CN109493982A - A kind of spentnuclear fuel pool boiling test-bed - Google Patents
A kind of spentnuclear fuel pool boiling test-bed Download PDFInfo
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- CN109493982A CN109493982A CN201811113709.7A CN201811113709A CN109493982A CN 109493982 A CN109493982 A CN 109493982A CN 201811113709 A CN201811113709 A CN 201811113709A CN 109493982 A CN109493982 A CN 109493982A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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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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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a kind of spentnuclear fuel pool boiling test-beds for belonging to technical field of nuclear power.Spentnuclear fuel pool boiling test-bed is totally made of six parts, is respectively as follows: Spent Fuel Pool boiling test section, water purification system, water storage and water-carriage system, temperature control system, data collection system and drainage system；Test section is to be made of in stainless steel sleeve the fixed 81 stainless steel heating rod pipes for being arranged into square according to 9 х 9 of grid spacer, inside the stainless steel heating tube along the vertical direction on be evenly arranged thermometric K-type thermocouple, simulate different spentnuclear fuel Decay afterheats by adjusting different heating powers；Automatic measurement, acquisition, transmission and the preservation to each temperature point temperature are realized using data collection system during test, while shooting the interbank steam bubble flow pattern of heating tube using high-speed camera.Study the pool boiling heat transfer characteristic due to caused by Decay afterheat；Experimental study content includes the Performance for Boiling Heat Transfer between temperature field, vertical tube bundle in pond.
Description
Technical field
The invention belongs to technical field of nuclear power, in particular to a kind of spentnuclear fuel pool boiling test-bed.
Background technique
Nuclear power station occurs under whole audience power-off or the accident conditions such as earthquake, Spent Fuel Pool normal cooling system or will be long-term
Failure.During the failure of Spent Fuel Pool cooling system, a big Natural Circulation field, water can be established inside Spent Fuel Pool
It flows downward along the channel between spent fuel storage rack and pool wall, flows through the space between storage screen work bottom plate and bottom of pond,
The discharge orifice passed sequentially through on storage screen work bottom plate again enters irradiated fuel assembly, finally in the hydrospace more than irradiated fuel assembly
It hands over mixed.Water heats up because conducting heat with irradiated fuel assembly, and resulting density contrast is the driving force of Natural Circulation[4].Spentnuclear fuel
The decay heat that spentnuclear fuel constantly generates is taken away in pond by the evaporation of pool inner water, and pool inner water position declines as water evaporates.
Spent Fuel Pool will appear pool boiling phenomenon in the process, and the heat transfer characteristic in Spent Fuel Pool also changes therewith,
Boiling heat transfer is developed to by the single-phase heat transfer of initial stage.As pool inner water position constantly declines, if nuclear power station is not had
The Spent Fuel Pool make-up water measure of effect, or even will appear this exposed danger signal of irradiated fuel assembly.It is exposed in irradiated fuel assembly
Stage, water level decreasing to irradiated fuel assembly height hereinafter, in pond heat transfer characteristic again will change, by two-phase conduct heat become weary combustion
Single-phase convection heat exchange occurs for the vapor that material component exposed part and basin bottom evaporate.In this stage in Spent Fuel Pool
Heat-exchange performance have direct influence to the integrality of irradiated fuel assembly, determine irradiated fuel assembly to the packet of internal radioactive substance
Capacitive.If irradiated fuel assembly clad temperature, which is increased to certain value, will lead to the rupture of involucrum component, radioactive substance leaks, will be right
Nuclear plant safety has an immense impact on.For configuration aspects, channel is a kind of between the vertical tube bundle inside irradiated fuel assembly
The channel in special geometric section, this narrow elongate affects the flow pattern and kinetic characteristic of bubble in two phase flow boiling heat transfer.
Therefore for the research of the boiling heat transfer of irradiated fuel assembly vertical channel, there will be important meaning to Spent Fuel Pool safety,
Also there is important test reference value to engineer application simultaneously.
It is concentrated mainly in theoretical analysis and numerical method aspect for the safety research of Spent Fuel Pool both at home and abroad, needle
It is fewer to the experimental study of Spent Fuel Pool.Wang Minglu is that the passive cooling heat pipe of research imitates the cooling of Spent Fuel Pool
It answers, builds separate heat pipe experiment porch and study its cooling capacity, analyze the heat transfer characteristic of cooling heat pipe.It is counted simultaneously using CFD
The temperature field and flow field of Spent Fuel Pool are calculated, and is compared and analyzed with test result.
Han Yidan et al. fails for Spent Fuel Pool cooling system, and the irradiated fuel assembly in Spent Fuel Pool is due to water level
Evaporation declines and occurs in the exposed situation of cluster, spraying cooling effect of the research spray system to exposed irradiated fuel assembly.Test
Irradiated fuel assembly is simulated using 5 × 5 electrically heated rod, is provided with different tests operating condition, including different heating stick power, difference spray
Flux density is drenched to study temperature changing trend of the irradiated fuel assembly under spraying cooling.Heating cluster is obtained finally by test
Temperature Distributions and spent fuel rods itself under different spray operating conditions decline influence of the power for its safety.
In conclusion it is abundant not enough to have in spentnuclear fuel pool boiling and vertical tube bundle channel heat transfer characteristic research in mind,
Less pertinence is strong.It is mainly manifested in following three aspects:
(1) in terms of Spent Fuel Pool safety research is concentrated mainly on theoretical analysis and numerical method, for spentnuclear fuel water
The experimental study in pond is fewer；
(2) more to fluid interchange research in Experimental Study of Heat Transfer Characteristics research between vertical tube bundle, for Spent Fuel Pool pool
It is less in terms of the experimental study of boiling heat transfer；
(3) moulded dimension in vertical tube bundle channel is not extensive enough, and experiment tube beam passage is generally shorter, to elongated and narrow channel
Interior Study of boiling heat transfer is less.
Summary of the invention
The purpose of the present invention is to propose to a kind of spentnuclear fuel pool boiling test-beds, and the test-bed is with Nuclear Power Station's Exhausted Fuels
Pond is background in cooling system failure conditions, studies the spentnuclear fuel cluster in Spent Fuel Pool due to caused by Decay afterheat
Pool boiling heat transfer characteristic；Experimental study content includes boiling heat transfer coefficient, vertical tube bundle between temperature field, vertical tube bundle in pond
Between bubble flow pattern and flow behavior；It is characterized in that, specifically including:
(1) experimental rig
Experimental rig is totally made of six parts, is respectively as follows: Spent Fuel Pool boiling test section 1, water purification system 2, water storage
And water-carriage system 3, temperature control system 4, data acquisition is 5 and drainage system 6；
The Spent Fuel Pool boiling test section 1 is fixed according to 9 х 9 by grid spacer 20 in stainless steel sleeve 11
81 stainless steel heating rod pipes, 10, the 81 stainless steel heating rod pipes 10 for being arranged into square pass through 9 х 9 on bottom plate 22 and are arranged into
The corresponding hole of square, silica gel pad 9 and gland 23 are put on, by snail 21, silica gel pad 9 is pressed in the slot of bottom plate 22
It is interior, realize the sealed connection of stainless steel heating rod pipe 10 and bottom plate 22；Stainless steel sleeve 11 is connect with 22 welded seal of bottom plate；
(2) thermocouple is arranged
The boil main object of test temperature measurement of Spent Fuel Pool is stainless steel heating rod tube wall face temperature and adjacent
The water temperature in waters；For the vertical tube bundle of 9 × 9 arrangements, it is contemplated that certain symmetry principle takes the square of 9 × 9 arrangements
Thermometric region of the delta-shaped region that upper left corner fine line surrounds as this test；In triangle thermometric region, every stainless
Inside steel heating tube along the vertical direction on be evenly arranged 6 thermometric K-type thermocouples 25.
The water purification system 2 is made of water purifier 15 and the connection of clarified water pump 16, and passes through control valve and water storage and water delivery system
14 water inlet of the water tank connection of system 3；
The water storage and water-carriage system 3 are to go here and there in 14 bottom water outlet of water tank and control valve, filter 13 and water-delivery pump 12
Connection；It is connect again by control valve with 11 water inlet of stainless steel sleeve；
The temperature control system 4 is made of control cabinet 8 and distribution box 7, the output end and stainless steel heating rod of control cabinet 8
The lead 24 of pipe 10 connects；
Data acquisition is 5 to be made of display 17 and data acquisition module 18, and data acquisition module 18 connects weary combustion
The temperature sensor that material pond is boiled in test section 1 and the high-speed camera being mounted near form 19；
The drainage system 6 is made of drain valve and draining melt pit.
Seven groups of grid spacers 20 are arranged in 81 stainless steel heating rods pipe 10 altogether in the axial direction, prevent stainless steel from adding
Hot pin pipe 10 shakes during testing Working fluid flow, realizes that the transverse direction of stainless steel heating rod pipe is fixed, and heated
Reinforce test working fluid in journey to stir and make muddy.
The test working medium is deionized water prepared by water purifier 15, and conductivity meets test water less than 0.5 μ s/cm
Matter requirement.
The temperature-controlling system Control experiment temperature is adjusted, and is declined by adjusting different heating powers to simulate different spentnuclear fuels
Relict heat；Automatic measurement, acquisition, transmission and the guarantor to each temperature point temperature are realized using data collection system during test
It deposits, while shooting the interbank steam bubble flow pattern of heating tube using high-speed camera.
The Spent Fuel Pool boiling test section is designed as normal pressure, and open circuit is communicated with the atmosphere.
Inside the stainless steel heating tube along the vertical direction on be evenly arranged 6 thermometric K-type thermocouples, in genesis analysis
In 6 thermometric height, each height arranges 2 water temperature thermocouples at tube bank channel center and at tube bank side, for measuring
Close to the waters temperature of near-wall.
Beneficial effects of the present invention: this test-bed may be implemented: (1) being back with Spent Fuel Pool coolant failure accidents
Scape, wall temperature and adjacent waters fluid temperature variations for irradiated fuel assembly are researched and analysed, and it is vertical to obtain spentnuclear fuel cluster
Interbank heat transfer characteristic.(2) pass through setting different heating power, the different multi-states such as initial temperature and dry combustion method tests, research
The pool boiling heat transfer characteristic of spentnuclear fuel cluster.(3) in the boiling heat transfer stage, lead to using high-speed camera is narrow to vertical tube bundle
Flow pattern and flow behavior are studied in road.(4) safety issue when pool boiling occurs in entire Spent Fuel Pool is evaluated.
Detailed description of the invention
Fig. 1 is that spent fuel rods restrains spraying cooling pilot system schematic diagram.
Fig. 2 is fuel rod Pipe bundle structure schematic diagram
Fig. 3 is the A-A view and thermocouple temperature measurement delta-shaped region of Fig. 2
Fig. 4 is built-in thermocouple heating tube arrangement schematic diagram.
Fig. 5 is experimental section entirety temperature thermocouple arrangement
Specific embodiment
The present invention proposes a kind of spentnuclear fuel pool boiling test-bed, and the test-bed is with nuclear power station spent fuel reservoir cold
But thrashing situation is background, studies spentnuclear fuel cluster pool boiling due to caused by Decay afterheat in Spent Fuel Pool
Heat transfer characteristic；Experimental study content includes bubble stream between boiling heat transfer coefficient, vertical tube bundle between temperature field, vertical tube bundle in pond
Type and flow behavior；It is explained with reference to the accompanying drawings and examples.
Fig. 1 show spent fuel rods tube bank spraying cooling pilot system schematic diagram.Include: in figure
(1) experimental rig
Experimental rig is totally made of six parts, is respectively as follows: Spent Fuel Pool boiling test section 1, water purification system 2, water storage
And water-carriage system 3, temperature control system 4, data acquire the drainage system 6 for being 5 and being made of drain valve and draining melt pit；
The Spent Fuel Pool boiling test section 1 is fixed according to 9 х 9 by grid spacer 20 in stainless steel sleeve 11
81 stainless steel heating rod pipes, 10, the 81 stainless steel heating rod pipes 10 for being arranged into square pass through 9 х 9 on bottom plate 22 and are arranged into
The corresponding hole of square, puts on silica gel pad 9 and gland 23, by snail 21, silica gel pad 9 is pressed in the slot of bottom plate 22
It is interior (as shown in Figure 2), realize the sealed connection of stainless steel heating rod pipe 10 and bottom plate 22；Stainless steel sleeve 11 and bottom plate 22 weld
Connect sealed connection.Wherein, water purification system 2 is made of water purifier 15 and the connection of clarified water pump 16, and passes through control valve and water storage and defeated
14 water inlet of water tank of water system 3 connects；Water storage and water-carriage system 3 are in 14 bottom water outlet of water tank and control valve, filtering
Device 13 and water-delivery pump 12 are connected；It is connect again by control valve with 11 water inlet of stainless steel sleeve；Temperature control system 4 is by control cabinet
8 and distribution box 7 form, the output end of control cabinet 8 connect with the lead 24 of stainless steel heating rod pipe 10；Data acquisition is 5 by showing
Show that device 17 and data acquisition module 18 form, the temperature that data acquisition module 18 connects in Spent Fuel Pool boiling test section 1 passes
Sensor and the high-speed camera being mounted near form 19；The temperature-controlling system Control experiment temperature is adjusted, by adjusting difference
Heating power simulate different spentnuclear fuel Decay afterheats；It is realized using data collection system to each temperature point temperature during test
Automatic measurement, acquisition, transmission and the preservation of degree, while the interbank steam bubble flow pattern of heating tube is shot using high-speed camera.It is described
Spent Fuel Pool boiling test section is designed as normal pressure, and open circuit is communicated with the atmosphere.
(2) thermocouple is arranged
The boil main object of test temperature measurement of Spent Fuel Pool is stainless steel heating rod tube wall face temperature and adjacent
The water temperature in waters；For the vertical tube bundle of 9 × 9 arrangements, it is contemplated that certain symmetry principle takes the square of 9 × 9 arrangements
Thermometric region of the delta-shaped region that upper left corner fine line surrounds as this test；In triangle thermometric region, every stainless
Inside steel heating tube along the vertical direction on be evenly arranged 6 thermometric K-type thermocouples 25 (as shown in figure 3, figure 4 and figure 5).Wherein, 81
Seven groups of grid spacers 20 (as shown in Figure 2) are arranged in root stainless steel heating rod pipe 10 altogether in the axial direction, prevent stainless steel from heating
Stick pipe 10 shakes during testing Working fluid flow, realizes that the transverse direction of stainless steel heating rod pipe is fixed, and in heating process
Middle reinforcement test working fluid is stired and make muddy.The test working medium is deionized water prepared by water purifier 15, and conductivity is less than 0.5 μ
S/cm meets test water quality requirement.
Inside the stainless steel heating tube along the vertical direction on be evenly arranged 6 thermometric K-type thermocouples, in genesis analysis
In 6 thermometric height, each height arranges 2 water temperature thermocouples (such as Fig. 5 institute at tube bank channel center and at tube bank side
Show), for measuring the waters temperature close to near-wall.
Mentality of designing of the invention is further described below:
Experimental rig is totally made of six parts, is respectively as follows: Spent Fuel Pool boiling test section 1, water purification system 2, water storage
And water-carriage system 3, temperature control system 4, data acquisition is 5 and drainage system 6；Due to heating rod bundle diameters ten in test section
It is point limited, if there are larger impurity in test working medium, surface scale is easily caused even impurity accumulated plugging flow channel occur,
Therefore test prepares deionized water using equipment of De-ionized Water, and conductivity meets test water quality requirement less than 0.5 μ s/cm, from
And it ensure that diabatic process, the reliability of flow condition from source while being also beneficial to measurement accuracy；Subsequent deionized water
Before entering test section, kept in first in high-level water storage case, high-level water storage case is welded by stainless steel plate, and inside is lined with
Polyvinyl chloride plastic flitch, top can be effectively prevented impurity and are mixed into equipped with top cover, be always ensured that deionized water meets test
It is required that the reason of setting high-level water storage case is that the deionized water cleaning equipment rate of filtration is limited, main feed pump lift is higher, because
This cannot achieve deionized water preparation and pours water with test section and carry out simultaneously；Deionized water is defeated by main feed pump by high-level water storage case
It is fed into test section cabinet, stopping is poured water after reaching predetermined reserve-water-level, and test section system is mainly heated by 81 stainless steels
Pipe is formed for simulating spentnuclear fuel cluster, and heater strip built in heating tube simulates spentnuclear fuel heat release, to prevent heating rod tube bank from shaking,
Six groups of grid spacers are arranged in the axial direction；Test temperature adjusting is controlled by temperature-controlling system, by adjusting different heating function
Rate is for simulating different decays；The automatic measurement to each temperature point temperature is realized using data collection system during test, is adopted
Collection, transmission and preservation, while the interbank steam bubble flow pattern of heating tube is shot using high-speed camera.Test-bed major parameter such as table
Shown in 1.
1 test-bed major parameter of table
The design of spentnuclear fuel cluster
For simulating spentnuclear fuel cluster, it is mainly made of test section cabinet and stainless steel heating rod pipe test section main system,
The former simulates Spent Fuel Pool, and the latter is for simulating irradiated fuel assembly.Stainless steel heating tube totally 81, according to square 9 × 9 rows
Column, heating tube overall length 4800mm, box house heating tube length be 4500mm, hair hot end length be 4270mm, diameter 9.6mm,
Using uniform heating pattern；To prevent stainless steel heating tube from shaking during Working fluid flow, set altogether in the axial direction
Seven groups of grid spacers are set, not only can reinforce during heating fluid and stir and make muddy, can also realize the cross of stainless steel heating rod pipe
To fixation；The interbank arrangement spacing of stainless steel heating rod is 3.4mm, and stainless steel heating rod pipe and box body wall identity distance are from for 14mm；
To avoid additional stress, stainless steel heating tube is using finishing, it is ensured that surface is smooth, without pit and collision scar etc.；It is real
Test section stainless steel water tank cross section be side length 165mm square, height 6000mm, for convenient for testing crew during the test
It observes at any time while shooting flow pattern reserved window for high-speed camera, respectively arrange 7 sights to the adjacent two sides of cabinet in test section
Window is examined, observation window is having a size of 435mm × 135mm, using quartz glass；Side is according to hot with heating tube inside in cabinet outside the enclosure
The concordant place drilling insertion water temperature thermocouple of galvanic couple height, to measure the fluid temperature (F.T.) near heating tube；For guarantee test section
Internal working medium maintains steady temperature as far as possible, coats spun-glass insulation cotton on the outside of test section to reduce heat loss, tries
It tests shown in a section schematic diagram (as shown in Figure 3).
Heating tube major parameter is as shown in the table:
2 test section geometric parameter of table
Spentnuclear fuel Decay afterheat is simulated by stainless steel heating tube during test, heater strip has higher inside heating tube
Resistance, generated heat further heats stainless steel tube wall in thermo-conducting manner after energization, and stainless steel tube wall reheats stream
Through its external test working medium.Since heating bottom of the tube is connected with heater strip power supply line and thermocouple lead, while heating tube
Wall is very thin, therefore can not be welded, while working medium weight is born in experiment casing bottom, passes through for mode flow working medium interbank
Gap outflow, it is necessary to which carrying out effectively sealing prevents working medium leakage guarantee test personnel safety simultaneously.Test section sealed bottom structure
As shown in the lower half Fig. 2.
It is machined with square arrangement in the middle part of stainless steel plate, 81 through-holes that diameter is 9.6mm, is heated for stainless steel
Pipe is across being machined with side length in the middle part of bottom plate, square, depth 35mm groove is used in inside grooves filling gel gasket for 134mm
In blind, ensure to seal, depth of packing reaches 30mm；Gland is connect by bolt with bottom plate, the pretightning force that bolt provides
Silica gel pad is compressed, has the function that leakage test working medium by its deformation.
The temperature measurement main object of Spent Fuel Pool boiling test is the water temperature of heating tube wall surface temperature and adjacent waters.
For the vertical tube bundle of 9 × 9 arrangements, it is contemplated that certain symmetry principle takes the delta-shaped region of upper left side shown in Fig. 3, Fig. 4
Thermometric region as this test.
In triangle thermometric region, inside every stainless steel heating tube along the vertical direction on be evenly arranged 6 thermometric K-types
Thermocouple, each thermocouple difference in height is 700mm, for measuring heating tube inner wall temperature.Heating tube specific size and thermoelectricity
Even distribution situation is as shown in figure 3, figure 4 and figure 5.
The heating method that stainless steel hot galvanic couple heating tube uses is is evenly heated, pipe outside diameter 9.6mm, and wall thickness is
0.68mm.Thermocouple is close to heating tube inner wall, can directly measure heating tube inner wall temperature, pass through between heater strip and thermocouple
Magnesia powder is filled.
In 6 thermometric height of genesis analysis, each height arranges 2 at tube bank channel center and at tube bank side
Water temperature thermocouple, for measuring the waters temperature close to near-wall, thermocouple arrangement is as shown in Figure 5.
Test method and step:
Spent Fuel Pool boiling is tested using nuclear power station spent fuel reservoir in cooling system failure conditions as background, and weary combustion is studied
Expect spentnuclear fuel cluster pool boiling heat transfer characteristic due to caused by Decay afterheat in pond.Experimental study content includes pond
Bubble flow pattern and flow behavior etc. content between boiling heat transfer coefficient, vertical tube bundle between interior temperature field, vertical tube bundle.According to anti-
The phenomenon in various accidents for answering heap to be likely to occur is analyzed, and setting operating condition covers all parameter models being likely to occur as far as possible
It encloses.A series of experiments is done for 0~30kW of fuel assembly thermal power, also the initial temperature different to pool inner water temperature has carried out reality
It tests.
Its specific test method is as follows:
(1) first integral experiment rack is checked before test, whether the connection including each system equipment is correct, each
The sealing of interface and test water tank is complete, and acquisition system works normally.
(2) test section drain valve is closed, water-supply valve is successively opened, starts water purification system, injects deionization toward test water tank
Water, while water level is monitored, water purification system is closed after reaching predetermined water level.
(3) after completing measuring device debugging, electrical power cabinet power supply is opened, operating condition of test is set on digit manipulation plate
Electrical power is evenly heated stainless steel heating tube in water tank.
(4) it is carried out simultaneously in test, stainless steel heating tube heating state, observation boiling starting is observed by test observation window
Point position.And high-speed photography is carried out to bubble flow pattern and kinetic characteristic using high-speed camera in desired height position.
(5) as test carries out, water tank starts boiling phenomenon occur, followed by reforwarding after water tank reaches whole pool boiling
Row for a period of time, after the key parameter for recording boiling stage, closes power control cabinet power supply, after data collection system runs a period of time
Stop acquiring again.
(6) when carrying out half dry combustion method test, with the decline of water level in water tank, the moment monitors heating tube wall surface temperature, to prevent
Burn heating tube.
(7) boiling stops heating experimental section after the test, natural cooling is carried out to bulk testing rack, at a temperature of
When being down to room temperature, record water temperature drop position, tested in water evaporation capacity.
(8) drain valve is opened after testing, the water in water tank is arranged to melt pit.
(9) after the test, it checks whether all valve switch, power supply close, checks again for experimental rig and junction
Leakproofness, processing test data complete correlation test report.
By above-mentioned specific experiment, obtains result and is summarized as follows:
(1) under specified heat flow density, vertical direction tube wall temperature is distributed between vertical tube bundle are as follows: free convection stage top
Tube wall temperature is higher than lower part tube wall temperature；It is lower than lower part tube wall temperature in boiling stage top tube wall temperature.
(2) there is apparent thermal stratification in free convection and boiling stage in pond, wherein in the free convection stage
Thermal stratification is affected between heat exchange vertical tube bundle；In boiling stage, thermal stratification makes pond entirety do not occur
Saturation pool boiling, upper area is saturation boiling, and intermediate region is subcooled boiling, and bottom section is still in single-phase convection
Heat exchange.
(3) for heating tube under different operating conditions, heating power is higher, and the rate of heat addition is faster, on wall surface temperature and fluid temperature (F.T.)
Raising speed rate is faster, and the time for reaching saturation boiling is shorter；Initial temperature is higher, and the time used in the reached saturation temperature of fluid gets over
It is short.
(4) vertical tube bundle center tube wall temperature is higher than outside tube bank temperature on boiling stage, same level.
(5) the vertical tube bundle boiling stage coefficient of heat transfer, which is researched and analysed, obtains, the coefficient of heat transfer under different height is with hot-fluid
The increase of density and increase；The coefficient of heat transfer increases with the increase of height under identical heat flow density.
(6) it is tested by half dry combustion method, heating tube exchanges heat in exposed dry combustion method sharply to be deteriorated, and the coefficient of heat transfer sharply declines, and adds
Heat pipe outer wall temperature increases rapidly in approximately linear, should avoid the exposed dry combustion method of irradiated fuel assembly in engineering as far as possible.
(7) by many experiments, heating tube wall surface temperature does not occur that there is no DNB (to deviate complex in boiling stage
Boiling) phenomenon, under water covering, heating pipe outer wall keeps stablizing in boiling stage temperature, and heat transfer deterioration will not occur.
Claims (10)
1. a kind of spentnuclear fuel pool boiling test-bed, the test-bed is with nuclear power station spent fuel reservoir in cooling system failure feelings
Condition is background, studies spentnuclear fuel cluster pool boiling heat transfer characteristic due to caused by Decay afterheat in Spent Fuel Pool；Examination
Testing research contents includes that bubble flow pattern and flowing are special between boiling heat transfer coefficient, vertical tube bundle between temperature field, vertical tube bundle in pond
Property；It is characterized in that, specifically including:
(1) experimental rig
Experimental rig is totally made of six parts, is respectively as follows: Spent Fuel Pool boiling test section (1), water purification system (2), water storage
And water-carriage system (3), temperature control system (4), data acquisition system (5) and drainage system (6)；
Spent Fuel Pool boiling test section (1) is designed as normal pressure, and open circuit is communicated with the atmosphere；Spent Fuel Pool boiling
Test section is in stainless steel sleeve (11) by grid spacer (20) fixed 81 stainless steels for being arranged into square according to 9 х 9
Heating rod pipe (10), 81 stainless steel heating rod pipes (10) pass through the corresponding hole that 9 х 9 on bottom plate (22) are arranged into square,
Silica gel pad (9) and gland (23) are put on, by snail (21), silica gel pad (9) is pressed in the slot of bottom plate (22), is realized not
The sealed connection of rust steel heating rod pipe (10) and bottom plate (22)；Stainless steel sleeve (11) is connect with bottom plate (22) welded seal；
(2) thermocouple is arranged
The main object of Spent Fuel Pool boiling test temperature measurement is stainless steel heating rod tube wall face temperature and adjacent waters
Water temperature；For the vertical tube bundle of 9 × 9 arrangements, it is contemplated that certain symmetry principle takes the square upper left corner of 9 × 9 arrangements
Thermometric region of the delta-shaped region that fine line surrounds as this test；In triangle thermometric region, every stainless steel heating
Inside pipe along the vertical direction on be evenly arranged 6 thermometric K-type thermocouples (25).
2. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that the water purification system (2)
It is made of water purifier (15) and clarified water pump (16) connection, and passes through the water tank (14) of control valve and water storage and water-carriage system (3)
Water inlet connection.
3. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that the water storage and water delivery system
System (3) is to connect in water tank (14) bottom water outlet with control valve, filter (13) and water-delivery pump (12)；Again by control valve with
The connection of stainless steel sleeve (11) water inlet.
4. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that the temperature control system
(4) it is made of control cabinet (8) and distribution box (7), the output end of control cabinet (8) and the lead (24) of stainless steel heating rod pipe (10)
Connection.
5. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that data acquisition system
(5) it is made of display (17) and data acquisition module (18), data acquisition module (18) connects Spent Fuel Pool boiling test
Section (1) in temperature sensor and be mounted on the high-speed camera of form (19) nearby.
6. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that the drainage system (6)
It is made of drain valve and draining melt pit.
7. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that 81 stainless steels add
Seven groups of grid spacers (20) are arranged in hot pin pipe (10) altogether in the axial direction, prevent stainless steel heating rod pipe (10) in test working medium
It is shaken in flow process, realizes that the transverse direction of stainless steel heating rod pipe is fixed, and reinforce test working medium stream during heating
Body is stired and make muddy.
8. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that the test working medium is net
The deionized water of hydrophone (15) preparation, conductivity meet test water quality requirement less than 0.5 μ s/cm.
9. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that the stainless steel heating tube
It is internal along the vertical direction on be evenly arranged 6 thermometric K-type thermocouples, in 6 thermometric height of genesis analysis, each height exists
It restrains and arranges 2 water temperature thermocouples at tube bank side at channel center, for measuring the waters temperature close to near-wall.
10. a kind of spentnuclear fuel pool boiling test-bed according to claim 1, which is characterized in that the temperature-controlling system control
Test temperature processed adjusts, and simulates different spentnuclear fuel Decay afterheats by adjusting different heating powers；Number is used during test
Automatic measurement, acquisition, transmission and the preservation to each temperature point temperature are realized according to acquisition system, while being clapped using high-speed camera
Take the photograph the interbank steam bubble flow pattern of heating tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811113709.7A CN109493982A (en) | 2018-09-25 | 2018-09-25 | A kind of spentnuclear fuel pool boiling test-bed |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811113709.7A CN109493982A (en) | 2018-09-25 | 2018-09-25 | A kind of spentnuclear fuel pool boiling test-bed |
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| CN110470695A (en) * | 2019-08-29 | 2019-11-19 | 哈尔滨工程大学 | A kind of bulk container boiling experimental system |
| CN110534222A (en) * | 2019-08-26 | 2019-12-03 | 中广核陆丰核电有限公司 | A kind of nuclear safety control method after nuclear power unit complete unloading |
| CN114113211A (en) * | 2021-11-26 | 2022-03-01 | 上海交通大学 | Natural cooling flow heat transfer characteristic research experiment system and method |
| CN114326870A (en) * | 2021-11-10 | 2022-04-12 | 江苏华洋新思路能源装备股份有限公司 | Adjustable hot water flow testing arrangement |
| WO2023284267A1 (en) * | 2021-07-16 | 2023-01-19 | 中国华能集团清洁能源技术研究院有限公司 | System for studying flow boiling in visual annular channel, and operating method therefor |
| CN115910401A (en) * | 2022-11-07 | 2023-04-04 | 中国核动力研究设计院 | Visualization device, system and method for simulating downstream two-phase flow field mixing effect |
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| CN110133037A (en) * | 2019-06-12 | 2019-08-16 | 中国核动力研究设计院 | A kind of experimental provision to conduct heat for studying pool boiling under the structure of different heating face |
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| CN114326870A (en) * | 2021-11-10 | 2022-04-12 | 江苏华洋新思路能源装备股份有限公司 | Adjustable hot water flow testing arrangement |
| CN114113211A (en) * | 2021-11-26 | 2022-03-01 | 上海交通大学 | Natural cooling flow heat transfer characteristic research experiment system and method |
| CN114113211B (en) * | 2021-11-26 | 2024-03-12 | 上海交通大学 | Natural cooling flow heat transfer characteristic research experiment system and method |
| CN115910401A (en) * | 2022-11-07 | 2023-04-04 | 中国核动力研究设计院 | Visualization device, system and method for simulating downstream two-phase flow field mixing effect |
| CN115910401B (en) * | 2022-11-07 | 2023-09-05 | 中国核动力研究设计院 | Visualization device, system and method for simulating downstream two-phase flow field mixing effect |
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