CN206672646U - Stagnation pressure external container cooling test stand in a kind of fused mass heap - Google Patents
Stagnation pressure external container cooling test stand in a kind of fused mass heap Download PDFInfo
- Publication number
- CN206672646U CN206672646U CN201720228460.9U CN201720228460U CN206672646U CN 206672646 U CN206672646 U CN 206672646U CN 201720228460 U CN201720228460 U CN 201720228460U CN 206672646 U CN206672646 U CN 206672646U
- Authority
- CN
- China
- Prior art keywords
- heating plate
- control system
- water tank
- section
- heating
- 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.)
- Withdrawn - After Issue
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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model belongs to stagnation pressure external container cooling test stand in technical field of nuclear power, more particularly to a kind of fused mass heap.Low head is simulated using full scale model mostly to solve the current correlative study for IVR ERVC both at home and abroad, construction-time length, the problem of cost amount of money is larger.The utility model proposes stagnation pressure external container cooling test stand in a kind of fused mass heap.Test-bed includes test section, system circuit and accessory system, specifically includes heating system, U-type groove, insulation spacer, stainless steel heating plate, power supply, rising pipeline section, water tank, heat exchanger, decline pipeline section, data acquisition and whistle control system and power control system；The utility model carries out contracting ratio to prototype size using scale reduction method, the duration can be shortened, reduce cost, and can ensures the accuracy of experiment, while the utility model is directed to specific heap-type, that is CAP1400 heap-type, certain theories integration can be provided for the research of specific heap-type.
Description
Technical field
The utility model belongs to stagnation pressure external container in technical field of nuclear power, more particularly to a kind of fused mass heap and cooled down
Test-bed.
Background technology
In nuclear power developing course, nuclear safety is always people's Important Problems of concern.Although nuclear power plant has taken up
Come the generation that avoids a nasty accident the serious thing of super design reference may still occur for a series of measure under extreme condition
Therefore such as Three Mile Island accident, Chernobyl accident and Fukushima accident.Once major accident occurs, vapour explosion may be caused, released
The serious consequences such as amplification quantity radioactive substance.Investigation shows that accident once occurs for nuclear power plant, as long as ensureing pressure vessel and safety
The integrality of shell, it just can largely reduce the release of radioactive substance.Since then, gradually formed in the world stagnant in fused mass heap
Cooling severe accident relieving strategy outside the pressure vessel stayed, i.e., cooling water flows through forms between pressure vessel outer wall and heat-insulation layer
Runner, the heat by fused mass derived from lower head of pressure vessel wall is taken out of, so as to prevent lower head of pressure vessel
Boiling crisis occurs for surface, ensures the integrality of low head.At present, IVR-ERVC has become using AP1000 series as representative
The severe accident relieving measure of a core in the advanced nuclear power technology of the third generation.Equally, in other advanced nuclear reactor types,
EVR-ERVC equally has broad application prospects.But it is all to use 1 that research external at present is most of:The model of 1 ratio
To simulate low head, even if it is also full-scale simulation to take hierarchical model, the time so expended is more, and quantities is bigger, and
And many problems also occur in experimentation.
Utility model content
In view of the above-mentioned problems, the utility model proposes stagnation pressure external container cooling test platform in a kind of fused mass heap
Frame, including test section, system circuit and accessory system；The head of the test section and afterbody are connected by flange and system circuit
Connect, system circuit is connected with accessory system；The test section includes heating system, U-type groove, heating plate and sealed insulation pad；
Heating system is fixed in heating plate, and heating plate forms flow passage system with U-type groove, is provided with heating plate and U-type groove contact position
Insulation spacer, for the space between heated sealed plate and U-type groove；The test section is the advanced high-power presurized water reactor of simulation
A CAP1400 lower head of pressure vessel part, using 1:14 contractings use 1 than low head structure, wherein radius:5 contracting ratios, and two
The heater plate thickness of each segmental arc of dimension section increases successively.
The both ends of the heating plate set positive electrode and negative electrode respectively, for adjusting the hot-fluid of the heating plate of different-thickness
The size of density, heating system are fixed on two electrodes at heating plate both ends, in the surface soldered thermometric line of heating plate inwardly,
For measuring the inner wall temperature of bringing-up section, thickness different from heating plate are respectively arranged in the entrance of test section, outlet and runner
Corresponding thermocouple is spent, thermocouple is inserted into runner by U-type groove outer surface, for measuring runner water temperature, the heating
The mode of heating of plate is directly heated using alternating current, realizes that the different hot-fluid of each segmental arc is close by the different-thickness of heating plate
Degree.
The system circuit includes rising pipeline section, water tank, heat exchanger and declines pipeline section, and the water tank is by flange with rising
Pipeline section is connected, and water tank bottom is connected by two pipelines with heat exchanger, and gas outlet is provided with above water tank, and contacting external air,
Side is provided with water inlet, is connected with supply channel, and imported valve is set in water tank inlet position, and water outlet of water tank position is set
Outlet valve, imported valve and outlet valve are used for adjusting the size of flow；All pipelines being connected with water tank bottom are all provided with
There is flange section, can change tank height by adding or reducing the pipeline section at these passage flange sections；Set declining pipeline section
There is flowmeter, for monitoring flow in real time.
The accessory system includes power supply, data acquisition and whistle control system and power control system, power supply, power supply control
System processed and data acquisition and whistle control system are sequentially connected, and data acquisition and whistle control system lead to power control system
Cross system circuit respectively with test section to be connected, the data acquisition and whistle control system use NI acquisition system, and data are adopted
The gathering line of collection and whistle control system is connected respectively on the thermocouple arranged in heating system.
The beneficial effects of the utility model are：
(1) this test-bed accesses the interior wall temperature of the bringing-up section under different operating modes, the fluid temperature (F.T.) of runner, test section pressure
A series of parameters changed over time such as difference and void fraction, while constant parameter value can be changed experiment is tied to study it
The influence of fruit.It is significant to the study mechanism of nuclear power plant's major accident.
(2) this test-bed primary study CHF regularities of distribution, natural circulation characteristic and biphase gas and liquid flow during experiment
Behavior.Take its two dimension slicing to test after carrying out contracting ratio to low head than means by certain contracting, heating plate can be passed through
Different thickness realizes the different heat flow density of each segmental arc.This test-bed can be commented under conditions of time and funds is saved
Estimate the feasibility of the ERVC measures under major accident.Experiment basis are established for the design and validation verification of IVR-ERVC systems.
Brief description of the drawings
Accompanying drawing 1 is test-bed structural representation.
Accompanying drawing 2 is the front view of test section.
Accompanying drawing 3 is the right view of test section.
Accompanying drawing 4 is the sectional view of test section.
Embodiment
The utility model is described in detail with reference to the accompanying drawings and detailed description.Accompanying drawing 1 is test-bed knot
Structure schematic diagram, as shown in figure 1, the test-bed includes system circuit, accessory system and test section.The head of test section and tail
Portion is connected by flange with system circuit, and system circuit is connected with accessory system, and test section includes heating system, U-type groove, insulation
Pad and heating plate, heating plate form flow passage system with U-type groove, are provided with insulation spacer in heating plate and U-type groove contact position, use
The space come between heated sealed plate and U-type groove；The system circuit includes rising pipeline section, water tank, heat exchanger and declines pipeline section,
The both ends of U-type groove are connected by flange with rising pipeline section with declining pipeline section, set electromagnetic flowmeter to be used for examining on pipeline section is declined
Survey water-carrying capacity.Water tank is arranged on the rising pipeline section of U-type groove, and water tank bottom is connected by two pipelines with heat exchanger, above water tank
Gas outlet is provided with, with contacting external air, side is provided with water inlet, is connected with supply channel, is set in water tank inlet position
Imported valve, water outlet of water tank position set outlet valve, and imported valve and outlet valve are used for adjusting the size of flow.With water
All pipelines that bottom portion is connected are equipped with flange section, are changed by adding or reducing the pipeline section at these passage flange sections
Become tank height, heat exchanger is connected to water tank bottom by two pipelines, for adjusting entrance degree of supercooling and flow, made in water tank
Water temperature be maintained at relatively low state.Accessory system includes power supply, data acquisition and whistle control system and power control system,
Power supply, power control system and data acquisition and whistle control system are sequentially connected, data acquisition and whistle control system and electricity
Source control system is connected with test section respectively by system circuit.Power supply general power is 50KW.Signal acquiring system is using NI's
Acquisition system, it is controlled by power control system.The gathering line of signal acquiring system is connected respectively to cloth in heating system
On the thermocouple put, for gathering the delta data of water temperature and heating plate wall temperature.Accompanying drawing 2 is the front view of test section, and accompanying drawing 3 is
The right view of test section, as shown in Figures 2 and 3, test section is mainly by heating system, U-type groove, sealed insulation pad and heating plate
Composition.The test section is two dimension slicing, simulates a part for advanced high-power presurized water reactor CAP1400 lower head of pressure vessel,
Heating plate constitutes flow passage system with U-type groove, and insulation spacer is provided with heating plate and U-type groove contact position, as shown in Figure 4,
Insulation spacer is close to runner inner wall, to the space insulated between heated sealed plate and U-type groove.The both ends of whole test section lead to
Flange is crossed to be attached with pipeline.Heating system is the main system of test-bed, and heating system is fixed on stainless steel heating plate two
On two electrodes at end, it is controlled by power control system, watt level can be adjusted.Heating plate both ends are set just respectively
Negative electrode, for adjusting the size of heating plate electric current, in the surface soldered thermometric line of heating plate inwardly, thermometric line, which is used for measuring, to be added
Hot arc inner wall temperature, corresponding bringing-up section different-thickness set armoured thermocouple, are separately positioned in entrance, outlet and runner, armour
Dress thermocouple is inserted into runner by U-type groove outer surface, for measuring water temperature.Test section is hemispheric two dimension slicing, examination
It is different to test each segmental arc heater plate thickness of section, reaches required heat flow density.Connection tedge segment pipe, is being tried at the top of test section
A natural convection loop is formed during testing, under water-filled state, the fluid in U-type groove is heated, in this pipeline
Fluid is heated to be risen, and enters upper tank along rising pipeline section after heated, the decline that the cold fluid in water tank passes through water tank bottom
Pipeline section, which declines, again passes by heating system, forms a circulation.During experiment, by adding or reducing water tank bottom method
Pipeline section at blue section changes tank height, influence degree of the research tank height to result of the test.
This embodiment is only the preferable embodiment of the utility model, but the scope of protection of the utility model not office
It is limited to this, any one skilled in the art can readily occur in the technical scope that the utility model discloses
Change or replacement, it should all cover within the scope of protection of the utility model.Therefore, the scope of protection of the utility model should be with
Scope of the claims is defined.
Claims (4)
1. stagnation pressure external container cooling test stand in a kind of fused mass heap, it is characterised in that returned including test section, system
Road and accessory system；The head of the test section and afterbody are connected by flange with system circuit, and system circuit is with auxiliary
System is connected；The test section includes heating system, U-type groove, heating plate and sealed insulation pad；Heating system is fixed on heating plate
On, heating plate forms flow passage system with U-type groove, insulation spacer is provided with heating plate and U-type groove contact position, for heated sealed
Space between plate and U-type groove；The test section is the advanced high-power presurized water reactor CAP1400 lower head of pressure vessel one of simulation
Point, using 1:14 contractings use 1 than low head structure, wherein radius:5 contracting ratios, and the heater plate thickness of each segmental arc of two dimension slicing
Increase successively.
2. stagnation pressure external container cooling test stand, its feature exist in a kind of fused mass heap according to claim 1
In the both ends of the heating plate set positive electrode and negative electrode respectively, for adjusting the heat flow density of the heating plate of different-thickness
Size, heating system is fixed on two electrodes at heating plate both ends, in the surface soldered thermometric line of heating plate inwardly, is used for
The inner wall temperature of bringing-up section is measured, the different-thickness phase with heating plate is respectively arranged in the entrance of test section, outlet and runner
Corresponding thermocouple, thermocouple are inserted into runner by U-type groove outer surface, for measuring runner water temperature, the heating plate
Mode of heating is directly heated using alternating current, and the different heat flow density of each segmental arc is realized by the different-thickness of heating plate.
A kind of 3. stagnation pressure external container cooling test stand in fused mass heap according to claim 1, it is characterised in that
The system circuit includes rising pipeline section, water tank, heat exchanger and declines pipeline section, and the water tank is connected by flange with rising pipeline section
Connect, water tank bottom is connected by two pipelines with heat exchanger, and gas outlet is provided with above water tank, and with contacting external air, side is opened
There is water inlet, be connected with supply channel, imported valve is set in water tank inlet position, water outlet of water tank position sets outlet valve
Door, imported valve and outlet valve are used for adjusting the size of flow；All pipelines being connected with water tank bottom are equipped with flange
Section, can change tank height by adding or reducing the pipeline section at these passage flange sections；Flow is provided with declining pipeline section
Meter, for monitoring flow in real time.
A kind of 4. stagnation pressure external container cooling test stand in fused mass heap according to claim 1, it is characterised in that
The accessory system includes power supply, data acquisition and whistle control system and power control system, power supply, power control system and
Data acquisition and whistle control system are sequentially connected, and data acquisition and whistle control system are returned with power control system by system
Road is connected with test section respectively, and the data acquisition and whistle control system use NI acquisition system, data acquisition and signal
The gathering line of control system is connected respectively on the thermocouple arranged in heating system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201720228460.9U CN206672646U (en) | 2017-03-09 | 2017-03-09 | Stagnation pressure external container cooling test stand in a kind of fused mass heap |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201720228460.9U CN206672646U (en) | 2017-03-09 | 2017-03-09 | Stagnation pressure external container cooling test stand in a kind of fused mass heap |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN206672646U true CN206672646U (en) | 2017-11-24 |
Family
ID=60377206
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201720228460.9U Withdrawn - After Issue CN206672646U (en) | 2017-03-09 | 2017-03-09 | Stagnation pressure external container cooling test stand in a kind of fused mass heap |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN206672646U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106952669A (en) * | 2017-03-09 | 2017-07-14 | 华北电力大学 | Stagnation pressure external container cooling test stand in a kind of fused mass heap |
| CN109509564A (en) * | 2018-12-11 | 2019-03-22 | 西安交通大学 | A kind of nuclear reactor engineering magnitude bilayer Bath Heat-Transfer characteristic test apparatus |
-
2017
- 2017-03-09 CN CN201720228460.9U patent/CN206672646U/en not_active Withdrawn - After Issue
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106952669A (en) * | 2017-03-09 | 2017-07-14 | 华北电力大学 | Stagnation pressure external container cooling test stand in a kind of fused mass heap |
| CN109509564A (en) * | 2018-12-11 | 2019-03-22 | 西安交通大学 | A kind of nuclear reactor engineering magnitude bilayer Bath Heat-Transfer characteristic test apparatus |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106952669B (en) | Stagnation pressure external container cooling test rack in a kind of fusant heap | |
| CN105911087B (en) | A kind of large size nuclear reactor fusion pool heat transfer free convection pilot system and method | |
| CN102661845B (en) | Visualized narrow rectangular natural circulation system | |
| CN106066235B (en) | Supercritical water narrow passage Natural Circulation experimental provision and method | |
| CN108109708A (en) | Villiaumite cools down ball bed high-temperature heap reactor core fluid interchange experimental system for simulating | |
| CN106024079B (en) | Passive residual heat removal circulation performance test system and test method | |
| CN104966536A (en) | High-temperature working medium heat exchange test system using heat conducting oil as hot fluid and test method | |
| CN110097983A (en) | The cooling three dimensional taest section of stagnation pressure external container in a kind of fusant heap | |
| CN207637503U (en) | Experimental rig for the passive guiding system of containment heat | |
| CN107238627A (en) | Conduction oil working medium forced circulation Comprehensive Experiment circuit system | |
| CN108761022A (en) | A kind of liquid lead bismuth alloy hot-working hydraulic characteristic and etching characteristic experimental system | |
| CN107293340B (en) | A kind of small-sized steam generator thermal hydraulic analysis pilot system | |
| CN206672646U (en) | Stagnation pressure external container cooling test stand in a kind of fused mass heap | |
| CN106981321A (en) | Simulate the experimental rig and method of sodium-cooled fast reactor fuel assembly hot-working hydraulic characteristic | |
| CN107315068A (en) | A kind of purifying molten metal experimental loop system and its application method | |
| CN107884332A (en) | A kind of high flow rate multimode aqueous corrosion experimental provision for controlling oxygen content | |
| CN104634810A (en) | High Rayleigh (Ra) number coupling heat-transfer characteristic measuring and evaluating device | |
| Rozzia et al. | Experimental investigation on powder conductivity for the application to double wall heat exchanger (NACIE-UP) | |
| CN110223790A (en) | Stagnation pressure external container cooling test rack in a kind of fusant heap | |
| CN103175732B (en) | Test bed for simulating thermal fatigue phenomenon of nuclear power station pipeline | |
| Men et al. | Heat transfer analysis of passive residual heat removal heat exchanger under natural convection condition in tank | |
| CN203745401U (en) | Device for measuring and evaluating high Rayleigh number coupling heat-transfer characteristics | |
| CN103983661A (en) | Molten salt forced-convection heat transfer experimental facility with strong internal heat source and large-size bead pebble-bed channel | |
| CN105784257B (en) | A kind of minor diameter ball bed high-temperature helium pressure drop measuring device and method | |
| CN208902638U (en) | Heat transfer free convection testing equipment |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20171124 Effective date of abandoning: 20190301 |
|
| AV01 | Patent right actively abandoned |