and fixed mode, adhering fixed mode, securing member fixed form or riveted joint fixed form, described jut is fixedly installed on described heat-insulation layer internal face.
9. the device of raising pressure vessel outside wall surface critical heat flux density as claimed in claim 1, wherein, described jut and described heat-insulation layer are one-body molded.
10. the device of the raising pressure vessel outside wall surface critical heat flux density as described in claim 1 to 9 any one, wherein, described jut is fin.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320510717.1U CN203456100U (en) | 2013-08-20 | 2013-08-20 | Device for improving critical heat flux density of outer wall surface of pressure vessel |
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| CN201320510717.1U CN203456100U (en) | 2013-08-20 | 2013-08-20 | Device for improving critical heat flux density of outer wall surface of pressure vessel |
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| CN203456100U true CN203456100U (en) | 2014-02-26 |
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| CN201320510717.1U Expired - Lifetime CN203456100U (en) | 2013-08-20 | 2013-08-20 | Device for improving critical heat flux density of outer wall surface of pressure vessel |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103578583A (en) * | 2013-10-24 | 2014-02-12 | 清华大学 | Boiling heat transfer enhancement runner outer shell with flow guide component |
| CN105041010A (en) * | 2015-08-24 | 2015-11-11 | 华北电力大学 | Floating point type passive nuclear containment with super-hydrophobic surface |
| CN106531251A (en) * | 2016-11-21 | 2017-03-22 | 华东理工大学 | Pressure vessel lower gland heat flux quenching testing system having motion control function |
| 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 |
-
2013
- 2013-08-20 CN CN201320510717.1U patent/CN203456100U/en not_active Expired - Lifetime
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103578583A (en) * | 2013-10-24 | 2014-02-12 | 清华大学 | Boiling heat transfer enhancement runner outer shell with flow guide component |
| CN103578583B (en) * | 2013-10-24 | 2016-02-10 | 清华大学 | A kind of enhanced boiling heat transfer runner shell body with air guide |
| CN105041010A (en) * | 2015-08-24 | 2015-11-11 | 华北电力大学 | Floating point type passive nuclear containment with super-hydrophobic surface |
| CN106531251A (en) * | 2016-11-21 | 2017-03-22 | 华东理工大学 | Pressure vessel lower gland heat flux quenching testing system having motion control function |
| 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 |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder | ||
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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 |
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| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20140226 |