CN105007641B - Critical heat flux density test heating rod - Google Patents
Critical heat flux density test heating rod Download PDFInfo
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- CN105007641B CN105007641B CN201510451490.1A CN201510451490A CN105007641B CN 105007641 B CN105007641 B CN 105007641B CN 201510451490 A CN201510451490 A CN 201510451490A CN 105007641 B CN105007641 B CN 105007641B
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- pipe
- nickel
- flux density
- heat
- ceramic member
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- H—ELECTRICITY
- H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
- H05B—ELECTRIC HEATING; ELECTRIC LIGHT SOURCES NOT OTHERWISE PROVIDED FOR; CIRCUIT ARRANGEMENTS FOR ELECTRIC LIGHT SOURCES, IN GENERAL
- H05B3/00—Ohmic-resistance heating
- H05B3/40—Heating elements having the shape of rods or tubes
- H05B3/42—Heating elements having the shape of rods or tubes non-flexible
- H05B3/44—Heating elements having the shape of rods or tubes non-flexible heating conductor arranged within rods or tubes of insulating material
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The open a kind of critical heat flux density test heating rod of the present invention, it includes nickel rod, adds heat pipe, nickel pipe, copper pipe, ceramic member, copper sheet and thermocouple, add the fixing connection that heat pipe, nickel pipe and copper pipe dock successively and seal, and form the barred body in hollow structure, nickel rod is connected with extraneous top charging equipment, copper pipe is connected with extraneous bottom charging equipment, ceramic member is attached on the inwall of barred body and around forming hot chamber, copper sheet adds heat pipe in being horizontally set at uniformly in hot chamber and being positioned at, and thermocouple is unsettled being arranged at hot intracavity and fix by copper sheet；Heating-up temperature of the present invention is high, heat flow density is high and compact conformation, meet critical heat flux density test required, and temperature parameter is measured in real time by thermocouple and exported, can precisely realize simulating nuclear fuel heat release and effectively meeting critical heat flux density test requirements document, the critical heat flux density of nuclear fuel rod under different operating condition can also be measured, the research and development of nucleus fuel assembly are had good supporting role.
Description
Technical field
The present invention relates to a kind of nuclear reactor experimental study field, particularly relate to a kind of for studying nuclear fuel group
The critical heat flux density test heating rod of part.
Background technology
In convective boiling, mainly there is two kinds of critical heat flux density: deviation nucleate boiling is with dry.
In presurized water reactor nuclear power unit Steady State Thermal designs, the most only run into the saturated of subcooled boiling and low quality
Boiling, hence deviates from nucleate boiling heat flow density and is even more important.
Deviation nucleate boiling mechanism model mainly includes three types: (a) is big when forming one on heater element wall
During steam bubble, bottom it, thin electrolyte film constantly evaporates, and forms dry spot, causes heater element wall heat transfer deterioration；
B (), when the steam bubble layer on heater element wall thickens and be enough to hinder liquid moistening wall, steam will be unable to ease
Go out and form vapour shell, plug flow channel for liquids, cause heater element wall to occur overheated；C () is close at high hot-fluid
Under degree, when the liquid film evaporation speed between vapour block and heater element wall is more than liquid moistening wall speed, lead
Cause heater element wall abnormal overheated and dry.Owing to critical heat flux density mechanism and phenomenon thereof are the most complicated, logical
Frequently with the method for experimental study, obtain Critical heat flux correlation.Mesh is tested according to critical heat flux density
And content, by similarity criterion requirement design experiment section, Study system pressure, mass velocity, critical point
The impact on critical heat flux density of the factor such as vapor content, structural parameters.
In critical heat flux density process of the test, critical judgement typically uses heating element heater wall temperature to judge, it is sentenced
According to having two: one to be, heating element heater wall temperature rises to speed and meets or exceeds certain certain value；Two is heating element heater wall
Temperature meets or exceeds maximum temperature limit value.Critical heat flux density test data analyzer requires to provide the confidence level of 95%
On, there is not the critical heat flux ratio of critical boiling in the probability of at least 95%.
To uniform heat run section, general employing local average parametric method processes critical heat flux density test data；
To non-uniform heating test section, general employing subchannel analysis method processes critical heat flux density test data.?
In nuclear power unit review, critical heat flux density is important restricted thermal-hydraulic parameter, it big
The little safety directly affecting nuclear power unit and economy.By optimizing fuel assembly structure, improve critical
Heat flow density, makes reactor system produce maximum thermal power, thus is ensureing nuclear power unit engineering design
On the basis of safe and reliable, improve economy.
In nuclear fuel assembly is researched and developed, critical heat flux density is the key characterizing fuel assembly thermal-hydraulic performance
One of parameter, the critical heat flux density of fuel assembly can't use the method for theory to be predicted, only at present
Can be obtained by test, the most therefore this heating rod produces, and it mainly flows through conductor with electric current and produces heat
For principle, the uniform heat produced by heating rod is simulated nuclear fuel heat release, thus is carried out critical heat flux density
Experimental study.
United States Patent (USP) US4720624 discloses a kind of heating rod, and this heating rod is non-uniform heating rod, material
For rustless steel, zircaloy or inconel, the thickness of non-uniform heating rod and resistance are along with rod length direction
Change, but external diameter is constant.Apply voltage at the two ends of non-uniform heating rod, have electric current and flow through, enter
And produce heat, simulate core heat release and carry out correlation test research；This non-uniform heating rod can produce along axle
To the heat of non-uniform Distribution, but it is in technology such as overall package, heating-up temperature measurement, external voltage connections
Certain defect is there is in problem.
United States Patent (USP) US4156127 also discloses that a kind of electrically heated rod, and this electrically heated rod is made up of three layers of extruding,
Nexine is politef light wall pipe, play insulation and with media for heat exchange effect；Intermediate layer is carbon and politef
Mixture, play conductive exothermal effect；Outermost layer is politef thickness pipe, rises and insulate and heat insulation with environment
Effect；Draw, at heating rod head and the tail two ends, the wire connected with intermediate layer, when applying voltage on wire, have
Electric current flows through the intermediate layer being evenly arranged carbonizable substance, and then produces consistent heat generation amount；Therefore this electrically heated rod energy
Produce the most equally distributed heat, but maximum temperature is only capable of reaching 260 DEG C, does not far reach critical heat flux density
Test temperature required；Zone of heating and medium are by teflon insulation and heat conduction, it is impossible to realize rapid, high volume
Heat exchange；Being relatively large in diameter of electrically heated rod, it is impossible to be processed assembling according to nuclear fuel size.
Therefore, need one badly can precisely realize simulating nuclear fuel heat release and effectively meeting critical heat flux density examination
Test the critical heat flux density test heating rod that research requires.
Summary of the invention
It is an object of the invention to provide one can precisely realize simulating nuclear fuel heat release and effectively meeting critical
The critical heat flux density test heating rod of heat flow density test requirements document.
For achieving the above object, the invention provides a kind of critical heat flux density test heating rod, it is adaptable to
Simulation nuclear fuel heat release and carry out critical heat flux density test, it include nickel rod, add heat pipe, nickel pipe, copper pipe,
Ceramic member, copper sheet and thermocouple, the upper end of described nickel rod is connected with extraneous top charging equipment, described nickel rod
Lower end and the docking of the described upper end adding heat pipe and fixing being connected of sealing, described in add the lower end of heat pipe with described
Nickel pipe upper end docking and seal fixing connection, the upper end of described copper pipe dock with the lower end of described nickel pipe and
The fixing connection sealed, the lower end of described copper pipe is connected with external world's bottom charging equipment, described in add heat pipe, nickel
Pipe and copper pipe dock the barred body formed in hollow structure successively, and described ceramic member is attached to described in hollow structure
Barred body inwall on and around formed hot chamber, described copper sheet is in being horizontally set at uniformly in described hot chamber also
Being positioned at and add heat pipe, described thermocouple is unsettled being arranged at described hot intracavity and fix by described copper sheet.
It is preferred that many described thermocouples are parallel and staggered to be distributed in described hot intracavity.
It is preferred that the rounded structure of cross-sectional profiles of the described barred body in hollow structure.
It is preferred that described ceramic member include being mutually butted successively add in heat pipe ceramic member in ceramic member, nickel pipe
And ceramic member in copper pipe, described in add ceramic member in heat pipe be attached to be positioned at described in add barred body corresponding to heat pipe
On inwall, in described nickel pipe, ceramic member is attached to be positioned on the inwall of the barred body corresponding to described nickel pipe, described
In copper pipe, ceramic member is attached to be positioned on the inwall of the barred body corresponding to described copper pipe.
Compared with prior art, owing to heating-up temperature of the present invention is high, meet critical heat flux density test required,
And temperature parameter is measured in real time by thermocouple and exported；The another present invention can also produce bigger heat flow density,
There is good heat conductivity, rapid, high volume heat exchange can be realized, can be processed assembling according to nuclear fuel size,
Solve existing heating rod and tend not to be reliably connected the problem of high-current supply, reach accurate control effective
The purpose of heating length；Present configuration is compact simultaneously, size is unified and accurately, heat flow density high, can be
Work safe and reliable under high temperature and high pressure condition, therefore the present invention can precisely realize simulating nuclear fuel heat release and energy
Effectively meet critical heat flux density test requirements document, moreover it is possible to measure the critical heat of nuclear fuel rod under different operating condition
The research and development of nucleus fuel assembly are had good supporting role by current density.
Accompanying drawing explanation
Fig. 1 is the structural representation of critical heat flux density test heating rod of the present invention.
Fig. 2 is the sectional view of line A-A along Fig. 1.
Fig. 3 is the sectional view of line B-B along Fig. 1.
Fig. 4 is the sectional view of line C-C along Fig. 1.
Detailed description of the invention
With reference now to accompanying drawing, describing embodiments of the invention, element numbers similar in accompanying drawing represents similar unit
Part.
As it is shown in figure 1, the critical heat flux density test heating rod 100 of the present invention, it is used for simulating nuclear fuel and releases
Heat and carry out critical heat flux density test, it include nickel rod 10, add heat pipe 20, nickel pipe 30, copper pipe 40,
Ceramic member 50, copper sheet 60 and thermocouple 70, the upper end of described nickel rod 10 is connected with extraneous top charging equipment,
The lower end of described nickel rod 10 is connected with the described upper end docking adding heat pipe 20 and the fixing of sealing, uses nickel rod
10 dock fixing with adding heat pipe 20, it is ensured that also reduce invalid caloric value while intensity；Described add heat pipe
The lower end of 20 is connected with the docking of the upper end of described nickel pipe 30 and the fixing of sealing, adds heat pipe 20 in energising situation
Lower generation heat, it is existing for adding heat pipe 20, and it utilizes self-resistance energising to produce heat, thus realizes
Heating, the upper end of described copper pipe 40 is connected with the docking of the lower end of described nickel pipe 30 and the fixing of sealing, described
The lower end of copper pipe 40 is connected with extraneous bottom charging equipment, uses copper pipe 40 with extraneous bottom charging equipment even
Connect, while ensureing to be reliably connected high-current supply, also reduce invalid caloric value；Described add heat pipe 20,
Nickel pipe 30 and copper pipe 40 dock the barred body formed in hollow structure successively, and described ceramic member 50 is attached to described
Also in hollow structure on the inwall of the barred body in hollow structure and around formation hot chamber 51, i.e. ceramic member 50, heat
Chamber 51 is the hollow structure of ceramic member 50 and is formed, and utilizes pottery to have excellent insulating properties and thermal insulation,
Ensure that the accuracy of test data；Described copper sheet 60 is in being horizontally set at uniformly in described hot chamber 51 also
Be positioned at and add heat pipe 20, described thermocouple 70 in unsettled be arranged at described hot chamber 51 in and by described copper
Sheet 60 is fixed, and utilizes copper sheet 60 to have excellent heat conductivity and mechanicalness, therefore on the one hand by this copper sheet
Thermocouple 70 can firmly be fixed by 60, and another side can will add produced by heat pipe 20 by this copper sheet 60
Heat quickly conducts to thermocouple 70；Critical heat flux density test heating rod 100 heating-up temperature of the present invention
Height, can be met critical heat flux density test required, and be measured in real time and defeated by thermocouple 70 by temperature parameter
Go out；The critical heat flux density test heating rod 100 of the present invention can produce bigger heat flow density simultaneously, tool
Having good heat conductivity, can realize rapid, high volume heat exchange, therefore the present invention can precisely realize simulating nuclear fuel
Heat release and can effectively meet critical heat flux density test requirements document, moreover it is possible to measure nuclear fuel rod under different operating condition
Critical heat flux density, to nucleus fuel assembly research and development there is good supporting role；Separately, thermoelectricity is passed through
Even 70 measure appointment position temperature in real time, effectively avoid the critical heat flux density test heating of the present invention
Rod 100 is burned out.
Continuing with shown in Fig. 1, specifically, the lower end of nickel rod 10 is passed through to weld with the upper end adding heat pipe 20
The mode fixing connection that achieves a butt joint and seal, the two welding forms pad 11；Add the lower end of heat pipe 20
The fixing connection that the upper end of nickel pipe 30 achieves a butt joint again by the mode welded and seals, the two welds shape
Becoming pad 12, the mode that the upper end of same copper pipe 40 is also adopted by welding with the lower end of nickel pipe 30 realizes the two
Docking and the fixing connection sealed, the two welding forms pad 13；Realize above-mentioned by the way of welding
Fixing connection between device two-by-two, both ensure that intensity also reduced contact resistance simultaneously；Hereinafter continue knot
Close Fig. 2-Fig. 4 the critical heat flux density test heating rod 100 of the present invention is described in further detail:
Preferably, many described thermocouples 70 are distributed in described hot chamber 51 in parallel and staggered；I.e. originally
Invention is provided with the many thermocouples being parallel to each other 70, and every thermocouple 70 is arranged at diverse location, from
And form staggered distribution；The embodiment of Fig. 1-Fig. 4 of the present invention only gives two thermocouples 70 are set
Embodiment；Those skilled in the art are on the premise of technical scheme provided by the present invention, according to actual feelings
The demand of condition, it is not necessary to any creativeness can implement to arrange the embodiment party of three, four, five etc. thermocouples
Formula, no longer describes in detail at this.
In conjunction with Fig. 2-Fig. 4 Suo Shi preferably, the cross-sectional profiles of the described barred body in hollow structure is rounded
Structure.
In conjunction with Fig. 1-Fig. 4 Suo Shi preferably, described ceramic member 50 includes that be mutually butted successively adds in heat pipe
Ceramic member 50c in ceramic member 50b and copper pipe in ceramic member 50a, nickel pipe, described in add ceramic member 50a in heat pipe
It is attached to described in being positioned at add on the inwall of the barred body corresponding to heat pipe 20, ceramic member 50b attachment in described nickel pipe
On the inwall of the barred body being positioned at corresponding to described nickel pipe 30, in described copper pipe, ceramic member 50c is attached to be positioned at
On the inwall of the barred body corresponding to described copper pipe 40.
Continuing with Fig. 1-Fig. 4, owing to the critical heat flux density test heating rod 100 of the present invention heats temperature
Degree height, is met critical heat flux density test required, and is measured in real time and defeated by thermocouple 70 by temperature parameter
Go out；The another present invention can also produce bigger heat flow density, has good heat conductivity, can realize rapid, high volume
Heat exchange, can be processed assembling according to nuclear fuel size, solve existing heating rod and tend not to reliably connect
The problem connecing high-current supply, has reached the purpose of accurate control efficient heat generation length；Present configuration simultaneously
Compact, size unified and accurately, heat flow density high, work that can be safe and reliable under high temperature and high pressure condition,
Therefore the critical heat flux density test heating rod 100 of the present invention can precisely realize simulating nuclear fuel heat release and energy
Effectively meet critical heat flux density test requirements document, moreover it is possible to measure the critical heat of nuclear fuel rod under different operating condition
The research and development of nucleus fuel assembly are had good supporting role by current density.
Separately, involved in the present invention adds heat pipe 20 and the concrete structure of thermocouple 70 and operation principle, is
Well known to those of ordinary skill in the art, no longer it is described in detail at this.
Above disclosed only the preferred embodiments of the present invention, can not limit the present invention with this certainly
Interest field, the equivalent variations therefore made according to scope of the present invention patent, still belong to the present invention and contained
Scope.
Claims (4)
1. a critical heat flux density test heating rod, it is adaptable to simulate nuclear fuel heat release and carry out critical heat
Current density test, it is characterised in that: include nickel rod, add heat pipe, nickel pipe, copper pipe, ceramic member, copper sheet and
Thermocouple, the upper end of described nickel rod is connected with extraneous top charging equipment, and the lower end of described nickel rod adds with described
The upper end docking of heat pipe and the fixing connection sealed, described in add heat pipe the upper end of lower end and described nickel pipe dock
And the fixing connection sealed, the upper end of described copper pipe is connected with the docking of the lower end of described nickel pipe and the fixing of sealing,
The lower end of described copper pipe is connected with extraneous bottom charging equipment, described in add heat pipe, nickel pipe and copper pipe and dock successively
Forming the barred body in hollow structure, described ceramic member is attached on the inwall of the described barred body in hollow structure also
Around forming hot chamber, described copper sheet adds heat pipe in being horizontally set at uniformly in described hot chamber and being positioned at, institute
Stating thermocouple is unsettled being arranged at described hot intracavity and fix by described copper sheet.
2. critical heat flux density test heating rod as claimed in claim 1, it is characterised in that: many institutes
Stating thermocouple is parallel and staggered to be distributed in described hot intracavity.
3. critical heat flux density test heating rod as claimed in claim 1, it is characterised in that: described in
The rounded structure of cross-sectional profiles of the barred body of hollow structure.
4. critical heat flux density test heating rod as claimed in claim 1, it is characterised in that: described pottery
Ceramic member, institute in ceramic member and copper pipe in ceramic member, nickel pipe in what porcelain piece included being mutually butted successively add heat pipe
State add ceramic member in heat pipe be attached to be positioned at described in add on the inwall of the barred body corresponding to heat pipe, in described nickel pipe
Ceramic member is attached to be positioned on the inwall of the barred body corresponding to described nickel pipe, and in described copper pipe, ceramic member is attached to
It is positioned on the inwall of the barred body corresponding to described copper pipe.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510451490.1A CN105007641B (en) | 2015-07-29 | 2015-07-29 | Critical heat flux density test heating rod |
| PCT/CN2015/097228 WO2017016136A1 (en) | 2015-07-29 | 2015-12-14 | Heating rod for critical heat flux test |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510451490.1A CN105007641B (en) | 2015-07-29 | 2015-07-29 | Critical heat flux density test heating rod |
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| CN105007641A CN105007641A (en) | 2015-10-28 |
| CN105007641B true CN105007641B (en) | 2016-09-28 |
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| CN201510451490.1A Active CN105007641B (en) | 2015-07-29 | 2015-07-29 | Critical heat flux density test heating rod |
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| WO (1) | WO2017016136A1 (en) |
Families Citing this family (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105007641B (en) * | 2015-07-29 | 2016-09-28 | 中广核研究院有限公司 | Critical heat flux density test heating rod |
| CN106158057B (en) * | 2016-08-17 | 2019-12-13 | 中国核电工程有限公司 | simulation device of spent fuel pool |
| CN107945895A (en) * | 2017-06-19 | 2018-04-20 | 重庆大学 | A kind of non-homogeneous electrically heated nuclear fuel simulation rod |
| CN108990185A (en) * | 2018-08-23 | 2018-12-11 | 镇江裕太防爆电加热器有限公司 | Compound high voltage heater |
| CN110296765A (en) * | 2019-06-06 | 2019-10-01 | 深圳市合众清洁能源研究院 | A kind of extraordinary non-homogeneous electrical heating elements of total temperature field measurement formula and manufacturing method |
| CN112080405A (en) * | 2020-09-23 | 2020-12-15 | 吴园园 | Clinical laboratory's bacterial incubator |
| CN114048424A (en) * | 2021-11-08 | 2022-02-15 | 中海油田服务股份有限公司 | Thermal recovery experimental method and device |
| CN114121319B (en) * | 2021-11-23 | 2022-08-05 | 西安交通大学 | Single-rod boiling critical test device and method for nuclear reactor under six-degree-of-freedom motion condition |
| CN114235887B (en) * | 2021-12-13 | 2024-08-02 | 西安交通大学 | Visual experimental apparatus of high temperature high pressure single stick critical heat flow density |
| CN115101224B (en) * | 2022-04-11 | 2024-09-06 | 国家电投集团科学技术研究院有限公司 | Electric heating simulated fuel rod |
| CN114916101B (en) * | 2022-05-12 | 2024-06-21 | 西北核技术研究所 | Heating rod and heating rod bundle device |
| CN114980378B (en) * | 2022-05-12 | 2024-06-21 | 西北核技术研究所 | Thermal hydraulic experimental device for electric heating fuel assembly |
| CN115223738B (en) * | 2022-07-15 | 2024-01-26 | 西安交通大学 | Experimental section and measuring method for measuring temperature and potential of cladding |
| CN115265817B (en) * | 2022-07-26 | 2024-09-17 | 北京理工大学 | Fuel coanda combustion transient heat flow density measuring device |
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| JPS52133321U (en) * | 1976-04-06 | 1977-10-11 | ||
| DE3373255D1 (en) * | 1982-11-23 | 1987-10-01 | Atomic Energy Authority Uk | Resistance heater probe |
| JPS6066198A (en) * | 1983-09-20 | 1985-04-16 | 動力炉・核燃料開発事業団 | Thickness inequality resistance heating tube and manufacture thereof |
| JPH10208853A (en) * | 1996-11-19 | 1998-08-07 | Ngk Spark Plug Co Ltd | Ceramic heater and manufacture thereof |
| CN201260249Y (en) * | 2008-07-21 | 2009-06-17 | 杨智慧 | Composite electric heating tube |
| FR2975527B1 (en) * | 2011-05-18 | 2013-07-05 | Commissariat Energie Atomique | DEVICE FOR ELECTRICALLY HEATING A LIQUID, ITS PRODUCTION METHOD AND APPLICATION TO THE ELECTRICAL SIMULATION OF NUCLEAR FUEL PENCILS |
| CN102592689B (en) * | 2012-02-06 | 2015-01-14 | 国核华清（北京）核电技术研发中心有限公司 | Composite material heating block, and manufacturing method and application thereof |
| US10222091B2 (en) * | 2012-07-17 | 2019-03-05 | Eemax, Inc. | Next generation modular heating system |
| CN102881339B (en) * | 2012-08-31 | 2014-10-15 | 中国核动力研究设计院 | Spherical fuel element simulator being convenient for wall temperature measurement and assembly technology thereof |
| CN104517656B (en) * | 2013-09-30 | 2016-08-17 | 中国核动力研究设计院 | A kind of slender type non-uniform heating element and processing technique thereof |
| CN105007641B (en) * | 2015-07-29 | 2016-09-28 | 中广核研究院有限公司 | Critical heat flux density test heating rod |
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- 2015-07-29 CN CN201510451490.1A patent/CN105007641B/en active Active
- 2015-12-14 WO PCT/CN2015/097228 patent/WO2017016136A1/en active Application Filing
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| WO2017016136A1 (en) | 2017-02-02 |
| CN105007641A (en) | 2015-10-28 |
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Address after: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Applicant after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Applicant after: China General Nuclear Power Corporation Applicant after: China wide nuclear electricity incorporated company Address before: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Applicant before: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Applicant before: China General Nuclear Power Corporation Applicant before: China wide nuclear electricity incorporated company |
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