CN114113211A - Natural cooling flow heat transfer characteristic research experiment system and method - Google Patents
Natural cooling flow heat transfer characteristic research experiment system and method Download PDFInfo
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- 238000001816 cooling Methods 0.000 title claims abstract description 27
- 239000000446 fuel Substances 0.000 claims abstract description 58
- 230000008569 process Effects 0.000 claims abstract description 18
- 238000010438 heat treatment Methods 0.000 claims description 95
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 22
- 238000012795 verification Methods 0.000 claims description 12
- 238000009529 body temperature measurement Methods 0.000 claims description 11
- 238000005259 measurement Methods 0.000 claims description 9
- 239000003758 nuclear fuel Substances 0.000 claims description 9
- 239000000523 sample Substances 0.000 claims description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 7
- 238000005485 electric heating Methods 0.000 claims description 6
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- 239000012530 fluid Substances 0.000 claims description 4
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- 229910052751 metal Inorganic materials 0.000 description 4
- 239000002184 metal Substances 0.000 description 4
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- 239000000498 cooling water Substances 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
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- 230000003647 oxidation Effects 0.000 description 2
- 238000007254 oxidation reaction Methods 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 230000001360 synchronised effect Effects 0.000 description 2
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000006399 behavior Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000004939 coking Methods 0.000 description 1
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Abstract
The invention provides a natural cooling flow heat transfer characteristic research experiment system and a method, relating to the technical field of experiment devices, wherein the method comprises the following steps: the device comprises an experiment body, a rectangular channel, a related supporting structure, a direct-current power supply, a measuring instrument and a data acquisition system; the related supporting device is used for supporting the whole experiment body; the experiment body is connected with a direct current power supply, the rectangular channel is connected with a measuring instrument, and the data acquisition system is responsible for acquiring relevant data of the measuring instrument; the outer wall of the rectangular channel is wrapped with a heat-insulating layer. The invention can finely monitor the temperature distribution in the fuel assembly of the nuclear reactor, explores the problem of transient characteristics of the fuel assembly in the temperature rise process, and has the advantages of high precision of experimental data, good safety, convenient operation and the like.
Description
Technical Field
The invention relates to the technical field of experimental devices, in particular to a natural cooling flow heat transfer characteristic research experimental system of a nuclear reactor fuel assembly in an air environment, and particularly relates to a natural cooling flow heat transfer characteristic research experimental system and a method.
Background
After the accidents of the three-li island and the chernobyl accidents, the natural circulation system is gradually widely used in the nuclear industry because it can automatically discharge heat without inputting energy from the outside. During the past decades, a great deal of experimentation and numerical research has been conducted on the natural circulation system. At present, a great deal of experimental research is carried out on natural convection behaviors in a fuel assembly of a nuclear reactor, the research mainly focuses on the local steady-state thermal hydraulic characteristics of fuel bundles and positioning grids, and relatively few researches on the operation characteristics of the whole natural circulation system are carried out. The complete loss of cooling water from the nuclear reactor spent fuel pool is the final stage of four accident stages in the spent fuel pool water loss and cold loss research report issued by OECD NEA. If the water loss speed of the spent fuel pool is too high, the accident can quickly enter the stage of complete water loss. At this time, the cooling water in the spent fuel pool is completely lost, and the spent fuel assembly is completely exposed to the air environment. Through the ventilation system of the spent fuel pool, cold air is continuously input into the spent fuel pool plant. This cool air is drawn in from the bottom of the spent fuel and is gradually heated by the spent fuel assemblies during the upward flow.
Because the natural circulation flow is less, and the external environment space is huge, hot-air can be cooled down rapidly after entering the external environment after flowing out from the top of the spent fuel. Therefore, the hot air inside the spent fuel and the cold air outside form strong natural air circulation flow. Due to the large number of spent fuel assemblies in the spent fuel pool and the close arrangement of the spent fuel assemblies in the storage grid, the single spent fuel assembly in the central area has a boundary condition of near thermal insulation at the periphery. At this time, the heat generated by the spent fuel assembly can be brought out only by the heat radiation of the end part and the natural circulation flow of air. Due to the limited heat removal capability of both heat transfer modes, the temperature of the spent fuel assembly will gradually rise. Finally, the zirconium alloy and oxygen are subjected to a strong oxidation-reduction reaction at high temperature, a large amount of heat is released, and the spent fuel assembly is burnt to cause radioactivity leakage. Currently, there is a need for advanced experimental systems to supplement the thermodynamic and hydraulic properties of nuclear reactor fuel assemblies that produce natural circulation in an air environment.
The utility model discloses a utility model patent with publication number CN209280318U, which discloses a research system for heat transfer characteristics of an adjustable combustion chamber sample piece, comprising a two-dimensional adjustable combustion chamber sample piece, a constant volume combustion bomb, a synchronous control and transient temperature acquisition subsystem, a fuel supply subsystem, a high-speed camera shooting subsystem, an air intake and exhaust subsystem and a cooling subsystem; the two-dimensional adjustable combustion chamber sample piece is arranged in the constant volume combustion bomb and used for simulating different top dead center position states of the piston; the constant-volume combustion bomb main body is in a cylindrical shape and is used for simulating a high-temperature and high-pressure environment in a combustion chamber of a diesel engine; the synchronous control and transient temperature acquisition subsystem has the functions of oil injection time control, image shooting control and transient temperature acquisition.
The invention patent with the publication number of CN109509564A discloses a nuclear reactor engineering-level double-layer molten pool heat transfer characteristic test device, which comprises a test section, a cover plate, an electric heating element, a partition plate and a temperature measuring assembly, and the test device can be used for researching the natural convection heat transfer characteristic of a double-layer configuration molten pool (an upper metal layer and a lower oxidation molten pool) under the nuclear reactor engineering level, obtaining the upward and downward heat transfer characteristics of the oxidation molten pool and the heat transfer characteristic of the metal layer to the side wall under different working conditions, analyzing the influence of the thickness and height of the metal layer on the heat transfer characteristic of the double-layer molten pool, and providing an important basis for the research of the hot coking effect of the metal layer.
Disclosure of Invention
Aiming at the defects in the prior art, the invention provides a natural cooling flow heat transfer characteristic research experiment system and a method.
According to the natural cooling flow heat transfer characteristic research experiment system and the method provided by the invention, the scheme is as follows:
in a first aspect, a natural cooling flow heat transfer characteristic research experiment system is provided, the system comprising: the device comprises an experiment body, a rectangular channel, a related supporting structure, a direct-current power supply, a measuring instrument and a data acquisition system;
the related supporting device is used for supporting the whole experiment body;
the experiment body is connected with a direct current power supply, the rectangular channel is connected with a measuring instrument, and the data acquisition system is responsible for acquiring relevant data of the measuring instrument;
the outer wall of the rectangular channel is wrapped with a heat insulation layer.
Preferably, the system further comprises: an inlet channel; in the experimental process, determining the air flow rate at the inlet by adopting a method of reducing the air flow cross section at the flow measurement part, increasing the air flow rate at the measurement part, supplementing and connecting a divergent section at the lower end of the rectangular inlet channel, and connecting a DN50 circular pipe at the inlet of the divergent section for installing an air flow measurement device;
the side surface of the circular tube is provided with a hot wire anemometer for measuring the inlet air flow rate;
the hot wire anemometer is fixed on the sliding guide rail, and the position of the measuring point is adjusted through a control system of the sliding guide rail to obtain radial flow velocity distribution data in the circular tube.
Preferably, the system adopts a test section heating mode, and specifically comprises: the experiment body is the full-scale fuel assembly of pressurized water reactor, contains many nuclear fuel rods, changes many fuel rods of fuel assembly into the electrical heating rod of the same external diameter, and the heating length of heating rod is the same with former fuel rod active area length, and in the heating section interval, the power evenly distributed of each position on the heating rod.
Preferably, the decay heat of the spent fuel is simulated by adjusting the power of the electric heating rod in the experimental process.
Preferably, the experimental system further comprises a cluster wall thermocouple, namely, a thermocouple for measuring the wall temperature of the heating rod is arranged on part of the heating rod.
Preferably, the thermocouple installation method comprises: the surface of the heating rod is axially provided with a plurality of micro grooves, the thermocouple including a compensation lead thereof is embedded into the micro grooves, the measuring end of the thermocouple is fixed at the designed temperature measuring height, and finally the notch is packaged and welded, and the outer wall of the heating rod is ensured to be smooth and neat.
Preferably, in order to verify symmetry in the experimental process, a symmetry verification heating rod is specially arranged, the arrangement position of a thermocouple of the symmetry verification heating rod is the same as that of the radial temperature measurement group, temperature data on the verification heating rod and other heating rods are compared, and symmetry of a temperature field in the fuel assembly is verified.
Preferably, the system further comprises a fuel assembly sub-channel fluid temperature measuring thermocouple arranged: a plurality of small holes are formed in the wall surface of the rectangular channel, a plurality of air temperature probe type thermocouples are respectively fixed on the sliding guide rail capable of sliding, the temperature of air in the channel is measured through the small holes, the air temperature at different radial positions is measured by controlling the sliding guide rail, and the air temperature probe type thermocouples and the wall temperature plane of the rod bundle form a complete temperature measuring plane.
Preferably, the system further comprises a rectangular channel outer wall thermocouple: fixing a bare wire N-type thermocouple on the outer wall surface of the rectangular channel, and measuring the temperature of the rectangular channel;
arranging a plurality of N-type thermocouples at the height of the fuel assembly supporting bottom plate and the height of an outlet at the upper part of the rectangular channel respectively, and measuring the local environment temperature;
a hygrometer is arranged at the height of the fuel assembly supporting bottom plate, and the relative humidity of the local environment is measured.
In a second aspect, a natural cooling flow heat transfer characteristic research experiment method is provided, the method comprising:
step S1: checking whether the experiment body, the direct-current power supply, each measuring instrument and the data acquisition system can work normally or not;
step S2: starting a direct current power supply, adjusting the heating power to a designed working condition, and starting heating;
step S3: continuously acquiring data in the heating process;
step S4: continuously heating for 24 hours, and immediately stopping heating if a temperature measuring point exceeds 400 ℃ in the period;
step S5: and naturally cooling the experiment body to room temperature, and starting the next power working condition until all the design working conditions are completed.
Compared with the prior art, the invention has the following beneficial effects:
1. the rod bundle temperature measuring points in the experimental system are densely arranged, so that the internal temperature distribution of the fuel assembly can be clearly and completely provided, and a solid foundation is provided for analyzing the heat transfer mechanism in the fuel assembly;
2. the invention can collect the data of the internal temperature and the air flow of the fuel assembly in the temperature rise process, and can basically know the transient characteristic of the fuel assembly in the temperature rise process;
3. the invention can monitor the temperature distribution in the fuel assembly of the nuclear reactor finely, explore the problem of transient characteristic of the fuel assembly in the temperature rise process, have high precision of experimental data, good security, easy to operate, etc.;
drawings
Other features, objects and advantages of the invention will become more apparent upon reading of the detailed description of non-limiting embodiments with reference to the following drawings:
FIG. 1 is a schematic view of an experimental apparatus for natural circulation in an air environment;
FIG. 2 is a DC power supply and heating rod;
FIG. 3 shows the arrangement of the thermometric heating rods.
Detailed Description
The present invention will be described in detail with reference to specific examples. The following examples will assist those skilled in the art in further understanding the invention, but are not intended to limit the invention in any way. It should be noted that it would be obvious to those skilled in the art that various changes and modifications can be made without departing from the spirit of the invention. All falling within the scope of the present invention.
The embodiment of the invention provides a natural cooling flow heat transfer characteristic research experiment system, which comprises a heat transfer characteristic and a transient characteristic in a temperature rise process. The rod bundle temperature measuring points in the experimental system are densely arranged, so that the internal temperature distribution of the fuel assembly can be clearly and completely provided, and a solid foundation is provided for analyzing the heat transfer mechanism in the fuel assembly. Meanwhile, the system can collect data of the internal temperature and the air flow of the fuel assembly in the temperature rise process, and can basically know the transient characteristics of the fuel assembly in the temperature rise process.
The experimental system for researching the thermal hydraulic characteristics of the fuel assembly of the nuclear reactor generating natural circulation flow in the air environment is mainly used for exploring: 1. temperature distribution within the nuclear reactor fuel assembly after reaching a thermal equilibrium steady state; 2. transient changes in the natural circulation characteristics of the nuclear reactor fuel assembly during the temperature ramp-up process.
Referring to fig. 1, the system includes the following components: experiment body, rectangle passageway, relevant bearing structure, DC power supply, measuring instrument and data acquisition system.
Particularly, the related supporting device is used for supporting the whole experiment body; the experiment body is connected with a direct current power supply, the rectangular channel is connected with a measuring instrument, and the data acquisition system is responsible for acquiring relevant data of the measuring instrument; the outer wall of the rectangular channel is wrapped with a heat-insulating layer.
The experimental system further comprises: an inlet channel; in the experimental process, determining the air flow rate at the inlet by adopting a method of reducing the air flow cross section at the flow measurement part, increasing the air flow rate at the measurement part, supplementing and connecting a divergent section at the lower end of the rectangular inlet channel, and connecting a DN50 circular pipe at the inlet of the divergent section for installing an air flow measurement device; the side surface of the circular tube is provided with a hot wire anemometer for measuring the inlet air flow rate; the hot wire anemometer is fixed on the sliding guide rail, and the position of the measuring point is adjusted through a control system of the sliding guide rail to obtain radial flow velocity distribution data in the circular tube.
Adopt test section heating method in the system, specifically include: the experiment body is the full-scale fuel assembly of pressurized water reactor, contains many nuclear fuel rods, changes many fuel rods of fuel assembly into the electrical heating rod of the same external diameter, and the heating length of heating rod is the same with former fuel rod active area length, and in the heating section interval, the power evenly distributed of each position on the heating rod.
The decay heat of the spent fuel is simulated by adjusting the power of the electric heating rod in the experimental process.
The experimental system also comprises a thermocouple arranged on the wall surface of the rod cluster, namely a thermocouple for measuring the wall surface temperature of the heating rod is arranged on part of the heating rod. The installation method of the thermocouple comprises the following steps: the surface of the heating rod is axially provided with a plurality of micro grooves, the thermocouple including a compensation lead thereof is embedded into the micro grooves, the measuring end of the thermocouple is fixed at the designed temperature measuring height, and finally the notch is packaged and welded, and the outer wall of the heating rod is ensured to be smooth and neat.
In order to verify the symmetry in the experimental process, a symmetry verification heating rod is specially arranged, the arrangement position of a thermocouple of the symmetry verification heating rod is the same as that of a radial temperature measurement group, temperature data on the verification heating rod and other heating rods are compared, and the symmetry of a temperature field in the fuel assembly is verified.
The system further includes arranging a fuel assembly sub-channel fluid temperature measuring thermocouple: a plurality of small holes are formed in the wall surface of the rectangular channel, a plurality of air temperature probe type thermocouples are respectively fixed on the sliding guide rail capable of sliding, the temperature of air in the channel is measured through the small holes, the air temperature at different radial positions is measured by controlling the sliding guide rail, and the air temperature probe type thermocouples and the wall temperature plane of the rod bundle form a complete temperature measuring plane.
The system also includes a rectangular channel outer wall thermocouple: fixing a bare wire N-type thermocouple on the outer wall surface of the rectangular channel, and measuring the temperature of the rectangular channel; arranging a plurality of N-type thermocouples at the height of the fuel assembly supporting bottom plate and the height of an outlet at the upper part of the rectangular channel respectively, and measuring the local environment temperature; a hygrometer is arranged at the height of the fuel assembly supporting bottom plate, and the relative humidity of the local environment is measured.
The heating power of the fuel assembly is adjusted by adjusting the power of the direct current power supply, the inlet flow rate is measured by a hot wire anemometer, and the temperature distribution of the fuel assembly is measured by a thermocouple.
The invention also provides an experimental method for researching the heat transfer characteristic of the natural cooling flow, which comprises the following experimental steps:
step S1: checking whether the experiment body, the direct-current power supply, each measuring instrument and the data acquisition system can work normally or not;
step S2: starting a direct current power supply, adjusting the heating power to a designed working condition, and starting heating;
step S3: continuously acquiring data in the heating process;
step S4: continuously heating for 24 hours, and if a temperature measuring point exceeds 400 ℃ in the period, immediately stopping heating to protect the fuel assembly;
step S5: and naturally cooling the experiment body to room temperature, and starting the next power working condition until all the design working conditions are completed.
Next, the present invention will be described in more detail.
In the experiment, a continuous data acquisition mode is adopted, so that the acquired data can be used for analyzing the heat transfer characteristics under the heat balance steady state and can also be used for analyzing the transient characteristics before the heat balance steady state. The natural circulation characteristics of fuel assemblies with different decay heat are explored by adjusting the power of an external power supply.
Inlet air flow rate determination: considering that the air flow rate is extremely small (<0.1m/s) under the natural circulation working condition and is close to the sensitivity limit of the measuring instrument, the method of reducing the air flow cross section at the flow measuring position is adopted, the air flow rate at the measuring position is improved, and the air flow measuring precision is further improved. The lower end of the rectangular inlet channel is additionally connected with a divergent inlet channel, and the divergent inlet is further connected with a DN50 round tube with the length of 40cm and used for installing an air flow measuring device. The side of the round tube is provided with a hot wire anemometer with small pressure loss for measuring the inlet air flow rate. The hot wire anemometer is fixed on the sliding guide rail, and the position of the measuring point can be adjusted through a control system of the sliding guide rail to obtain radial flow velocity distribution data in the circular tube.
The heating method of the experimental section comprises the following steps: the experimental body is a pressurized water reactor full-size fuel assembly and contains 264 nuclear fuel rods. Referring to fig. 2, in this experiment, 264 fuel rods of the fuel assembly were replaced with electric heating rods having the same outer diameter, and the heating length (3.658m) of the heating rods was the same as the length of the raw fuel rod active region. And in the heating section interval, the power of each position on the heating rod is uniformly distributed.
The decay heat of the spent fuel can be simulated by adjusting the power of the electric heating rod in the experimental process. The maximum voltage of the heating direct-current power supply which can be used by the experimental system at present is 25V, the maximum current is 1000A, and the maximum heating power is 25 kW. Referring to fig. 1, the dc power supply is provided with a wiring cabinet, each heating rod has a separate power line, and each power line is connected to the wiring cabinet. The resistance deviation of the 264 heating rods used in the experiment was less than 0.5%, and therefore, it can be considered that the power of each heating rod was the same during heating.
Bundle wall thermocouple placement: and thermocouples for measuring the wall temperature of the heating rods are arranged on part of the heating rods. The installation method of the thermocouple comprises the following steps: firstly, a plurality of micro grooves are axially formed in the surface of a heating rod, then a thermocouple including a compensation lead thereof is embedded into the micro grooves, the measuring end of the thermocouple is fixed at a designed temperature measuring height, and finally, a notch is packaged and welded, and the outer wall of the heating rod is ensured to be smooth and neat. Each heating rod is provided with 8 thermocouples which are uniformly distributed along the circumferential direction. The thermocouple wire is led out from the top of the heating rod along the micro-groove and then is connected to the data acquisition system through the compensation wire. Of all 264 heating rods, 16 heating rods including thermocouples were mounted, and 128 thermocouples were mounted. The mounting positions and numbers of the 16 thermometric heating rods are shown in FIG. 3. The thermocouple site height H on each heating rod is shown in table 1 below. The 16 temperature measuring heating rods are divided into three groups: 5 axial temperature measurement groups (number 1-5), 10 radial temperature measurement groups (number 6-15) and 1 symmetry verification group (number 16). The axial temperature measurement group comprises 5 temperature measurement heating rods.
TABLE 1 Cluster wall temperature thermocouple arrangement
The axial temperature measurement group is used for obtaining the axial distribution of the wall temperature of the heating rod at the center of the fuel assembly. Due to the symmetry, the positions of the 5 heating rods of the axial thermometry group are equivalent. The total height of the fuel assembly is provided with 40 temperature measuring points with different heights, and each temperature measuring rod shares 8 temperature measuring points. The 40 temperature measuring points of 5 heating rods are equivalent to arranging 40 temperature measuring points on 1 heating rod.
The radial group comprises 10 temperature measuring heating rods with the same temperature measuring arrangement height, and 8 temperature measuring points of each rod are evenly distributed in the axial direction. Therefore, 10 temperature measuring points from different radial temperature measuring group heating rods and 1 temperature measuring point from an axial temperature measuring group heating rod are included in the height of the 8 temperature measuring points. The 11 measuring points have the same height and different radial positions, and form a radial temperature measuring plane. The height of the 8 measuring points becomes 8 temperature measuring planes for measuring the radial temperature change on the height. Because the radial temperature change is large at the position close to the outer rectangular channel, the heating rods of the radial temperature measurement group are mainly distributed at the periphery of the fuel assembly.
In order to verify the symmetry, a symmetry verification heating rod (number 16 in fig. 3) is specially arranged, and the arrangement position of a thermocouple of the symmetry verification heating rod is the same as that of the radial temperature measurement group. The symmetry of the temperature field within the fuel assembly can be verified by comparing the temperature data on the heater rods and the No. 12 heater rod.
Fuel assembly sub-channel fluid temperature measurement thermocouple arrangement: the wall surface of the rectangular channel is provided with small holes, thermocouples are fixed on the guide rails capable of sliding, the temperature of air in the channel is measured through the small holes, eight temperature measuring guide rails are arranged in the axial direction, each guide rail is provided with 3 thermocouples, the height of each thermocouple is consistent with that of each 8 temperature measuring planes, the air temperature at different radial positions can be measured through controlling the guide rails, and the air temperature and the wall temperature planes of the rod bundles form a complete temperature measuring plane.
Arranging thermocouples on the outer wall of the rectangular channel: and welding a bare-wire N-type thermocouple on the outer wall surface of the rectangular channel to measure the temperature of the rectangular channel as one of boundary conditions for analyzing the temperature characteristics of the fuel assembly. On the basis of the fuel assembly supporting bottom plate, 10 temperature measuring points are arranged on five heights of 0.5m, 1.5m, 2.5m, 3.5m and 4.5m, and two measuring points are arranged on each height. The two measuring points are respectively positioned at the axial line position (namely, the position near the heating rod No. 10 in the figure 3) and the edge position (namely, the position near the heating rod No. 6 in the figure 3) in the rectangular channel plate. The temperature data of other heights can be interpolated from the temperature values of these 5 heights.
And (3) the temperature and humidity of the environment: two N-type thermocouples are respectively arranged at the height of the fuel assembly supporting bottom plate and the height of an outlet at the upper part of the rectangular channel and are used for measuring the local environment temperature. A hygrometer is arranged at the level of the fuel assembly support floor for measuring the local ambient relative humidity.
The embodiment of the invention provides a natural cooling flow heat transfer characteristic research experiment system and a method, which can be used for finely monitoring the temperature distribution in a nuclear reactor fuel assembly and researching the problem of transient characteristics of the fuel assembly in the temperature rise process, and have the advantages of high accuracy of experiment data, good safety, convenience in operation and the like.
Those skilled in the art will appreciate that, in addition to implementing the system and its various devices, modules, units provided by the present invention as pure computer readable program code, the system and its various devices, modules, units provided by the present invention can be fully implemented by logically programming method steps in the form of logic gates, switches, application specific integrated circuits, programmable logic controllers, embedded microcontrollers and the like. Therefore, the system and various devices, modules and units thereof provided by the invention can be regarded as a hardware component, and the devices, modules and units included in the system for realizing various functions can also be regarded as structures in the hardware component; means, modules, units for performing the various functions may also be regarded as structures within both software modules and hardware components for performing the method.
The foregoing description of specific embodiments of the present invention has been presented. It is to be understood that the present invention is not limited to the specific embodiments described above, and that various changes or modifications may be made by one skilled in the art within the scope of the appended claims without departing from the spirit of the invention. The embodiments and features of the embodiments of the present application may be combined with each other arbitrarily without conflict.
Claims (10)
1. A natural cooling flow heat transfer characteristic research experiment system is characterized by comprising: the device comprises an experiment body, a rectangular channel, a related supporting structure, a direct-current power supply, a measuring instrument and a data acquisition system;
the related supporting device is used for supporting the whole experiment body;
the experiment body is connected with a direct current power supply, the rectangular channel is connected with a measuring instrument, and the data acquisition system is responsible for acquiring relevant data of the measuring instrument;
the outer wall of the rectangular channel is wrapped with a heat insulation layer.
2. The natural cooling flow heat transfer property research experiment system of claim 1, wherein the system further comprises: an inlet channel; in the experimental process, determining the air flow rate at the inlet by adopting a method of reducing the air flow cross section at the flow measurement part, increasing the air flow rate at the measurement part, supplementing and connecting a divergent section at the lower end of the rectangular inlet channel, and connecting a DN50 circular pipe at the inlet of the divergent section for installing an air flow measurement device;
the side surface of the circular tube is provided with a hot wire anemometer for measuring the inlet air flow rate;
the hot wire anemometer is fixed on the sliding guide rail, and the position of the measuring point is adjusted through a control system of the sliding guide rail to obtain radial flow velocity distribution data in the circular tube.
3. The natural cooling flow heat transfer characteristic research experiment system according to claim 1, wherein a test section heating mode is adopted in the system, and the system specifically comprises: the experiment body is the full-scale fuel assembly of pressurized water reactor, contains many nuclear fuel rods, changes many fuel rods of fuel assembly into the electrical heating rod of the same external diameter, and the heating length of heating rod is the same with former fuel rod active area length, and in the heating section interval, the power evenly distributed of each position on the heating rod.
4. The natural cooling flow heat transfer characteristic research experiment system according to claim 3, wherein the decay heat of the spent fuel is simulated by adjusting the power of the electric heating rod during the experiment.
5. The natural cooling flow heat transfer characteristic research experiment system according to claim 1, wherein the experiment system further comprises a cluster wall thermocouple, namely, a thermocouple for measuring the wall temperature of the heating rod is installed on part of the heating rods.
6. The natural cooling flow heat transfer characteristic research experiment system according to claim 5, wherein the installation method of the thermocouple comprises the following steps: the surface of the heating rod is axially provided with a plurality of micro grooves, the thermocouple including a compensation lead thereof is embedded into the micro grooves, the measuring end of the thermocouple is fixed at the designed temperature measuring height, and finally the notch is packaged and welded, and the outer wall of the heating rod is ensured to be smooth and neat.
7. The natural cooling flow heat transfer characteristic research experiment system according to claim 1, wherein a symmetry verification heating rod is specially arranged for verifying symmetry in the experiment process, the thermocouple arrangement position of the symmetry verification heating rod is the same as that of the radial temperature measurement group, and the symmetry of the temperature field in the fuel assembly is verified by comparing the temperature data of the verification heating rod and the temperature data of other heating rods.
8. The natural cooling flow heat transfer property research experiment system of claim 1, further comprising a fuel assembly sub-channel fluid temperature measuring thermocouple arranged: a plurality of small holes are formed in the wall surface of the rectangular channel, a plurality of air temperature probe type thermocouples are respectively fixed on the sliding guide rail capable of sliding, the temperature of air in the channel is measured through the small holes, the air temperature at different radial positions is measured by controlling the sliding guide rail, and the air temperature probe type thermocouples and the wall temperature plane of the rod bundle form a complete temperature measuring plane.
9. The natural cooling flow heat transfer property research experiment system of claim 1, further comprising arranging rectangular channel outer wall thermocouples: fixing a bare wire N-type thermocouple on the outer wall surface of the rectangular channel, and measuring the temperature of the rectangular channel;
arranging a plurality of N-type thermocouples at the height of the fuel assembly supporting bottom plate and the height of an outlet at the upper part of the rectangular channel respectively, and measuring the local environment temperature;
a hygrometer is arranged at the height of the fuel assembly supporting bottom plate, and the relative humidity of the local environment is measured.
10. A natural cooling flow heat transfer characteristic research experiment method, based on the natural cooling flow heat transfer characteristic research experiment system of claim 1, comprising:
step S1: checking whether the experiment body, the direct-current power supply, each measuring instrument and the data acquisition system can work normally or not;
step S2: starting a direct current power supply, adjusting the heating power to a designed working condition, and starting heating;
step S3: continuously acquiring data in the heating process;
step S4: continuously heating for 24 hours, and immediately stopping heating if a temperature measuring point exceeds 400 ℃ in the period;
step S5: and naturally cooling the experiment body to room temperature, and starting the next power working condition until all the design working conditions are completed.
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