CN202917186U - Accident alleviating device and pressure vessel used in nuclear power station - Google Patents
Accident alleviating device and pressure vessel used in nuclear power station Download PDFInfo
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- CN202917186U CN202917186U CN2012205810463U CN201220581046U CN202917186U CN 202917186 U CN202917186 U CN 202917186U CN 2012205810463 U CN2012205810463 U CN 2012205810463U CN 201220581046 U CN201220581046 U CN 201220581046U CN 202917186 U CN202917186 U CN 202917186U
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- pressure vessel
- micromechanism
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- mitigation device
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The utility model discloses a serious accident alleviating device for a nuclear power station, which can enhance boiling heat transfer property when a serious accident occurs in the nuclear power station. The device capable of enhancing the boiling heat transfer property is positioned on the outer surface of a lower sealing head of a pressure vessel. By utilizing the principle that capillary force can be amplified by roughness, the device improves the high-efficiency hydrophilicity of a silicon crystal microstructure, prevents bubbles from covering the outer surface of the lower sealing head of the pressure vessel, improves the degree of wetness, moisture capacity and heat transfer area of the pressure vessel, increases the density of critical heat flux of the pressure vessel and enhances the heat transfer effect, so as to more effectively take away decay heat of reactor core melt, effectively alleviate or avoid the phenomenon that the pressure vessel is melt through, keep the integrity of the pressure vessel, alleviate the consequence of the serious accident of the nuclear power station and reduce the damage degree of the accident. The utility model further discloses the pressure vessel provided with the accident alleviating device and used in the nuclear power station.
Description
Technical field
The utility model relates to the nuclear plant safety field, particularly strengthens the nuclear power plant accident relieving apparatus of boiling heat transfer performance during nuclear power station generation major accident, and the nuclear plant pressure vessels with this accident mitigation device.
Background technology
After the Fukushima, Japan nuclear accident occured, nuclear plant safety was paid close attention to more and more widely.It is one of important goal of Severe accident management that the integrality of pressure vessel guarantees.Pressure vessel is being born the function of being detained fused mass and containing radiomaterial as the second barrier important component part of radioactive fission product in the major accident situation of reactor core melting.
Fused mass is detained whether successfully depend on two key factors in the pressure vessel: whether (1) pressure vessel wall departure nucleate boiling occurs; (2) under accident conditions, whether pressure vessel wall residual thickness bears its physical strength, such as thermal stress, pressure etc.Therefore, under accident conditions, reduce the bubble of Surface Pressure Vessel, enlarge the contact area of pressure vessel outer wall and heat eliminating medium, strengthen the critical heat flux density of pressure vessel boiling heat transfer, timely and effectively the heat of the inner reactor core fused mass of pressure vessel being derived is assurance pressure vessel integrality, the minimizing radiomaterial is to containment and alleviate migration, reduce containment integrity loses one of key measure of risk.
The utility model content
The purpose of this utility model is to propose a kind of accident mitigation device of the boiling heat transfer performance of pressure vessel when strengthening nuclear plant severe accident.
Strengthen boiling heat transfer performance invests pressure vessel with the accident mitigation device of alleviating nuclear plant severe accident low head outside surface, utilize roughness to amplify the principle of capillary force, improve the efficient water wettability of silicon crystal micromechanism, avoid bubble to cover the low head outside surface of pressure vessel, enlarge simultaneously its degree of wetting and wettability power and heat transfer area, the critical heat flux density of adherence pressure container, strengthen the effect of conducting heat, and then can more effectively take away the decay heat of reactor core fused mass, avoid or the container of releasing the pressure by burn through, keep the integrality of pressure vessel, alleviate the nuclear plant severe accident consequence, reduce the harm of major accident.
Another purpose of the present utility model provides a kind of nuclear plant pressure vessels, and it has utilized above-mentioned accident mitigation device.
According to an aspect of the present utility model, a kind of accident mitigation device for nuclear plant pressure vessels has been proposed, comprise: thermal-conductivity substrate, be provided with the water wettability micromechanism on the surface of described substrate, described micromechanism increases the contact area with heat eliminating medium.Favourable, described micromechanism is Si micromechanism or SiO
2Micromechanism.Described micromechanism can be formed by a plurality of outstanding cylinders.
Described micromechanism can have at least a array in array of cylinders, triangulo column array, the polygon cylinder array.
Described micromechanism can have array of cylinders, and in described array of cylinders, cylindrical height is between 10 microns-5 millimeters, and diameter is between 5 microns-3 millimeters, and adjacent column body centre distance is 1.5 times-3 times of cylinder diameter.
Optionally, described micromechanism is formed by a plurality of holes or a plurality of groove.Favourable, the bottom that the bottom in described hole is formed with inverted cone surface or described groove is formed with the inclined-plane.Can become the angles between 50 degree-60 degree between described inverted cone surface or described inclined-plane and the surface level.
Optionally, described micromechanism is the Si micromechanism, and the thickness of described Si micromechanism is between 20 microns-10mm.
Optionally, described accident mitigation device also comprises thermal conductive material layer, is fixed on another surface relative with a described surface of described substrate.Favourable, described thermal conductive material layer is made by Cu, Ag, Al or ZnO.Further, described thermal conductive material layer is made by Cu, and the thickness of described thermal conductive material layer is between 1 micron-20 microns.
According on the other hand of the present utility model, a kind of nuclear plant pressure vessels has been proposed, comprising: container body has the low head that is arranged on the container body below; And above-mentioned accident mitigation device, described thermal-conductivity substrate is arranged at least a portion of outside surface of described low head the contact area with the heat eliminating medium of the outside surface that increases described low head and pressure vessel.
Favourable, described thermal-conductivity substrate has the shape of the outside surface of the low head that is adapted to pressure vessel.The arc of the outside surface of described low head or sphere outside surface can all be coated with described thermal-conductivity substrate.
Described pressure vessel can be nuclear power plant containment shell, and described micromechanism strengthens boiling heat transfer performance.
Utilize the technical solution of the utility model, can be under accident conditions, reduce the bubble of the low head outside surface of pressure vessel, enlarge the contact area of outside surface (or outer wall) with the heat eliminating medium of pressure vessel, strengthen the critical heat flux density of pressure vessel boiling heat transfer, timely and effectively the heat of the inner reactor core fused mass of pressure vessel is derived, thus help to guarantee pressure vessel integrality, reduce containment integrity forfeiture risk.
Description of drawings
Fig. 1 is that wherein the accident mitigation Plant arrangement is on the outside surface of the low head of pressure vessel according to the schematic diagram of the nuclear power plant accident relieving apparatus of the enhancing boiling heat transfer performance of an exemplary embodiment of the present utility model;
Fig. 2 is the local enlarged diagram of the A part among Fig. 1;
Fig. 3 is the process chart of manufacturing according to the accident mitigation device of the enhancing boiling heat transfer performance of an exemplary embodiment of the present utility model, and wherein, Fig. 3 a-Fig. 3 i shows respectively different manufacturing steps.
Embodiment
The below describes the embodiment of exemplary of the present utility model in detail, and the example of embodiment is shown in the drawings, and wherein same or analogous label represents same or analogous element.The embodiment that describes below with reference to accompanying drawing is exemplary, is intended to explain the utility model, and can not be interpreted as restriction of the present utility model.
When reactor generation core meltdown major accident, rely on gravity or pump to be injected between pressure vessel outer wall and its heat-insulation layer from containment inside or outside chilled water, chilled water is by cooling pressure container low head and barrel outer surface, efficiently take away the reactor core fused mass waste heat of pressure vessel low head, avoid the pressure vessel burn through as far as possible, prevent from that reactor core fused mass and concrete floor from reacting to produce the containment that non-condensable gas and inflammable gas cause and fire or slow superpressure; Avoid simultaneously the low head burn through can prevent that the interior chilled water of reactor core fused mass and reactor pit from directly contacting, and occurs in order to avoid cause vapour explosion.Therefore, fused mass cooling with hold that to stay in the reactor vessel be a key measure of alleviating damage sequence.When the pressure vessel outside there was not by water logging, the damage mechanism that hot melt is worn was boiling crisis, and it occurs in the critical heat flux that the low head thermoflux surpasses this place, then turns to film boiling from nucleateboiling suddenly.The feature of film boiling is to have very low heat transfer coefficient, causes the wall surface temperature greatly to raise.At high temperature, the low head inwall at first begins corrode, and along with wall thickness reduction, low head is tending towards creep failure gradually under fused mass gravity and high temperature double action.Therefore, must guarantee that the heat flow density of chamber wall part is less than critical heat flux density.Only have boiling crisis does not occur, and in container, in the low pressure situation, just can not occur to cause structural failure because of Thermal Load lower wall thickness attenuate.
The nuclear plant severe accident relieving apparatus that strengthens boiling heat transfer performance be utilize have the effect of silicon crystal micromechanism capillary water absorption and efficiently water-wet behavior develop a kind of simple in structure, cost is controlled, the nuclear plant severe accident relieving apparatus of easy mass production.It is compared with general heat-transfer equipment, the heat transfer sheet area that contacts with heat eliminating medium in the size situation of formed objects can enlarge several times, simultaneously can avoid bubble to cover the low head outside surface of pressure vessel, strengthen its degree of wetting and wettability power, the critical heat flux density of adherence pressure container, strengthen the effect of conducting heat, and then can more effectively take away the decay heat of reactor core fused mass, effectively alleviate or avoid pressure vessel by burn through, keep the integrality of pressure vessel, alleviate the nuclear plant severe accident consequence, the extent of injury of reduction accident.
Fig. 1 is nuclear power station (seriously) accident mitigation device 10 schematic diagram that strengthen boiling heat transfer performance, and this accident mitigation device 10 is arranged on the outside surface of low head 8 of pressure vessel.Fig. 2 is the local enlarged diagram of the A part among Fig. 1.
The innermost layer is pressure vessel low head 8 among Fig. 2, and copper plate 7 plays the effect of Si layer (or substrate) 1 being fixed and is connected to the pressure vessel low head.The column Si layer structure of microstructure is attached to the outside surface of pressure vessel low head, form have efficient water wettability, area that expansion contacts with heat eliminating medium and the exchange heat layer of enhancing critical heat flux density.
It should be noted that microstructure or micromechanism in the utility model represent can prevent the structure that bubble adsorbs based on the driving of capillary force.Water wettability in the utility model is illustrated on this micromechanism or the microstructure, and bubble is easily wetted and break away from microstructure or micromechanism.Growth phase at bubble, making a concerted effort and the momentum force balance of the surface force of bubble and buoyancy, in microstructure or micromechanism, because the driving of capillary force, can prevent that bubble is adsorbed on microstructure or the micromechanism, therefore, constantly wetted rear disengaging microstructure or micromechanism of bubble.
Fig. 3 is the process chart of making nuclear power station (seriously) the accident mitigation device that strengthens boiling heat transfer performance.Processing step is: at first, as shown in Fig. 3 a-3c, covering protection material layer 2 on silicon base 1, protective material becomes 2 for adopting the aluminium lamination of sputter formation, thickness is 100nm-950nm, need to be worked at the figure of etching on the silicon base 1 on the protective material layer 2 with Micrometer-Nanometer Processing Technology, the degree of depth of figure arrives silicon base 1 surface; Then, as shown in Fig. 3 d, for example use in silicon base 1 that deep reaction ion etching method (DRIE) vertically etches figure, the degree of depth is for can be 10 μ m-10mm; Then, as shown in Fig. 3 e, (participate in Fig. 3 d) on formed column surface 3 and coat photoresist 4; Afterwards, for example adopt wet corrosion technique, utilize HF, NH
4With the mixed liquor of water, carry out wet etching from the column bottom, the inclined-plane 5 that erodes away is 50 °-60 ° with the angle of surface level, as shown in Fig. 3 f; As shown in Fig. 3 g, adopt phosphoric acid solution to remove the protective material layer 2 of column top surface; Afterwards, as shown in Fig. 3 h, be 100nm-300nm copper seed layer 6 at silica-based bottom surface sputter thickness; At last, as shown in Fig. 3 i, electroplating thickness is the copper layer 7 of 1 μ m-20 μ m.
Si layer microstructure as shown in Figure 3 comprises substrate and the back taper microstructure that is etched in substrate inside, the cylindricality microstructure that is etched in base upper portion and the plating copper layer in silica-based bottom surface.This cylindricality microstructure is array arranges, and highly is 10 μ m-5mm, and diameter is 5 μ m-3mm, and the 1.5-3 that adjacent cylinder centre distance is diameter doubly.The inclined-plane of back taper microstructure and the angle of surface level are 50 °-60 °.This structure is utilized the wetting property of liquid, makes the pressure equilibrium of buoyancy, surface tension, gravity and the liquid internal of liquid, thereby makes liquid infiltration in each small part of device, strengthens its degree of wetting and wettability power.
The utility model relates to a kind of accident mitigation device for nuclear plant pressure vessels, comprise: thermal-conductivity substrate 1, be provided with water wettability micromechanism (for example microcylinder with surface 3 in Fig. 3 g-3i and the conical surface body with inclined-plane 5 between the microcylinder) on the surface of described substrate 1 (for example upper surface among Fig. 3), described micromechanism can increase the contact area with heat eliminating medium.
Except utilizing Si to form the above-mentioned micromechanism, can also use SiO
2And other any suitable Heat Conduction Materials of making this micromechanism consist of substrate 1 or form above-mentioned micromechanism.
Described micromechanism can be formed by a plurality of outstanding cylinders.Described micromechanism has at least a array in array of cylinders, triangulo column array, the polygon cylinder array.
Optionally, described micromechanism can be formed by a plurality of holes or a plurality of groove.Further, the bottom that also can be formed with inverted cone surface or described groove, the bottom in described hole also can be formed with the inclined-plane.Become the angles between 50 degree-60 degree between described inverted cone surface or described inclined-plane and the surface level.
When micromechanism was the Si micromechanism, the thickness of Si micromechanism can be between 20 microns-10mm.
The accident mitigation device can also comprise thermal conductive material layer (corresponding to copper seed layer 6 and copper layer 7), is fixed on another surface (being the lower surface among Fig. 3) relative with a described surface of described substrate 1.Except Cu, thermal conductive material layer can also be made by Ag, Al or ZnO.
The utility model also relates to nuclear plant pressure vessels, comprising: container body, container body have the low head 8 (referring to Fig. 1) that is arranged on the container body below; And above-mentioned accident mitigation device 10, described thermal-conductivity substrate is arranged at least a portion of outside surface of described low head the contact area with the heat eliminating medium of the outside surface that increases described low head and pressure vessel.As shown in fig. 1, described thermal-conductivity substrate 1 has the shape of the outside surface of the low head 8 that is adapted to pressure vessel.Favourable, the arc of the outside surface of described low head 8 or sphere outside surface all are coated with described thermal-conductivity substrate 1.
The utility model also discloses the method that a kind of manufacturing is used for the accident mitigation device 10 of nuclear plant pressure vessels, comprises step: provide Si or SiO
2Substrate 1; Form water wettability micromechanism (for example microcylinder with surface 3 in Fig. 3 g-3i and the conical surface body with inclined-plane 5 between the microcylinder) on a surface of described substrate 1 (for example upper surface among Fig. 3), described micromechanism increases the contact area with heat eliminating medium.Described micromechanism is formed by a plurality of outstanding cylinders.Described micromechanism has at least a array in array of cylinders, triangulo column array, the polygon cylinder array.
In forming the step of micromechanism, at the upper surface of substrate protective material layer 2 is set, described protective material layer 2 is formed with etched pattern; Based on described etched pattern, utilize the deep reactive ion etch method to etch a plurality of vertical holes or groove at the upper surface of described substrate 1.
The step that forms micromechanism also can comprise step: at the upright side walls coating photoresist 4 of described vertical hole or groove; Adopt wet corrosion technique, utilize HF, NH
4With the mixed liquid of water, carry out wet etching from the bottom of described vertical hole or groove.In the wet etching step, the mol ratio of HF, NH4 and water can be at 2: 7: 40-2: between 12: 63.In the wet etching step, the reaction time can between 2.5 minutes to 6.5 minutes and temperature of reaction can be between 14 degrees centigrade-28 degrees centigrade.In the step of wet etching, the inclined-plane that erodes away in described bottom and the angle of surface level are between 50 degree-60 degree.
The degree of depth of described vertical hole or groove can be between 10 microns-5 millimeters.
In said method, can be in described substrate 1 with lower surface above-mentioned thermal conductive material layer (corresponding to copper seed layer 6 and copper layer 7) is set.
The step that thermal conductive material layer is set comprises step: sputter copper seed layer 6 on the lower surface of substrate 1; Copper electroplating layer 7 on described copper seed layer 6.In the step of sputter copper seed layer, the thickness of described copper seed layer 6 is between 100 nanometers-300 nanometer; In the step of copper electroplating layer, electroplating current is that 0.3-3A and electroplating time are 5 minutes-120 minutes, and the thickness of copper layer 7 is between 1 micron-20 microns.
Optionally, at sputter copper layer on the lower surface of described substrate 1 until the thickness of this copper layer between 1 micron-20 microns.
The utility model has following beneficial effect with respect to prior art:
1, nuclear power station (seriously) the accident mitigation device of the utility model enhancing boiling heat transfer performance has controlled geometry, the process repeatability energy is high and mechanical stability is strong.This structure is utilized the wetting property of liquid, makes the pressure equilibrium of buoyancy, surface tension, gravity and the liquid internal of liquid, thereby makes liquid infiltration in each small part of device.
2, the utility model adopts the characteristics that the deep reaction ion etching dry etching combines with wet etching; protective material layer 2 can be avoided in dry etching the etching to silicon substrate 1; photoresist 4 can avoid in wet etching solution to the etching of column surface 3; has lower equipment cost; easily batch production can be widely used in the heat transfer equipment field.
3, the utility model makes that liquid and heat exchanger surface are long-pending fully to be contacted, strengthen wettability, avoid bubble in the boiling heat transfer process to be attached to the exchange that equipment surface hinders heat, the more general traditional heat transmission equipment of heat interchanging area enlarges several times simultaneously, significantly improve critical heat flux density, can effectively carry out the heat radiation of high heat flux equipment.
Although illustrated and described embodiment of the present utility model, for the ordinary skill in the art, be appreciated that in the situation that do not break away from principle of the present utility model and spirit can change these embodiment.The scope of application of the present utility model is limited by claims and equivalent thereof.
Claims (17)
1. an accident mitigation device that is used for nuclear plant pressure vessels comprises thermal-conductivity substrate, wherein:
Be provided with the water wettability micromechanism on the surface of described substrate, described micromechanism increases the contact area with heat eliminating medium.
2. accident mitigation device according to claim 1, wherein:
Described micromechanism is Si micromechanism or SiO
2Micromechanism.
3. accident mitigation device according to claim 2, wherein:
Described micromechanism is formed by a plurality of outstanding cylinders.
4. accident mitigation device according to claim 3, wherein:
Described micromechanism has at least a array in array of cylinders, triangulo column array, the polygon cylinder array.
5. accident mitigation device according to claim 4, wherein:
Described micromechanism has array of cylinders, and in described array of cylinders, cylindrical height is between 10 microns-5 millimeters, and diameter is between 5 microns-3 millimeters, and adjacent column body centre distance is 1.5 times-3 times of cylinder diameter.
6. accident mitigation device according to claim 1, wherein:
Described micromechanism is formed by a plurality of holes or a plurality of groove.
7. accident mitigation device according to claim 6, wherein:
The bottom that the bottom in described hole is formed with inverted cone surface or described groove is formed with the inclined-plane.
8. accident mitigation device according to claim 7, wherein:
Become the angles between 50 degree-60 degree between described inverted cone surface or described inclined-plane and the surface level.
9. accident mitigation device according to claim 2, wherein:
Described micromechanism is the Si micromechanism, and the thickness of described Si micromechanism is between 20 microns-10mm.
10. accident mitigation device according to claim 1 also comprises:
Thermal conductive material layer is fixed on another surface relative with a described surface of described substrate.
11. accident mitigation device according to claim 10, wherein:
Described thermal conductive material layer is the copper layer, and thickness is between 1 micron-20 microns.
12. a nuclear plant pressure vessels comprises:
Container body comprises the low head that is arranged on the container body below; And
According to claim 1, each described accident mitigation device-9, described thermal-conductivity substrate are arranged at least a portion of outside surface of described low head the contact area with the heat eliminating medium of the outside surface that increases described low head and pressure vessel.
13. pressure vessel according to claim 12, wherein:
Described thermal-conductivity substrate has the shape of the outside surface of the low head that is adapted to pressure vessel.
14. pressure vessel according to claim 13, wherein:
The arc of the outside surface of described low head or sphere outside surface all are coated with described thermal-conductivity substrate.
15. pressure vessel according to claim 14, wherein:
Described pressure vessel is nuclear power plant containment shell, and described micromechanism strengthens boiling heat transfer performance.
16. pressure vessel according to claim 12, wherein:
Described accident mitigation device is for according to claim 10 or 11 described accident mitigation devices.
17. pressure vessel according to claim 16, wherein:
Described thermal-conductivity substrate is arranged at least a portion of outside surface of described low head the contact area with the heat eliminating medium of the outside surface that increases described low head and pressure vessel via described thermal conductive material layer.
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| CN2012205810463U CN202917186U (en) | 2012-11-06 | 2012-11-06 | Accident alleviating device and pressure vessel used in nuclear power station |
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| CN2012205810463U CN202917186U (en) | 2012-11-06 | 2012-11-06 | Accident alleviating device and pressure vessel used in nuclear power station |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2016070776A1 (en) * | 2014-11-04 | 2016-05-12 | 南方增材科技有限公司 | Electric melting method for forming nuclear power plant pressure vessel cylinder |
| CN115938619A (en) * | 2022-11-22 | 2023-04-07 | 上海核工程研究设计院股份有限公司 | High-power reactor is with pressure vessel and reactor system of area delay basket |
-
2012
- 2012-11-06 CN CN2012205810463U patent/CN202917186U/en not_active Expired - Fee Related
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2016070776A1 (en) * | 2014-11-04 | 2016-05-12 | 南方增材科技有限公司 | Electric melting method for forming nuclear power plant pressure vessel cylinder |
| CN115938619A (en) * | 2022-11-22 | 2023-04-07 | 上海核工程研究设计院股份有限公司 | High-power reactor is with pressure vessel and reactor system of area delay basket |
| CN115938619B (en) * | 2022-11-22 | 2024-01-19 | 上海核工程研究设计院股份有限公司 | Pressure vessel with retention basket for high-power reactor and reactor system |
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