CN103594133A - Experiment device for simulating retention of in-pile melts obtained by melting of reactor core of nuclear reactor and experiment method - Google Patents
Experiment device for simulating retention of in-pile melts obtained by melting of reactor core of nuclear reactor and experiment method Download PDFInfo
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- CN103594133A CN103594133A CN201310497247.4A CN201310497247A CN103594133A CN 103594133 A CN103594133 A CN 103594133A CN 201310497247 A CN201310497247 A CN 201310497247A CN 103594133 A CN103594133 A CN 103594133A
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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
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Abstract
The invention discloses an experiment device for simulating retention of in-pile melts obtained by melting of a reactor core of a nuclear reactor and an experiment method. The device consists of a copper heating section, a quartz glass component and a data measurement system. According to the experiment device, a melt hard shell of the reactor core is simulated through a semispherical copper ball shell; decay heat is simulated through a spiral heating wire embedded into the semispherical shell; the inner wall surface of a lower enclosure of a pressure container is simulated through quartz glass, and therefore, a flowing heat exchange phenomenon of a narrow gap between the inner wall surface of the pressure container of the reactor and the melt hard shell can be simulated, and the influence on the retention of the in-pile melts caused by flowing of water in the narrow gap can be researched. The experiment device has the advantages of visible experiment process, high experiment precision, high safety, easiness in operation and the like. A running practice shows that the experiment device runs stably and can thoroughly meet a design requirement.
Description
Technical field
The invention belongs to experimental provision technical field, be specifically related to a kind of experimental provision and method that in the rear heap of nuclear reactor fusing, fused mass is detained of simulating.
Background technology
After the major accident of reactor generation core meltdown, pressure vessel becomes the important barrier that prevents that radiomaterial from escaping.Having there is the major accident of core meltdown in three mile island nuclear stations in 1979, in to the analysis of this accident, thereby all well-known safety analysis software result of calculation all shows that pressure vessel low head can lose efficacy, causes fused mass spill pressure container.Yet pressure vessel did not lose efficacy in accident, this just shows that a kind of new cooling mechanism exists and reactor pressure vessel low head has been carried out to effective cooling.By the theoretical and experimental study both at home and abroad, find, fused mass fall in pressure vessel low head process can be due to low head in the cooling effect of water in melt surface, form solid-state duricrust, the part heat of fused mass is also taken away in the gap of water Continuous-flow between pressure vessel low head and duricrust, thereby realization is permanently effective cooling to fused mass, guaranteed the integrality of pressure vessel.For the maximum heat (critical heat flux density) of understanding the thermal-hydraulic phenomenon in narrow annular channel in depth and seething with excitement and can take away by water in gap, need to carry out further experimental study to disclose the coolant mechanism of narrow annular channel, for piling interior fused mass delay related software, provide checking foundation.
Doing some abroad similarly tests, one piece of document (Akihiro UCHIBORI that for example Akihiro UCHIBORI publishes, Tatsuya MATSUMOTO, Koji MORITA, et al.Evaluation of Cooling Capability in a Heated Narrow Flow Passage.Journal of Nuclear Science and Technology, Vol.40, No.10, p.796 – 806) in, the gap analogue pressure vessel low head between employing semisphere copper bringing-up section and semisphere glass and the narrow slit between duricrust.Experiment adopts the decay heat of electrical heating simulation fused mass, and heating power is respectively 1.05kW, 1.40kW.Gap between copper bringing-up section and semisphere glass is 5mm.Experimental provision is built in cylindrical drum, and cylindrical drum and experimental provision base plate all adopt Pyrex glass to realize visual to experimental phenomena.Between internal and external layers of glass, be evacuated with the good insulation effect of assurance device.But the experimental section of this experimental provision does not have entrance and exit, finish must dismantle after part experiment condition experimental section again water filling can again test, also can not study the impact of discharge on phenomenons such as critical heat flux density, two phase countercurrent flows; Therefore this experimental provision does not have copper bringing-up section lifting assembly can not realize the lifting easily of copper bringing-up section, be difficult to the convenient clearance distance that regulates; In this experimental provision, inside and outside glass is independent of each other, and this just requires more complicated encapsulating method to guarantee that vacuum tightness between layer glass, to guarantee insulation effect, has reduced the reliability of device when making device more complicated.
One piece of document (J.H.Jeong that and for example J.H.Jeong publishes, R.J.Park, S.B.Kim.Thermal-hydraulic Phenomena Relevant to Global Dryout in a Hemispherical Narrow Gap.Heat and Mass Transfer, 34 (1998), p.321-328), in, adopt VISU-II experimental provision to carry out the research of the critical heat flux density mechanism in narrow annular channel.This device comprises semisphere well heater, heating power controller, semisphere copper ball shell, semisphere Pyrex glass and temperature survey and acquisition system etc.Maximum heating power is 6kW.This device has adopted the copper ball shell of 4 groups of different-diameters to study the impact of different gap size on thermal-hydraulic parameter.Flow working medium is deionized water.But this device has the drawback of upper routine device equally, as do not studied discharge on the impact of the phenomenons such as critical heat flux density, can easily not carry out lifting etc. by double ball copper shell.
Summary of the invention
The object of the present invention is to provide a kind of experimental provision and method that in the rear heap of nuclear reactor fusing, fused mass is detained of simulating, to overcome the shortcoming of above-mentioned existing experimental provision.
For achieving the above object, the present invention has adopted following technical scheme:
The experimental provision that after the fusing of simulation nuclear reactor, in heap, fused mass is detained, comprises quartz glass cylindrical shell, heating arrangement and data measurin system;
Quartz glass cylindrical shell comprises inner semisphere experimental section and outside vertically glass infuser, and semisphere experimental section and vertically glass infuser top are by being welded into one; Vertically on the sidewall on glass infuser top, be provided with experimental section entrance, on the relative vertical glass barrel of experimental section entrance, be provided with experimental section outlet; Experimental section entrance and experimental section outlet all connect inside and outside quartz glass cylindrical shell and are connected with semisphere experimental section, and experimental section entrance is vertically exporting higher than experimental section on height; Above semisphere experimental section, be provided with upper flange, vertically glass infuser below is provided with lower flange, and upper flange and lower flange are fastening by some groups of stainless steel threaded rods and quartz glass cylindrical shell, realize the sealing of experimental provision;
Heating arrangement comprises the semisphere copper ball shell that is arranged in quartz glass cylindrical shell, is arranged on the copper ball housing-plate on semisphere copper ball shell, also comprises support column and wire wire barrel; The shape of several heater strips is embedded in semisphere copper ball shell in the shape of a spiral and evenly; In the hemispherical cavity becoming with semisphere copper ball hull shape at copper ball housing-plate, be filled with ceramic packing; Wire wire barrel is connected with copper ball housing-plate through upper flange; The wire of several heater strips 22 is drawn by wire wire barrel; Support column is provided with external thread, itself and upper flange;
Data measurin system comprises flowmeter, vacuum meter and some groups of thermopairs; Wherein, flowmeter is for measuring the discharge entering in semisphere experimental section, and vacuum meter is for measuring the vacuum tightness between semisphere experimental section and vertical glass infuser, and some groups of thermopairs are for measuring the temperature field in semisphere experimental section.
The present invention further improves and is: on the vertical glass barrel below semisphere experimental section, be provided with vacuum meter and take over, be provided with vacuum pump and take on its relative vertical glass barrel, connect respectively vacuum meter and vacuum pump.
The present invention further improves and is: some groups of thermopairs are circumferentially arranged on the inner wall hole of semisphere copper ball shell; Wherein, every group of pore is comprised of two different holes of the degree of depth, and the distance between Kong Yukong is less than or equal to 1.5mm; The signal wire of some groups of thermopairs is drawn by the signal wire wire barrel 8 through upper flange.
The present invention further improves and is: the material of semisphere copper ball shell is brass, and the material of copper ball housing-plate is stainless steel.
The present invention further improves and is: semisphere experimental section and the vertically vacuum tightness between glass infuser are 1 kPa～5 kPas.
The present invention further improves and is: lower flange center is provided with circular hole, the aperture of this circular hole is less than or equal to vertical glass infuser below internal diameter, below vertical glass infuser with lower flange between be provided with vertical glass infuser below the identical poly (methyl methacrylate) plate of external diameter, this poly (methyl methacrylate) plate is embedded in the groove of lower flange; Between below poly (methyl methacrylate) plate and vertical glass infuser, be also provided with an O RunddichtringO, between above upper flange and vertical glass infuser, be provided with the 2nd O RunddichtringO; The material of upper flange and lower flange is stainless steel.
The present invention further improves and is: the spacing of semisphere copper ball shell and semisphere experimental section is 5mm.
The experimental technique of the experimental provision that after the fusing of simulation nuclear reactor, in heap, fused mass is detained, is characterized in that, comprises the following steps: first with vacuum pump, will between the layer glass of quartz glass cylindrical shell, be pumped into negative pressure state; Handle by swivel bearing capital end is realized the lifting of semisphere copper ball shell by rolling bearing, the distance between semisphere copper ball shell and semisphere experimental section is remained on to 5mm; Water flows into semisphere experimental section from experimental section entrance, and experimental section is flowed out in section outlet 9 by experiment; Switch on power and by heater strip, the water in semisphere experimental section is heated, by temperature and the heat flow density in thermocouple measurement semisphere copper ball shell.
Compared with prior art, the present invention has the following advantages and beneficial effect:
1. heater strip is embedded in semisphere copper ball shell inside, and design can reduce heating arrangement to the heat radiation of environment like this, reduces the uncertainty of experiment;
By demarcate support column rotating cycle and the axially movable distance of support column can realize to semisphere copper ball shell and and semisphere experimental section between the accurate control of distance;
3. experimental provision of the present invention is except top and bottom adopt steel flange, its border adopting quartz glass or organic glass, thus can realize from the sidepiece of experimental provision or bottom visual to experimental phenomena;
4. the present invention is designed to an integral body by quartz glass cylindrical shell and can reduces the additional support to inner semisphere experimental section, has both improved sealing effectiveness, has strengthened again the security of experimental provision.
In a word, semisphere copper ball shell Simulation Core fused mass duricrust for the present invention, with the spirality heater strip simulation decay heat that is embedded in hemispherical Shell inside, with quartz glass analogue pressure vessel low head internal face, with the fluid interchange phenomenon of narrow slit between this simulation reaction core pressure vessel internal face and fused mass duricrust, in research narrow slit, water flow is on piling the impact of interior fused mass retentivity; This experimental provision can be measured a series of thermal-hydraulic parameters such as semisphere copper ball shell surface heat flux, warm field distribution, air bubble growth and migration under static and flow state, and can realize bottom to experimental section, side is visual.By vacuumizing, fill the insulation methods such as ceramic packing, effectively reduce experiment uncertainty, thereby can to fused mass retentivity in reactor, assess more exactly, to reach experiment purpose.The advantages such as the present invention has that experimentation is visual, experimental precision is high, safe, easy operating; Through operation, facts have proved, experimental provision is stable, can reach designing requirement completely.
Accompanying drawing explanation
Fig. 1 is a kind of structural representation of simulating the experimental provision that in the rear heap of nuclear reactor fusing, fused mass is detained of the present invention;
Fig. 2 is vacuum meter connection diagram;
Fig. 3 is glass evacuating valve schematic diagram;
Fig. 4 is that thermopair is arranged front view;
Fig. 5 is that thermopair is arranged vertical view;
Fig. 6 is copper ball housing-plate cut-open view;
Fig. 7 is copper ball housing-plate vertical view.
Wherein: 1, experimental section entrance; 2, semisphere copper ball shell; 3, semisphere experimental section; 4, vertical glass infuser; 5, upper flange; 6, support column; 7, wire wire barrel; 8, signal wire wire barrel; 9, experimental section outlet; 10, rolling bearing; 11, copper ball housing-plate; 12, vacuum meter is taken over; 13, vacuum pump is taken over; 14, poly (methyl methacrylate) plate; 15, an O RunddichtringO; 16, lower flange; 17, the 2nd O RunddichtringO; 18, plastics back-up ring; 19, the stainless steel flange that is threaded; 20, vacuum meter; 21, poly fourfluoroplastics pad; 22, heater strip; 23, thermopair; 24, bearing seat.
Embodiment
Below in conjunction with accompanying drawing, the present invention is described in further detail:
Referring to Fig. 1 to Fig. 7, a kind of experimental provision of simulating fused mass delay in the rear heap of nuclear reactor fusing of the present invention, comprises quartz glass cylindrical shell, heating arrangement and data measurin system.
Quartz glass cylindrical shell comprises inner semisphere experimental section 3 and outside vertically glass infuser 4, and semisphere experimental section 3 and vertically glass infuser 4 tops, by being welded into one, do not provide extra supporting and sealing therefore be not required to be glass assembly.Vertically on the sidewall on glass infuser 4 tops, be provided with experimental section entrance 1, on its relative vertical glass infuser 4 walls, be provided with experimental section outlet 9, experimental section entrance 1 and experimental section outlet 9 all connect inside and outside quartz glass cylindrical shell and are connected with semisphere experimental section 3, and experimental section entrance 1 is vertically exporting 9 higher than experimental section on height.On vertical glass infuser 4 walls below semisphere experimental section 3, be provided with vacuum meter and take over 12, on its relative vertical glass infuser 4 walls, be provided with vacuum pump and take over 13, being respectively vacuum meter adapter and glass evacuating valve takes over, wherein, vacuum meter 20 is taken over 12 with vacuum meter and is connected, and vacuum pump and vacuum pump are taken over 13 and joined.In order to eliminate experimental section to the heat radiation in environment, must will semisphere experimental section 3 and vertically between glass infuser 4, be pumped into higher vacuum tightness (1 kPa～5 kPas) with vacuum pump before experiment, and measure by the vacuum tightness between 20 pairs of quartz glass cylindrical shells of vacuum meter.
Above semisphere experimental section 3, be provided with upper flange 5, vertically glass infuser 4 belows are provided with lower flange 16, and upper flange 5 and lower flange 16 are fastening by 6 groups of stainless steel threaded rods and quartz glass cylindrical shell, to realize the sealing of experimental provision.Lower flange 16 centers are provided with circular hole, the aperture of this circular hole is less than or equal to vertical glass infuser 4 below internal diameters, below vertical glass infuser 4 with lower flange 16 between be provided with vertical glass infuser 4 below the identical poly (methyl methacrylate) plate 14 of external diameter, this poly (methyl methacrylate) plate 14 is embedded in the groove of lower flange 16.Can be from the flow phenomenon of experimental provision bottom observation semisphere experimental section 3 in experimentation.Between below poly (methyl methacrylate) plate 14 and vertical glass infuser 4, be also provided with an O RunddichtringO 15, between above upper flange 5 and vertical glass infuser 4, be provided with the 2nd O RunddichtringO 17.Wherein, the material of upper flange 5 and lower flange 16 is stainless steel.
Heating arrangement is arranged in quartz glass cylindrical shell, comprise semisphere copper ball shell 2 and pass through bolt seal copper ball housing-plate 11 mounted thereto, the shape of several heater strips 22 is embedded in semisphere copper ball shell 2 (embedding in copper ball shell by casting), with approaching to reality fused mass heating effect in the shape of a spiral and evenly; Heater strip 22 is uniformly distributed to guarantee that the highest heating power of several heater strips 22 is 5kW to copper ball shell homogeneous heating in the shape of a spiral.Wherein, the material of semisphere copper ball shell 2 is brass, and the material of copper ball housing-plate 11 is stainless steel, is filled with ceramic packing, to reduce the heat radiation to environment at copper ball housing-plate 11 and semisphere copper ball shell 2 in the hemispherical cavity forming.Wire wire barrel 7 is connected with copper ball housing-plate 11 through upper flange 5, and wherein, the wire of these several heater strips 22 is drawn by wire wire barrel 7.Support column 6 is provided with external thread, and it matches with the internal thread hole on upper flange 5; Support column 6 bottoms are connected with copper ball housing-plate 11 with bearing seat 24 by rolling bearing 10, can realize the lifting of heating arrangement, to regulate the gap length between semisphere copper ball shell 2 and semisphere experimental section 3 by the handle of swivel bearing post 6 upper ends.In experiment, semisphere copper ball shell 2 is 5mm with the optimal spacing of semisphere experimental section 3.
Data measurin system comprises flowmeter, vacuum meter 20 and some groups of thermopairs 23.Wherein, flowmeter is for measuring the discharge entering in semisphere experimental section 3, vacuum meter 20 is for measuring the vacuum tightness between semisphere experimental section 3 and vertical glass infuser 4, and some groups of thermopairs 23 are for measuring the temperature field in semisphere experimental section 3 and indirectly measuring heat flow density.Vacuum meter 20 is connected by screw thread and the stainless steel flange 19 that is threaded, be threaded flange 19 and vacuum meter of stainless steel taken over 12 and is connected, be threaded flange 19 of stainless steel adopts plastics back-up rings 18 location, and vacuum meter is taken over 12 and is threaded with stainless steel and adopts poly fourfluoroplastics pad 21 to seal between flange 19.Some groups of thermopairs 23 are circumferentially arranged on the inwall pore of semisphere copper ball shell 2, wherein, inwall pore has 25 groups, every group of pore is comprised of two different holes of the degree of depth, distance between Kong Yukong is less than or equal to 1.5mm, therefore what can suppose 23 measurements of every group of thermopair is the temperature of semisphere copper ball shell 2 same radial positions, so just can obtain the heat flow density that heater strip 22 transmits to semisphere copper ball shell 2 according to the differential thermal calculation of every group of thermopair 23.Signal wire wire barrel 8 is connected with copper ball housing-plate 11 through upper flange 5, and the signal wire of some groups of thermopairs 23 is drawn by signal wire wire barrel 8.
Referring to Fig. 1, a kind of experimental provision of simulating fused mass delay in the rear heap of nuclear reactor fusing of the present invention, experiment initial vacuum pump is connected to vacuum pump and takes over 13, first with vacuum pump, will between the layer glass of quartz glass cylindrical shell, be pumped into negative pressure state, and vacuum tightness can be shown by the reading of vacuum meter 20; When reaching the vacuum tightness of requirement of experiment, turn off glass evacuating valve and (be installed on vacuum pump and take on 13, close vacuum pump after as shown in Figure 3).Vacuum meter 20 internal pressure readings not during temporal evolution indication device impermeability good.If force value temporal evolution, needs to improve sealing by 6 fastening bolts (for for purpose of brevity, not drawing in diagram) between fastening upper flange 5 and lower flange 16.Handle by swivel bearing post 6 tops can be realized the lifting of semisphere copper ball shell 2 by rolling bearing 10, during experiment, the distance between semisphere copper ball shell 2 and semisphere experimental section 3 is remained on to 5mm.Water flows into semisphere experimental section 3 from experimental section entrance 1, i.e. annular gap between semisphere copper ball shell 2 and semisphere experimental section 3, by experiment section outlet 9 outflow experimental sections.Heater strip 22 is embedded in semisphere copper ball shell 2 twist, and heater strip 22 two-stages are drawn by wire wire barrel 7.Switch on power the water in semisphere experimental section 3 is heated, with thermopair 23, measure temperature and the heat flow density in semisphere copper ball shell 2, the layout of thermopair 23 as shown in Figure 4, Figure 5.Thermopair 23 wiring are drawn by signal wire wire barrel 8.Vertically glass infuser 4 bottoms are connected with organic glass 14, adopt an O type circle to seal 15 between them, in experimentation, can observe from bottom semisphere experimental section 3 Bubble formation, grow up and the thermal-hydraulic phenomenon such as migration.This experimental provision can also carry out water flow experiment (test section entrance 1 is constantly intake, experimental section outlet 9 continuous water outlets), studies under different discharge operating modes the impact on semisphere copper ball shell 2 interior heat flow densities etc.
Above content is in conjunction with concrete preferred implementation further description made for the present invention; can not assert that the specific embodiment of the present invention only limits to this; for general technical staff of the technical field of the invention; without departing from the inventive concept of the premise; can also make some simple deduction or replace, all should be considered as belonging to the present invention and determine scope of patent protection by submitted to claims.
Claims (8)
1. the experimental provision that after the fusing of simulation nuclear reactor, in heap, fused mass is detained, is characterized in that, comprises quartz glass cylindrical shell, heating arrangement and data measurin system;
Quartz glass cylindrical shell comprises inner semisphere experimental section (3) and outside vertically glass infuser (4), and semisphere experimental section (3) and vertically glass infuser (4) top are by being welded into one; Vertically on the sidewall on glass infuser (4) top, be provided with experimental section entrance (1), on relative vertical glass infuser (4) wall of experimental section entrance (1), be provided with experimental section outlet (9); Experimental section entrance (1) and experimental section outlet (9) all connect inside and outside quartz glass cylindrical shell and are connected with semisphere experimental section (3), and experimental section entrance (1) is vertically exporting (9) higher than experimental section on height; In semisphere experimental section (3) top, be provided with upper flange (5), vertically glass infuser (4) below is provided with lower flange (16), upper flange (5) and lower flange (16) are fastening by some groups of stainless steel threaded rods and quartz glass cylindrical shell, realize the sealing of experimental provision;
Heating arrangement comprises the semisphere copper ball shell (2) that is arranged in quartz glass cylindrical shell, is arranged on the copper ball housing-plate (11) on semisphere copper ball shell (2), also comprises support column (6) and wire wire barrel (7); The shape of several heater strips (22) is embedded in semisphere copper ball shell (2) in the shape of a spiral and evenly; In the hemispherical cavity forming at copper ball housing-plate (11) and semisphere copper ball shell (2), be filled with ceramic packing; Wire wire barrel (7) is connected with copper ball housing-plate (11) through upper flange (5); The wire of several heater strips 22 is drawn by wire wire barrel (7); Support column (6) is provided with external thread, itself and upper flange (5);
Data measurin system comprises flowmeter, vacuum meter (20) and some groups of thermopairs (23); Wherein, flowmeter is for measuring the discharge entering in semisphere experimental section (3), vacuum meter (20) is for measuring the vacuum tightness between semisphere experimental section (3) and vertical glass infuser (4), and some groups of thermopairs (23) are for measuring the temperature field in semisphere experimental section (3).
2. the experimental provision that after simulation nuclear reactor fusing according to claim 1, in heap, fused mass is detained, it is characterized in that, on vertical glass infuser (4) wall of semisphere experimental section (3) below, be provided with vacuum meter and take over (12), on its relative vertical glass infuser (4) wall, be provided with vacuum pump and take over (13), connect respectively vacuum meter (20) and vacuum pump.
3. the experimental provision that after simulation nuclear reactor fusing according to claim 1, in heap, fused mass is detained, is characterized in that, some groups of thermopairs (23) are circumferentially arranged on the inner wall hole of semisphere copper ball shell (2); Wherein, every group of pore is comprised of two different holes of the degree of depth, and the distance between Kong Yukong is less than or equal to 1.5mm; The signal wire of some groups of thermopairs (23) is by drawing through the signal wire wire barrel 8 of upper flange (5).
4. the experimental provision that after simulation nuclear reactor fusing according to claim 1, in heap, fused mass is detained, is characterized in that, the material of semisphere copper ball shell (2) is brass, and the material of copper ball housing-plate (11) is stainless steel.
5. the experimental provision that after simulation nuclear reactor fusing according to claim 1, in heap, fused mass is detained, is characterized in that, semisphere experimental section (3) and the vertically vacuum tightness between glass infuser (4) are 1 kPa～5 kPas.
6. the experimental provision that after simulation nuclear reactor fusing according to claim 1, in heap, fused mass is detained, it is characterized in that, lower flange (16) center is provided with circular hole, the aperture of this circular hole is less than or equal to vertical glass infuser (4) below internal diameter, below vertical glass infuser (4) with between lower flange (16), be provided with the poly (methyl methacrylate) plate (14) identical with vertical glass infuser (4) below external diameter, this poly (methyl methacrylate) plate (14) is embedded in the groove of lower flange (16); Between poly (methyl methacrylate) plate (14) and vertical glass infuser (4) below, be also provided with an O RunddichtringO (15), between upper flange (5) and vertical glass infuser (4) top, be provided with the 2nd O RunddichtringO (17); The material of upper flange (5) and lower flange (16) is stainless steel.
7. the experimental provision that after simulation nuclear reactor fusing according to claim 1, in heap, fused mass is detained, is characterized in that, semisphere copper ball shell (2) is 5mm with the spacing of semisphere experimental section (3).
8. according to the experimental technique of the experimental provision that in heap after the simulation nuclear reactor fusing described in any one in claim 1 to 7, fused mass is detained, it is characterized in that, comprise the following steps: first with vacuum pump, will between the layer glass of quartz glass cylindrical shell, be pumped into negative pressure state; Handle by swivel bearing post (6) top is realized the lifting of semisphere copper ball shell (2) by rolling bearing (10), the distance between semisphere copper ball shell (2) and semisphere experimental section (3) is remained on to 5mm; Water flows into semisphere experimental section (3) from experimental section entrance (1), and experimental section is flowed out in section outlet 9 by experiment; Switch on power and by heater strip (22), the water in semisphere experimental section (3) is heated, with thermopair (23), measure temperature and the heat flow density in semisphere copper ball shell (2).
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| CN115862908A (en) * | 2023-01-30 | 2023-03-28 | 上海核工程研究设计院股份有限公司 | Experimental device for in-pile retention basket under serious accident |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108897950B (en) * | 2018-06-28 | 2020-05-22 | 西安交通大学 | Optimized design method of reactor core melting collector |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103033225A (en) * | 2012-12-11 | 2013-04-10 | 西安交通大学 | Device for measuring split-phase flow of two-phase flow under steady state condition |
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2013
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Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103033225A (en) * | 2012-12-11 | 2013-04-10 | 西安交通大学 | Device for measuring split-phase flow of two-phase flow under steady state condition |
Non-Patent Citations (3)
| Title |
|---|
| J.H.JEONG .ET AL: "Thermal-hydraulic Phenomena Relevant to Global Dryout in a Hemispherical Narrow Gap", 《HEAT AND MASS TRANSFER》 * |
| Y.P.ZHANG .ET AL: "A simple novel analysis procedure for IVR calculation in core-molten severe accident", 《NUCLEAR ENGINEERING AND DESIGN》 * |
| 封坤等: "熔融物下封头间球形窄缝通道内CHF理论研究", 《原子能科学与技术》 * |
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