CN105007641A - Heating rod used for critical heat flux density test - Google Patents
Heating rod used for critical heat flux density test Download PDFInfo
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- CN105007641A CN105007641A CN201510451490.1A CN201510451490A CN105007641A CN 105007641 A CN105007641 A CN 105007641A CN 201510451490 A CN201510451490 A CN 201510451490A CN 105007641 A CN105007641 A CN 105007641A
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- flux density
- heat flux
- nickel
- rod
- 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 invention discloses a heating rod used for a critical heat flux density test. The heating rod comprises a nickel rod, a heating tube, a nickel tube, a copper tube, a ceramic member, copper sheets and thermocouples. The heating tube, the nickel tube and the copper tube are fixedly connected in a butting and sealing way in turn so as to form a rod body with a hollow structure. The nickel rod is connected with external upper live equipment. The copper tube is connected with external lower live equipment. The ceramic member is attached to the internal wall of the rod body and surrounds so as to form a heat cavity. The copper sheets are evenly and transversely arranged in the heat cavity and positioned in the heating tube. The thermocouples are arranged in the heat cavity in a suspension way and fixed by the copper sheets. The heating rod used for the critical heat flux density test is high in heating temperature, high in heat flux density and compact in structure so that the requirements of the critical heat flux density test can be met. Besides, temperature parameters are measured and outputted via the thermocouples in real time so that simulation of nuclear fuel heat release can be accurately realized and the requirements of the critical heat flux density test can be effectively met, critical heat flux density of a nuclear fuel rod under different operation conditions can also be measured, and thus the heating rod used for the critical heat flux density test has a great supporting effect for research and development of new type of nuclear fuel assemblies.
Description
Technical field
The present invention relates to a kind of nuclear reactor experimental study field, particularly relating to a kind of critical heat flux density test heating rod for studying nuclear fuel assembly.
Background technology
In convective boiling, mainly contain the critical heat flux density of two types: depart from nucleate boiling and dry up.In the design of pressure water reactor nuclear power unit Steady State Thermal, usually only run into the saturation boiling of subcooled boiling and low quality, therefore departure from nucleate boiling flux is even more important.
Depart from nucleate boiling mechanism model and mainly comprise three types: (a), when heater element wall being formed a large 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 be enough to hinder liquid soak wall time, steam cannot be overflowed and form vapour shell, plug flow channel for liquids, cause heater element wall occur overheated; C (), under high heat flux, the liquid film evaporation speed between vapour block and heater element wall is greater than liquid when soaking wall speed, cause heater element wall abnormal overheated and dry.Because critical heat flux density mechanism and phenomenon thereof are too complicated, usually adopt the method for experimental study, obtain Critical heat flux correlation.According to critical heat flux density test objective and content thereof, by similarity criterion requirement design experiment section, the factor such as Study system pressure, mass velocity, critical point vapor content, structural parameters is on the impact of critical heat flux density.
In critical heat flux density process of the test, critical judgement generally adopts heating element wall temperature to judge, its criterion has two: one to be that heating element wall temperature rises to speed and meets or exceeds certain certain value; Two is that heating element wall temperature meets or exceeds maximum temperature limit value.Critical heat flux density test data analyzer requires to provide in the confidence level of 95%, and the critical heat flux ratio of critical boiling does not occur the probability of at least 95%.
To homogeneous heating test section, general employing local average parametric method process critical heat flux density test data; To non-uniform heating test section, general employing subchannel analysis method process critical heat flux density test data.In nuclear power unit review, critical heat flux density is important restricted thermal-hydraulic parameter, and its size directly affects fail safe and the economy of nuclear power unit.By optimizing fuel assembly structure, improving critical heat flux density, making reactor system produce maximum thermal power, thus ensureing, on the basis that nuclear power unit engineering design is safe and reliable, to improve economy.
In nuclear fuel assembly research and development, critical heat flux density is one of key parameter characterizing fuel assembly thermal-hydraulic performance, the critical heat flux density of fuel assembly can't adopt theoretical method to predict at present, can only be obtained by test, therefore this heating rod just produces, it mainly flows through conductor with electric current and produces heat for principle, the uniform heat simulation nuclear fuel heat release produced by heating rod, thus carries out critical heat flux density experimental study.
US Patent No. 4720624 discloses a kind of heating rod, and this heating rod is non-uniform heating rod, and material is stainless steel, zircaloy or inconel, and the thickness of non-uniform heating rod and resistance change along with excellent length direction, but external diameter is constant.Apply voltage at the two ends of non-uniform heating rod, have electric current and flow through, and then produce heat, simulate core heat release and carry out correlation test research; This non-uniform heating rod can produce the heat of non-uniform Distribution vertically, but it exists certain defect in the technical problems such as overall package, heating-up temperature measurement, external voltage connection.
US Patent No. 4156127 also discloses a kind of electrically heated rod, and this electrically heated rod is made up of three layers of extruding, and nexine is polytetrafluoroethylene light wall pipe, play insulation and with media for heat exchange effect; Intermediate layer is the mixture of carbon and polytetrafluoroethylene, plays conductive exothermal effect; Outermost layer is the thick pipe of polytetrafluoroethylene, rise insulation and with environment heat-blocking action; Draw at heating rod head and the tail two ends the wire be communicated with intermediate layer, when wire applies voltage, have electric current and flow through the intermediate layer being evenly arranged carbonizable substance, and then produce consistent heat generation amount; Therefore this electrically heated rod can produce equally distributed heat vertically, but maximum temperature only can reach 260 DEG C, does not far reach critical heat flux density and tests temperature required; Zone of heating and medium, by teflon insulation and heat conduction, cannot realize rapid, high volume heat exchange; The diameter of electrically heated rod is comparatively large, cannot carry out processing assembling according to nuclear fuel size.
Therefore, need a kind of can precisely realization badly simulate nuclear fuel heat release and effectively can meet the critical heat flux density test heating rod of critical heat flux density experimental study requirement.
Summary of the invention
A kind of can precisely realization is the object of the present invention is to provide to simulate nuclear fuel heat release and effectively can meet the critical heat flux density test heating rod of critical heat flux density test requirements document.
For achieving the above object, the invention provides a kind of critical heat flux density test heating rod, be applicable to simulation nuclear fuel heat release and carry out critical heat flux density test, it comprises nickel rod, heating tube, nickel pipe, copper pipe, ceramic member, copper sheet and thermocouple, the charged equipment connection in upper end and extraneous top of described nickel rod, the lower end of described nickel rod is docked with the upper end of described heating tube and being fixedly connected with of sealing, the lower end of described heating tube is docked with the upper end of described nickel pipe and being fixedly connected with of sealing, the upper end of described copper pipe is docked with the lower end of described nickel pipe and being fixedly connected with of sealing, the charged equipment connection in lower end and extraneous bottom of described copper pipe, described heating tube, nickel pipe and copper pipe dock the barred body formed in hollow structure successively, on the inwall that described ceramic member is attached to the described barred body in hollow structure and around the hot chamber of formation, described copper sheet is be horizontally set at uniformly in described hot chamber and be positioned at heating tube, described thermocouple is unsettled be arranged in described hot chamber and fix by described copper sheet.
Preferably, many described thermocouples are parallel and staggered being distributed in described hot chamber.
Preferably, the rounded structure of the cross-sectional profiles of described barred body.
Preferably, ceramic member in ceramic member and copper pipe in ceramic member, nickel pipe in the heating tube that described ceramic member comprises mutually docking successively, in described heating tube, ceramic member is attached on the inwall of the barred body be positioned at corresponding to described heating tube, in described nickel pipe, ceramic member adheres to and is positioned on the inwall of the barred body corresponding to described nickel pipe, and in described copper pipe, ceramic member adheres to and is positioned on the inwall of the barred body corresponding to described copper pipe.
Compared with prior art, because heating-up temperature of the present invention is high, meet needed for critical heat flux density test, and temperature parameter is measured in real time by thermocouple and exports; Another the present invention can also produce larger density of heat flow rate, there is good thermal conductivity, rapid, high volume heat exchange can be realized, processing assembling can be carried out according to nuclear fuel size, solve the problem that existing heating rod often reliably can not connect high-current supply, reach the object accurately controlling efficient heat generation length; Simultaneously compact conformation of the present invention, size unified and accurately, density of heat flow rate is high, work that can be safe and reliable under high temperature and high pressure condition, therefore the present invention precisely can realize simulation nuclear fuel heat release and can effectively meet critical heat flux density test requirements document, the critical heat flux density of nuclear fuel rod under different operating condition can also be measured, to the research and development of nucleus fuel assembly, there is good supporting role.
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 cutaway view along A-A line in Fig. 1.
Fig. 3 is the cutaway view along B-B line in Fig. 1.
Fig. 4 is the cutaway view along C-C line in Fig. 1.
Embodiment
With reference now to accompanying drawing, describe embodiments of the invention, element numbers similar in accompanying drawing represents similar element.
As shown in Figure 1, critical heat flux density test heating rod 100 of the present invention, critical heat flux density test is carried out for simulating nuclear fuel heat release, it comprises nickel rod 10, heating tube 20, nickel pipe 30, copper pipe 40, ceramic member 50, copper sheet 60 and thermocouple 70, the charged equipment connection in upper end and extraneous top of described nickel rod 10, the lower end of described nickel rod 10 is docked with the upper end of described heating tube 20 and being fixedly connected with of sealing, adopt nickel rod 10 to dock with heating tube 20 fixing, while proof strength, also reduce invalid caloric value; The lower end of described heating tube 20 is docked with the upper end of described nickel pipe 30 and being fixedly connected with of sealing, heating tube 20 produces heat in energising situation, heating tube 20 is existing, it utilizes self-resistance be energized and produce heat, thus realize heating, the upper end of described copper pipe 40 is docked with the lower end of described nickel pipe 30 and being fixedly connected with of sealing, the charged equipment connection in lower end and extraneous bottom of described copper pipe 40, adopt copper pipe 40 and the charged equipment connection in extraneous bottom, while guarantee reliable connection high-current supply, also reduce invalid caloric value; Described heating tube 20, nickel pipe 30 and copper pipe 40 dock the barred body formed in hollow structure successively, on the inwall that described ceramic member 50 is attached to the described barred body in hollow structure and around the hot chamber 51 of formation, namely ceramic member 50 is also in hollow structure, the hollow structure that hot chamber 51 is ceramic member 50 formed, utilize pottery to have excellent insulating properties and thermal insulation, ensure that the accuracy of test data; Described copper sheet 60 is be horizontally set at uniformly in described hot chamber 51 and be positioned at heating tube 20, described thermocouple 70 to be arranged in described hot chamber 51 in unsettled and fix by described copper sheet 60, copper sheet 60 is utilized to have excellent thermal conductivity and mechanicalness, therefore can firmly be fixed by thermocouple 70 by this copper sheet 60 on the one hand, the heat that heating tube 20 can produce by this copper sheet 60 by another side conducts to thermocouple 70 fast; Critical heat flux density test heating rod 100 heating-up temperature of the present invention is high, can meet needed for critical heat flux density test, and is measured in real time by thermocouple 70 by temperature parameter and export; Critical heat flux density test heating rod 100 of the present invention can produce larger density of heat flow rate simultaneously, there is good thermal conductivity, rapid, high volume heat exchange can be realized, therefore the present invention precisely can realize simulation nuclear fuel heat release and can effectively meet critical heat flux density test requirements document, the critical heat flux density of nuclear fuel rod under different operating condition can also be measured, to the research and development of nucleus fuel assembly, there is good supporting role; Separately, measure assigned address temperature in real time by thermocouple 70, effectively avoid critical heat flux density test heating rod 100 of the present invention and burnt.
Continue shown in composition graphs 1, particularly, the lower end of nickel rod 10 and the upper end of heating tube 20 are achieved a butt joint by the mode of weld and being fixedly connected with of sealing, and the two welds formation pad 11; The upper end of the lower end nickel pipe 30 of heating tube 20 is achieved a butt joint by the mode of welding and being fixedly connected with of sealing equally, the two welding forms pad 12, the upper end of same copper pipe 40 and the lower end of nickel pipe 30 also adopt the mode of welding to realize the two and docks and being fixedly connected with of seal, and the two welds formation pad 13; Realize above-mentioned being fixedly connected with between two between device by the mode of welding, both ensure that intensity also reduced contact resistance simultaneously; Below continue composition graphs 2-Fig. 4 to be described in further detail critical heat flux density test heating rod 100 of the present invention:
Preferably, many described thermocouples 70 are distributed in described hot chamber 51 in parallel and staggered; Namely the present invention is provided with the many thermocouples be parallel to each other 70, and every root thermocouple 70 is all arranged on diverse location, thus forms staggered distribution; The execution mode that two thermocouples 70 are set is only gived in the embodiment of Fig. 1-Fig. 4 of the present invention; Those skilled in the art, under the prerequisite of technical scheme provided by the present invention, according to the demand of actual conditions, can implement to arrange the execution mode of the thermocouples such as three, four, five, no longer describe in detail at this without the need to any creativeness.
Shown in composition graphs 2-Fig. 4, preferably, the rounded structure of cross-sectional profiles of described barred body.
Shown in composition graphs 1-Fig. 4, preferably, ceramic member 50c in ceramic member 50b and copper pipe in ceramic member 50a, nickel pipe in the heating tube that described ceramic member 50 comprises mutually docking successively, in described heating tube, ceramic member 50a is attached on the inwall of the barred body be positioned at corresponding to described heating tube 20, in described nickel pipe, ceramic member 50b adheres to and is positioned on the inwall of the barred body corresponding to described nickel pipe 30, and in described copper pipe, ceramic member 50c adheres to and is positioned on the inwall of the barred body corresponding to described copper pipe 40.
Continue composition graphs 1-Fig. 4, because critical heat flux density test heating rod 100 heating-up temperature of the present invention is high, meet needed for critical heat flux density test, and temperature parameter is measured in real time by thermocouple 70 and exports; Another the present invention can also produce larger density of heat flow rate, there is good thermal conductivity, rapid, high volume heat exchange can be realized, processing assembling can be carried out according to nuclear fuel size, solve the problem that existing heating rod often reliably can not connect high-current supply, reach the object accurately controlling efficient heat generation length; Simultaneously compact conformation of the present invention, size unified and accurately, density of heat flow rate is high, work that can be safe and reliable under high temperature and high pressure condition, therefore critical heat flux density test heating rod 100 of the present invention precisely can realize simulation nuclear fuel heat release and can effectively meet critical heat flux density test requirements document, the critical heat flux density of nuclear fuel rod under different operating condition can also be measured, to the research and development of nucleus fuel assembly, there is good supporting role.
Separately, heating tube 20 involved in the present invention and the concrete structure of thermocouple 70 and operation principle, be well known to those of ordinary skill in the art, be no longer described in detail at this.
Above disclosedly be only the preferred embodiments of the present invention, certainly can not limit the interest field of the present invention with this, therefore according to the equivalent variations that the present patent application the scope of the claims is done, still belong to the scope that the present invention is contained.
Claims (4)
1. a critical heat flux density test heating rod, be applicable to simulation nuclear fuel heat release and carry out critical heat flux density test, it is characterized in that: comprise nickel rod, heating tube, nickel pipe, copper pipe, ceramic member, copper sheet and thermocouple, the charged equipment connection in upper end and extraneous top of described nickel rod, the lower end of described nickel rod is docked with the upper end of described heating tube and being fixedly connected with of sealing, the lower end of described heating tube is docked with the upper end of described nickel pipe and being fixedly connected with of sealing, the upper end of described copper pipe is docked with the lower end of described nickel pipe and being fixedly connected with of sealing, the charged equipment connection in lower end and extraneous bottom of described copper pipe, described heating tube, nickel pipe and copper pipe dock the barred body formed in hollow structure successively, on the inwall that described ceramic member is attached to the described barred body in hollow structure and around the hot chamber of formation, described copper sheet is be horizontally set at uniformly in described hot chamber and be positioned at heating tube, described thermocouple is unsettled be arranged in described hot chamber and fix by described copper sheet.
2. critical heat flux density test heating rod as claimed in claim 1, is characterized in that: many described thermocouples are parallel and staggered being distributed in described hot chamber.
3. critical heat flux density test heating rod as claimed in claim 1, is characterized in that: the rounded structure of cross-sectional profiles of described barred body.
4. critical heat flux density test heating rod as claimed in claim 1, it is characterized in that: ceramic member in ceramic member and copper pipe in ceramic member, nickel pipe in the heating tube that described ceramic member comprises mutually docking successively, in described heating tube, ceramic member is attached on the inwall of the barred body be positioned at corresponding to described heating tube, in described nickel pipe, ceramic member adheres to and is positioned on the inwall of the barred body corresponding to described nickel pipe, and in described copper pipe, ceramic member adheres to and 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 true CN105007641A (en) | 2015-10-28 |
| CN105007641B CN105007641B (en) | 2016-09-28 |
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| WO (1) | WO2017016136A1 (en) |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106158057A (en) * | 2016-08-17 | 2016-11-23 | 中国核电工程有限公司 | The analog of Spent Fuel Pool |
| WO2017016136A1 (en) * | 2015-07-29 | 2017-02-02 | 中广核研究院有限公司 | Heating rod for critical heat flux test |
| 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 |
| CN114121319A (en) * | 2021-11-23 | 2022-03-01 | 西安交通大学 | Single-rod boiling critical test device and method for nuclear reactor under six-degree-of-freedom motion condition |
| CN114916101A (en) * | 2022-05-12 | 2022-08-16 | 西北核技术研究所 | Heating rod and heating rod bundle device |
| CN115223738A (en) * | 2022-07-15 | 2022-10-21 | 西安交通大学 | Experiment segment for measuring temperature and potential of cladding and measuring method |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2017016136A1 (en) * | 2015-07-29 | 2017-02-02 | 中广核研究院有限公司 | Heating rod for critical heat flux test |
| CN106158057A (en) * | 2016-08-17 | 2016-11-23 | 中国核电工程有限公司 | The analog of Spent Fuel Pool |
| 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 |
| CN114121319A (en) * | 2021-11-23 | 2022-03-01 | 西安交通大学 | Single-rod boiling critical test device and method for nuclear reactor under six-degree-of-freedom motion condition |
| 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 |
| CN114916101A (en) * | 2022-05-12 | 2022-08-16 | 西北核技术研究所 | Heating rod and heating rod bundle device |
| CN114916101B (en) * | 2022-05-12 | 2024-06-21 | 西北核技术研究所 | Heating rod and heating rod bundle device |
| CN115223738A (en) * | 2022-07-15 | 2022-10-21 | 西安交通大学 | Experiment segment for measuring temperature and potential of cladding and measuring method |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| WO2017016136A1 (en) | 2017-02-02 |
| CN105007641B (en) | 2016-09-28 |
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