CN113188598A - Experimental system for researching retention characteristics of radioactive substances in steam generator - Google Patents
Experimental system for researching retention characteristics of radioactive substances in steam generator Download PDFInfo
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- CN113188598A CN113188598A CN202110469709.6A CN202110469709A CN113188598A CN 113188598 A CN113188598 A CN 113188598A CN 202110469709 A CN202110469709 A CN 202110469709A CN 113188598 A CN113188598 A CN 113188598A
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- 239000000941 radioactive substance Substances 0.000 title claims abstract description 29
- 230000014759 maintenance of location Effects 0.000 title claims abstract description 23
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 72
- 239000007791 liquid phase Substances 0.000 claims abstract description 63
- 238000004088 simulation Methods 0.000 claims abstract description 48
- 239000007788 liquid Substances 0.000 claims abstract description 47
- 238000005485 electric heating Methods 0.000 claims abstract description 32
- 230000002285 radioactive effect Effects 0.000 claims abstract description 23
- 239000012071 phase Substances 0.000 claims abstract description 18
- 238000002474 experimental method Methods 0.000 claims abstract description 17
- 238000010438 heat treatment Methods 0.000 claims description 44
- 230000001105 regulatory effect Effects 0.000 claims description 9
- 239000012857 radioactive material Substances 0.000 claims description 7
- 238000001704 evaporation Methods 0.000 claims description 5
- 230000008020 evaporation Effects 0.000 claims description 5
- 238000013461 design Methods 0.000 abstract description 20
- 238000000034 method Methods 0.000 abstract description 17
- 230000008569 process Effects 0.000 abstract description 16
- 238000012546 transfer Methods 0.000 abstract description 14
- 238000005259 measurement Methods 0.000 abstract description 10
- 238000011160 research Methods 0.000 abstract description 5
- 238000009835 boiling Methods 0.000 abstract description 4
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- 238000013508 migration Methods 0.000 description 7
- 230000005012 migration Effects 0.000 description 7
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- 229910001220 stainless steel Inorganic materials 0.000 description 5
- 239000010935 stainless steel Substances 0.000 description 5
- 230000008859 change Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 230000000717 retained effect Effects 0.000 description 4
- 238000005070 sampling Methods 0.000 description 4
- 238000005406 washing Methods 0.000 description 4
- 230000003020 moisturizing effect Effects 0.000 description 3
- 238000012544 monitoring process Methods 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000007599 discharging Methods 0.000 description 2
- 238000001914 filtration Methods 0.000 description 2
- 230000017525 heat dissipation Effects 0.000 description 2
- 239000012774 insulation material Substances 0.000 description 2
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- 238000003904 radioactive pollution Methods 0.000 description 2
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- 230000000087 stabilizing effect Effects 0.000 description 2
- 239000002351 wastewater Substances 0.000 description 2
- 239000011260 aqueous acid Substances 0.000 description 1
- 230000001174 ascending effect Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000005587 bubbling Effects 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 239000008367 deionised water Substances 0.000 description 1
- 229910021641 deionized water Inorganic materials 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000003566 sealing material Substances 0.000 description 1
- 239000013049 sediment Substances 0.000 description 1
- 238000005507 spraying Methods 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
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- 230000005514 two-phase flow Effects 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01D—MEASURING NOT SPECIALLY ADAPTED FOR A SPECIFIC VARIABLE; ARRANGEMENTS FOR MEASURING TWO OR MORE VARIABLES NOT COVERED IN A SINGLE OTHER SUBCLASS; TARIFF METERING APPARATUS; MEASURING OR TESTING NOT OTHERWISE PROVIDED FOR
- G01D21/00—Measuring or testing not otherwise provided for
- G01D21/02—Measuring two or more variables by means not covered by a single other subclass
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention provides an experimental system for researching retention characteristics of radioactive substances in a steam generator, which mainly comprises a secondary side liquid phase environment simulation system, a secondary side water supply system, a gas and radioactive simulant distribution system and a measurement system, wherein the secondary side liquid phase environment simulation system is used as a pressure-bearing boundary and a steam generator simulator, a tube bundle structural type electric heating device is combined to simulate a boiling heat exchange environment in a heat transfer tube bundle area under a working state, meanwhile, the gas-liquid two-phase environment with extremely high gas content and apparent gas velocity in the steam generator is simulated through the variable cross-section structural design, the system can be suitable for wider experimental conditions, the research on retention characteristics of radioactive substances in the steam generator under different accident process conditions can be realized, meanwhile, by adopting the PID control design, the complexity of experiment operation and control is reduced, and the stability of experiment working conditions is improved.
Description
Technical Field
The invention relates to an experimental system for researching retention characteristics of radioactive substances in a steam generator of a nuclear power plant, which can simulate gas-phase and liquid-phase environments under different accident process conditions and is mainly used for researching migration and retention phenomena of the radioactive substances in the steam generator when a serious accident occurs in the nuclear power plant.
Background
With the continuous development of society, the demand of various industries on energy is increasingly serious, and nuclear power is widely applied as a clean and efficient energy source in the world. However, because it has great danger and needs strict danger assessment for serious accidents caused by its runaway, and the most serious threat is radioactive pollution caused by the leakage of radioactive substances, the research on the migration characteristics of radioactive substances in serious accident conditions of nuclear power plants is the focus of the current research. Pool filtration is an important physical phenomenon involved in the serious accident process of a reactor and exists in various reactor facilities, wherein the most typical phenomenon is steam generator heat transfer pipe break accident (SGTR). In the process, radioactive substances generated due to reasons such as reactor core meltdown enter the liquid phase along with non-condensable gas or water vapor, a part of the radioactive substances are retained in the liquid phase, and a part of the radioactive substances enter the gas space, so that the released radioactive substances can cause the risk of radioactive pollution to the whole two-circuit system or even a plant, and the retention characteristic of the radioactive substances in the liquid phase can generate important influence on the radioactive concentration in the containment at the later stage of an accident, therefore, the retention efficiency of the radioactive substances in the liquid phase is accurately mastered, and the method has important significance for reasonably evaluating the concentration level of the radioactive substances in the containment under the working condition of the accident and formulating corresponding accident relieving measures.
However, the phenomenon of Pool washing and filtering varies according to the different accident processes, and the document "Technical Bases and users' Manual for the protocol of a Superior Pool Aerosol Removal Code (SPARC) (Owczarski, P.C., Schreck, R.I. 1985)" proposes that the phenomenon can be divided into three parts, one is that high-temperature mixed gas is discharged into liquid phase from gas phase space under the driving of pressure difference, and at the initial contact stage of gas and liquid phase, because the pressure of the discharged gas is higher, jet flow conditions are formed at the discharge outlet, namely, a significant gas phase core area exists, and because of the density difference, speed difference and temperature difference of the gas and liquid phases in the jet flow area, complicated mass, momentum and energy exchange processes occur, and radioactive substances carried in the gas phase can be contacted with the liquid phase and retained in the process. With the development of the jet flow form, the energy of the main flow gas is continuously dissipated, the main flow gas is finally slowed down and dispersed into discrete bubbles with different scales, the bubbles move upwards under the action of self buoyancy to form a pool type bubbling condition, and in the whole process that the bubbles pass through the liquid phase, radioactive substances carried in the gas phase can generate a mass transfer phenomenon at a gas-liquid interface under the action of multi-force fields such as inertia force, diffusion force and the like, so that part of the radioactive substances are transferred from the gas phase to the liquid phase and are retained. Finally, when the bubbles rise to the liquid surface area, the micro liquid drops formed by the broken liquid film may be carried into the gas space by the ascending gas flow, so that the radioactive substances are released secondarily. However, there may be retention and release of other radioactive materials due to different accidents, for example, in a steam generator tube breakage accident, because the heat transfer tube is not failed, there still exists a large amount of steam bubbles, which also causes secondary release of radioactivity. Because of the existence of complex gas-liquid two-phase environment and boundary conditions in the tank washing process, how to simulate the gas-phase environment and the liquid-phase environment in the accident phenomenon is the key point for carrying out experiments.
The document "Aerosol retention in low-sub atmospheric air under real aqueous acid conditions" (Dehbi, 2001) "designs an experimental device for researching the Aerosol water washing phenomenon based on the serious accident, wherein the main body of the experimental device is a tank body with the height of 5m and the diameter of 1m, and the experimental device is mainly used for simulating the migration and sedimentation characteristics of radioactive Aerosol under the large space condition, and the experimental working condition design is mainly based on the stable liquid phase condition, does not consider the condition of existence of violent heat exchange, does not consider the droplet entrainment phenomenon generated under the high apparent gas velocity condition, and is also an important way for the migration of radioactive substances under the serious accident condition. The literature, "ARTIST, an international project of relating aerosol retention in a particulate steam generator (Guntay, 2002)" designs an experimental device for researching aerosol retention phenomenon in a heat transfer pipe bundle area based on steam generator heat transfer pipe break accidents, and can truly reflect the aerosol migration and sedimentation characteristics in an actual steam generator, but the experimental device is mainly designed to be under the conditions of drying of the steam generator and re-flooding of cold water in the later period of the accident, and does not consider the violent two-phase flow phenomenon under the high-temperature and high-pressure conditions in the early period of the accident.
The invention provides an experimental system for researching retention characteristics of radioactive substances in a steam generator of a nuclear power plant, which mainly comprises a secondary side liquid phase environment simulation system, a secondary side water supply system, a gas and radioactive substance distribution system and a measurement system, wherein the secondary side liquid phase environment simulation system is used as a pressure-bearing boundary and a steam generator simulator, a boiling heat exchange environment in a heat transfer pipe bundle area under a working state is simulated by combining a pipe bundle structural type electric heating device, and a gas-liquid two-phase environment with extremely high gas content and apparent gas velocity in the steam generator is simulated by a variable cross-section structural design, so that the system can be applied to wider experimental conditions, the research on retention characteristics of the radioactive substances in the steam generator under different accident process conditions can be realized, meanwhile, the PID control design is adopted, and the complexity of experimental operation and control is reduced, the stability of experimental operating mode has been improved.
Disclosure of Invention
The invention aims to design an experimental system for researching the retention environment of radioactive substances in a steam generator of a nuclear power plant, which can be applied to wider experimental conditions, and further realizes the research on retention characteristics of the radioactive substances in the steam generator under different accident process conditions.
The purpose of the invention is realized as follows: the secondary side liquid phase environment simulation system comprises an upper end enclosure, a mixing straight section, a heating section cylinder, a lower end enclosure and a PID control device, wherein the mixing straight section is provided with an air inlet nozzle, the heating section cylinder is internally provided with a motor thermal device, a liquid level meter and a liquid level signal measuring device are arranged between the mixing straight section and the heating section cylinder, the upper end enclosure is provided with an exhaust pipe, the side surfaces of the mixing straight section and the heating section cylinder are respectively provided with a liquid discharge pipe, the lower end of the heating section cylinder is provided with a drain pipe, and the middle upper part of the heating section cylinder is provided with a water supply pipe; the gas distribution system is communicated with the gas inlet nozzle through a pipeline, the secondary side water supply system is communicated with the water feeding pipe, the exhaust pipe is provided with a pressure sensor, the side surfaces of the mixed straight section and the heating section cylinder are provided with a temperature measuring device, the measuring system comprises an acquisition system aiming at flow, temperature, pressure and concentration data, and data acquisition is carried out on temperature, pressure and flow measuring points in the secondary side liquid phase environment simulation system and the gas and radioactive simulant distribution system in an experiment.
The invention also includes such structural features:
1. the gas distribution system comprises an air distribution loop, a steam distribution loop, a radioactive simulant distribution loop and a collecting pipeline, wherein the air distribution loop, the steam distribution loop and the radioactive simulant distribution loop are connected together by the collecting pipeline, and are finally connected with the gas inlet nozzle through flanges respectively, and temperature and pressure measuring points are arranged on the pipe wall of the collecting pipeline.
2. The secondary side water supply system comprises a water supply tank, an adjusting valve, a water supply pump and an electric heating device, wherein the water supply tank, the adjusting valve, the water supply pump and the electric heating device are sequentially connected, the water supply pump is connected with a water supply pipe through a management and valve body, and the water supply pump is further connected with a PID control device.
3. The temperature measuring device comprises an upper measuring point, a middle measuring point and a lower measuring point which are arranged on the side surface of the mixing straight section and an upper measuring point and a lower measuring point which are arranged on the side surface of the heating section cylinder body and are used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions.
4. A heating rod in the electric heating device is arranged at the lower part of the whole system through a circular opening of a lower end enclosure, and the electric heating device is connected with a PID control device and a pressure sensor through a control circuit; the exhaust pipe is provided with a regulating valve which can be used together with an electric heating device to control the system pressure and the water evaporation capacity.
Compared with the prior art, the invention has the beneficial effects that: the experimental device adopts PID control, is provided with a pressure control mode and a power control mode, can switch the modes according to different experimental simulation working conditions, and can be suitable for simulating different accident processes. The experimental device adopts the variable cross-section design of the upper and lower cylinders, can realize the simulation of the complex gas-liquid two-phase environment with extremely high apparent gas velocity and volume gas content, and simultaneously reduces the error of sampling and measuring radioactive simulants. The experimental device adopts the design of the rod bundle type electric heating device as a simulation body of the heat transfer pipe of the steam generator, can simulate the migration process of radioactive substances in a boiling heat transfer area in the rod bundle, and can more comprehensively simulate the accident of the heat transfer pipe of the steam generator compared with other experimental devices. The experimental device has comprehensive system design, is combined with the PID automatic control device, is convenient and simple to operate, is stable and reliable, and reduces the error of manual control.
Drawings
FIG. 1 is a system diagram of an experimental apparatus.
Fig. 2 is a structural diagram of a secondary-side liquid phase environment simulation system.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
The experimental system design of the invention mainly comprises a secondary side liquid phase environment simulation system, a secondary side water supply system, a gas and radioactive simulant distribution system and a measurement system 4; the secondary side liquid phase environment simulation system adopts a variable cross-section design, has an electric heating function and is mainly used for simulating a two-phase thermal hydraulic environment in a steam generator of a nuclear power plant; the secondary side water supply system adopts intelligent control logic and is used for supplying solution with specific flow to the secondary side liquid phase environment simulation system; the gas and radioactive simulant distribution system is mainly used for simulating the spraying process of the coolant and the radioactive substances under the accident condition; the measurement system 4 is mainly used for collecting data signals such as pressure, temperature, flow and concentration in the experiment.
The secondary side liquid phase environment simulation system is composed of a heating section cylinder 1.11, a mixing straight section 1.12, a lower end enclosure 1.13, an upper end enclosure 1.14, an electric heating device 1.15, a PID control device 1.16, a pressure sensor 1.17, an exhaust pipe 1.18, a liquid level meter 1.19, a liquid level signal measuring device 1.20, a liquid discharge pipe 1.21, a water supply pipe 1.22, a sewage discharge pipe 1.23, an air inlet nozzle 1.24 and a temperature measuring device 1.25. The main body of the simulation system is combined and matched by an upper seal head 1.14, a mixing straight section 1.12, a heating section cylinder 1.11 and a lower seal head 1.13 from top to bottom in sequence, all structures are connected through flanges, the simulation system is a pressure-bearing boundary of the whole secondary side liquid phase environment simulation system, and a heat insulation material is arranged on the outer side of the simulation system to reduce heat dissipation in the system.
The heating section cylinder 1.11 is arranged at the lowest part of the secondary side liquid phase environment simulation system, mainly comprises most of liquid phase environment in the tank body, is a pressure-bearing boundary at the lower part of the whole secondary side liquid phase environment simulation system, and is used for creating a liquid phase environment with violent heat exchange in a heat transfer pipe bundle area. The rod beam type electric heating device 1.15 is installed in the heating section, the electric heating device 1.15 is sealed and fixed through the lower end enclosure 1.13, and in order to avoid damage to the electric heater due to overhigh local gas content when the electric heater runs at full power, the height and the diameter of the heating section cylinder are designed by combining the heating power and the corresponding proportional relation of the cylinder size. And a water feeding pipe 1.22 is arranged on the side surface of the secondary side water supply system and is connected with the secondary side water supply system, so that liquid phase temperature fluctuation caused by water feeding at other positions is avoided.
The electric heating device 1.15 is arranged at the lower part of the secondary side liquid phase environment simulation system, comprises fifteen cylindrical electric heating rods which are divided into five groups, namely a plurality of groups of constant power heating rods and 1 group of variable power heating rods, and the five groups of constant power heating rods and the 1 group of variable power heating rods are uniformly distributed in the heating section cylinder body 1.11 through a circular opening of the lower end socket 1.13. The appearance of the heat transfer tube simulation device adopts a cylindrical structure design to simulate the geometric structure of the heat transfer tube of the steam generator, and simultaneously, the influence of the geometric structure and the boiling heat exchange phenomenon on the migration behavior of radioactive substances under the normal working condition of the heat transfer tube can be simulated by combining the proportional relation between the size of the heating section tube body and the heating power. The design is two working modes, one is a power mode, the total heating power can be directly set for control, and the other is a pressure mode, the electric heating power can be controlled through a PID control device 1.16 according to the feedback signal of the pressure sensor, and then the pressure of the system is controlled. When the experiment is started, the liquid phase can be heated by constant-power temperature rise, the temperature and the pressure in the system are adjusted, and the working mode is adjusted according to the experiment requirement in the experiment.
The mixing straight section 1.12 is arranged at the upper part of the heating section cylinder 1.11, comprises a gas phase environment and a part of liquid phase environment in the tank body and is the upper pressure-bearing boundary of the whole secondary side liquid phase environment simulation system. The diameter of the cylinder is calculated according to the maximum designed electric heating power and the maximum apparent gas velocity in the steam generator, so that a complex gas-liquid two-phase environment with high volume gas content and high apparent gas velocity in the steam generator can be simulated, and meanwhile, the proper power and normal work of the electric heater in the limited space such as the heating section cylinder 1.11 are guaranteed due to the design based on the electric heating power. The diameter of the heating section cylinder obtained through calculation is larger than that of the mixing straight section cylinder, and in order to ensure that the section is uniformly changed to avoid higher local gas content, the variable-section cylinder is designed to be connected with the heating section cylinder 1.11.
The upper end enclosure 1.14 is arranged at the upper part of the secondary side liquid phase environment simulation system and is directly connected with the mixed straight section 1.12. The design is a conical reducing structure, the uppermost part is directly connected with the exhaust pipe 1.18 to ensure the uniform replacement of the radioactive simulant penetrating through the liquid phase and the upper gas, the loss of the radioactive simulant in the system is reduced, and meanwhile, the outlet is provided with a regulating valve which can be matched with a constant power mode of an electric heater for use to regulate the pressure of the tank body and the evaporation capacity of the solution.
The liquid level meter 1.19 is installed on the side surface of the secondary side liquid phase environment simulation system, is connected with the upper part and the lower part thereof in a welding pipeline mode, and is mainly used for liquid level direct reading in the experimental process. The liquid level signal measuring device 1.20 is also installed on the side face of the secondary side liquid phase environment simulation system, is connected with the PID control device 1.16 and the water replenishing pump 2.2 through a control circuit and a signal line, can obtain a liquid level signal according to the pressure difference of water levels on two sides in an experiment, further controls the secondary side water replenishing and supplying system to work through setting the liquid level by a program, and utilizes the water supplying pipe 1.22 to supply water. The temperature measuring device 1.25 comprises an upper measuring point, a middle measuring point and a lower measuring point which are arranged on the side surface of the mixing straight section 1.12, and an upper measuring point and a lower measuring point which are arranged on the side surface of the heating section cylinder 1.11, and is used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions. Air inlet nozzle 1.24 divide into three positions about in the top and bottom and install the lateral part at mixed straight section 1.12 for simulate different crevasse positions, can change nozzle structure, size and orientation simultaneously according to the difference of experimental operating mode, can open the valve before the air inlet nozzle after stabilizing system temperature pressure control in the experiment, spout and put the experiment. The liquid discharge pipes 1.21 are respectively installed at the upper, middle and lower parts of the secondary side liquid phase environment simulation system, and are used for taking out solutions at different positions in an experiment and analyzing physical property parameters, and simultaneously can measure the concentration and particle size distribution of sediments or dissolved matters retained in the secondary side liquid phase environment simulation system. After the experiment is finished, the sewage discharge pipe 1.23 arranged at the lowest part can be used for discharging the waste water and the sewage.
The secondary side water supply system is characterized by comprising a water supply tank 2.11, a water supply pump 2.12, an adjusting valve 2.13 and an electric heating device 2.14. The water replenishing tank 2.11 is used for supplying a solution for replenishing the secondary side liquid phase environment simulation system, is also a main body of the secondary side water replenishing system, is filled with a certain amount of deionized water or a specific solution, and is connected with the secondary side liquid phase environment simulation system through a water feeding pipe 1.22. The water replenishing pump 2.12 is used for replenishing water to the secondary side liquid phase environment simulation system, adopts automatic frequency conversion design and intelligent control logic, is connected with the PID control device 1.16 through a control circuit, and can control the water replenishing flow and the water level change according to the feedback signal of the liquid level signal measuring device 1.20. It has two kinds of operating modes of manual control and automatic control, at first adjusts the washing jar of body of watering through manual control in the experiment, then utilizes liquid level automatic control mode, sets for the liquid level through PID controlling means 1.16, adjusts the operating frequency and the switch of moisturizing pump 2.12 through the liquid level signal of liquid level signal measuring device 1.20 feedback to guarantee that the liquid level is stable. The electric heating device 2.14 is arranged inside the water replenishing tank 2.11 and comprises an electric heating device, a temperature measuring device and a temperature control device, an electric heating rod is adopted to heat the water body, the temperature of the solution in the water replenishing tank 2.11 is controlled, and pressure and temperature fluctuation caused by the fact that the supercooled water is replenished in the secondary side liquid phase environment simulation system in the experimental process is reduced.
The gas and radioactive simulant dispensing system is characterized by comprising an air dispensing loop 3.11, a steam dispensing loop 3.12 and a radioactive simulant dispensing loop 3.13. The air distribution loop 3.11 is mainly used for air distribution, the steam distribution loop 3.12 is mainly used for steam distribution, in order to meet the requirements of different flow working conditions, each loop is provided with pipelines with three diameters, vortex streets or mass flowmeters with different ranges are respectively arranged on the pipelines, different pipelines can be selected according to the experimental flow requirements, the flowmeter with the proper range is used for measurement, and each pipeline is provided with a regulating valve, a vortex street or mass flowmeter and a pressure sensor so as to obtain the volume flow and the mass flow of steam or air. The collecting pipeline connects the air distribution loop 3.11, the steam distribution loop 3.12 and the radioactive simulant distribution loop 3.13 together, and finally connects with the air inlet nozzle 1.24 through flanges, and temperature and pressure measuring points are installed on the pipe wall and used for monitoring the temperature and pressure of the inlet of the air inlet nozzle 1.24. In the experiment, the mass flow of air and steam is first regulated by the upstream flow meter indication, then the pressure sensor on the summing loop is used as the indication, the flow velocity in the nozzle is calculated according to the density of the mixed gas at the nozzle, and the gas flow is further regulated.
The measurement system 4 comprises an acquisition system aiming at flow, temperature, pressure and concentration data, data acquisition is required to be carried out on temperature, pressure and flow measurement points in a secondary side liquid phase environment simulation system and a gas and radioactive simulant distribution system in an experiment, corresponding measurement systems are arranged aiming at different radioactive simulants, and sampling monitoring is carried out at different positions of the whole system.
Fig. 1 is a diagram showing the overall design of the experimental apparatus, which is, from left to right, a gas distribution system, a secondary side water supply system, a secondary side liquid environment simulation system, and a measurement system 4. Fig. 2 is a structural diagram of a secondary side liquid phase environment simulation system, which sequentially comprises an upper end enclosure 1.14, a mixing straight section 1.12, a heating section cylinder 1.11 and a lower end enclosure 1.13 from top to bottom, and an air inlet nozzle 1.24 and a liquid level signal measuring device 1.20 are arranged on the side surface of the mixing straight section cylinder. The main structures of the system are connected through flanges, a sealing ring is arranged at the joint to form a pressure-bearing boundary of the secondary side liquid phase environment simulation system, and a heat insulation material is arranged on the outer side of the secondary side liquid phase environment simulation system to reduce heat dissipation. The upper end enclosure 1.14 is directly welded with the exhaust pipe 1.18 by adopting a conical design, so that the loss of radioactive simulants in the tank body can be reduced, and the exhaust pipe 1.18 is internally provided with a regulating valve which can be matched with the electric heating device 1.15 for use to control the system pressure and the water evaporation capacity. The mixed straight section 1.12 side is perforated and welded with a short pipe of a section of external flange, and can be matched with a flange of a converging loop 3.14 air inlet pipe, the sections of the two flanges are both provided with grooves, a circular plate-shaped structure of an inlet of an air inlet nozzle 1.24 can be fixed, an air inlet is arranged in the middle of the plate-shaped structure, the diameter of the air inlet is the same as that of the converging loop 3.14 air inlet pipe, the front side of the nozzle adopts a tapered conical structure as a transition section, and the shape, the size and the orientation of the rear end of the nozzle can be changed according to experimental working conditions. The heating section barrel 1.11 side upper portion trompil and welding have water pipe 1.22, directly link to each other through pipeline and moisturizing case 2.11, moisturizing pump 2.12 and governing valve 2.13 for control liquid level in the experimentation. The sewage discharge pipe 1.23 is welded at the lower part of the lower seal head through a hole of the lower seal head 1.13 and is used for discharging waste water and sewage. The heating rod in the electric heating device 1.15 is arranged at the lower part of the whole system through the round opening of the lower end socket 1.13, is simultaneously provided with sealing materials, and is connected with the PID control device 1.16 and the pressure sensor 1.17 through a control circuit. The liquid level meter 1.19 is installed on the side of the secondary side liquid phase environment simulation system, the upper part and the lower part of the liquid level meter are connected in a mode of opening holes and welding pipelines, and based on the principle of a communicating vessel, the liquid level change in the liquid level meter can be reflected through the change of the magnetic turning plate and is mainly used for liquid level direct reading in the experimental process. The liquid level signal measuring device 1.20 is installed on the side face of the secondary side liquid phase environment simulation system, holes are respectively formed in the upper side wall and the lower side wall of the secondary side liquid phase environment simulation system, stainless steel pipes are welded to serve as pressure taking ports, a buffer tank and a water replenishing valve are installed on the uppermost portion of each stainless steel pipe, a pressure difference sensor is installed on the lower portion of each stainless steel pipe, and the pressure difference sensor is connected with a PID control device 1.16 and a water replenishing pump 2.2 through a control circuit and a signal line. The liquid discharge pipes 1.21 are respectively installed at the upper, middle and lower parts of the secondary side liquid phase environment simulation system and comprise ball valves and stainless steel pipelines penetrating through the wall surface. The temperature measuring device 1.25 is arranged on the side surface of the secondary side liquid phase environment simulation system in a mode of opening a hole on the side wall and welding a base, and mainly comprises an upper measuring point, a middle measuring point and a lower measuring point which are arranged on the side surface of the mixed straight section 1.12, an upper measuring point, a lower measuring point and a main body K-type thermocouple, wherein the upper measuring point, the middle measuring point and the lower measuring point are arranged on the side surface of the heating section cylinder 1.11, and the main body K-type thermocouple is guaranteed to be arranged in an air space and liquid and is connected with the measuring system 4.
The main body of the secondary side water supply system is composed of a water supply tank 2.11, water or solution is stored in the water supply tank and used for supplying liquid level to a secondary side liquid phase environment simulation system, an inlet of a water supply pipe 1.22 is welded to the secondary side liquid phase environment simulation system through an opening in the outer wall of the water supply tank and is connected with the secondary side liquid phase environment simulation system, a water supply pump 2.12 and an adjusting valve 2.13 are further installed on a pipeline of the water supply tank and are used for adjusting water supply flow, and meanwhile, the water supply pump 2.12 is connected with a liquid level signal measuring device 1.20 and a PID. The electric heating device 2.14 is arranged on the side surface of the water replenishing tank 2.11 by a threaded interface through forming a hole on the side wall and welding a threaded base.
The gas distribution system includes an air distribution circuit 3.11, a vapor distribution circuit 3.12, and a radioactive simulant distribution circuit 3.13. The air distribution loop 3.11 and the heating steam loop 3.12 are provided with pipelines with three diameters, vortex streets or mass flowmeters with different ranges are respectively arranged on the pipelines, regulating valves are respectively arranged at the front and the rear parts for stabilizing the flow, and thermocouples and pressure sensors are arranged at the outlets of the valves so as to calculate the density of the steam or the air. The collecting pipeline is arranged behind the air distribution loop 3.11 and the steam distribution loop 3.12, the two loops are connected together through a stainless steel tee joint, meanwhile, different radioactive simulant distribution pipelines are arranged on openings on the side wall of the pipeline, then the pipeline is connected with the air inlet nozzle 1.24 through a welding flange on the outlet pipe, and temperature and pressure measuring points are arranged on the pipe wall and used for monitoring the temperature and the pressure of the inlet of the air inlet nozzle 1.24.
The measuring system 4 comprises an acquisition system aiming at flow, temperature, pressure and concentration data, the signal acquisition system is connected with temperature, pressure and flow measuring points in the secondary side liquid phase environment simulation system and the gas distribution system through signal lines, corresponding measuring devices are installed aiming at different radioactive simulants, and sampling ports are installed at different positions of the system to carry out sampling measurement on gas.
Claims (7)
1. An experimental system for researching retention characteristics of radioactive substances in a steam generator is characterized in that: the secondary side liquid phase environment simulation system comprises an upper end enclosure, a mixing straight section, a heating section cylinder, a lower end enclosure and a PID control device, wherein the mixing straight section is provided with an air inlet nozzle, the heating section cylinder is internally provided with a motor thermal device, a liquid level meter and a liquid level signal measuring device are arranged between the mixing straight section and the heating section cylinder, the upper end enclosure is provided with an exhaust pipe, the side surfaces of the mixing straight section and the heating section cylinder are respectively provided with a liquid discharge pipe, the lower end of the heating section cylinder is provided with a drain pipe, and the middle upper part of the heating section cylinder is provided with a water supply pipe; the gas distribution system is communicated with the gas inlet nozzle through a pipeline, the secondary side water supply system is communicated with the water feeding pipe, the exhaust pipe is provided with a pressure sensor, the side surfaces of the mixed straight section and the heating section cylinder are provided with a temperature measuring device, the measuring system comprises an acquisition system aiming at flow, temperature, pressure and concentration data, and data acquisition is carried out on temperature, pressure and flow measuring points in the secondary side liquid phase environment simulation system and the gas and radioactive simulant distribution system in an experiment.
2. The experimental system for studying retention characteristics of radioactive materials in a steam generator according to claim 1, wherein: the gas distribution system comprises an air distribution loop, a steam distribution loop, a radioactive simulant distribution loop and a collecting pipeline, wherein the air distribution loop, the steam distribution loop and the radioactive simulant distribution loop are connected together by the collecting pipeline, and are finally connected with the gas inlet nozzle through flanges respectively, and temperature and pressure measuring points are arranged on the pipe wall of the collecting pipeline.
3. An experimental system for studying retention characteristics of radioactive materials in a steam generator according to claim 1 or 2, wherein: the secondary side water supply system comprises a water supply tank, an adjusting valve, a water supply pump and an electric heating device, wherein the water supply tank, the adjusting valve, the water supply pump and the electric heating device are sequentially connected, the water supply pump is connected with a water supply pipe through a management and valve body, and the water supply pump is further connected with a PID control device.
4. The experimental system for studying retention characteristics of radioactive materials in a steam generator according to claim 3, wherein: the temperature measuring device comprises an upper measuring point, a middle measuring point and a lower measuring point which are arranged on the side surface of the mixing straight section and an upper measuring point and a lower measuring point which are arranged on the side surface of the heating section cylinder body and are used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions.
5. An experimental system for studying retention characteristics of radioactive materials in a steam generator according to claim 1 or 2, wherein: the temperature measuring device comprises an upper measuring point, a middle measuring point and a lower measuring point which are arranged on the side surface of the mixing straight section and an upper measuring point and a lower measuring point which are arranged on the side surface of the heating section cylinder body and are used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions.
6. The experimental system for studying retention characteristics of radioactive materials in a steam generator according to claim 3, wherein: a heating rod in the electric heating device is arranged at the lower part of the whole system through a circular opening of a lower end enclosure, and the electric heating device is connected with a PID control device and a pressure sensor through a control circuit; the exhaust pipe is provided with a regulating valve which can be used together with an electric heating device to control the system pressure and the water evaporation capacity.
7. The experimental system for studying retention characteristics of radioactive materials in a steam generator according to claim 4, wherein: a heating rod in the electric heating device is arranged at the lower part of the whole system through a circular opening of a lower end enclosure, and the electric heating device is connected with a PID control device and a pressure sensor through a control circuit; the exhaust pipe is provided with a regulating valve which can be used together with an electric heating device to control the system pressure and the water evaporation capacity.
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| CN115032124A (en) * | 2022-03-21 | 2022-09-09 | 哈尔滨工程大学 | Experimental device for studying retention characteristics of aerosol in single-size steam bubble under high-temperature and high-pressure conditions |
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