CN113188598B - 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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- CN113188598B CN113188598B CN202110469709.6A CN202110469709A CN113188598B CN 113188598 B CN113188598 B CN 113188598B CN 202110469709 A CN202110469709 A CN 202110469709A CN 113188598 B CN113188598 B CN 113188598B
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- 239000000941 radioactive substance Substances 0.000 title claims abstract description 34
- 230000014759 maintenance of location Effects 0.000 title claims abstract description 16
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 80
- 239000007791 liquid phase Substances 0.000 claims abstract description 68
- 238000004088 simulation Methods 0.000 claims abstract description 54
- 230000001502 supplementing effect Effects 0.000 claims abstract description 48
- 238000005259 measurement Methods 0.000 claims abstract description 12
- 239000007788 liquid Substances 0.000 claims description 44
- 238000010438 heat treatment Methods 0.000 claims description 37
- 238000005485 electric heating Methods 0.000 claims description 32
- 230000002285 radioactive effect Effects 0.000 claims description 26
- 239000012071 phase Substances 0.000 claims description 20
- 238000002156 mixing Methods 0.000 claims description 19
- 230000001105 regulatory effect Effects 0.000 claims description 19
- 238000013461 design Methods 0.000 claims description 18
- 238000000034 method Methods 0.000 claims description 16
- 238000002474 experimental method Methods 0.000 claims description 15
- 230000008569 process Effects 0.000 claims description 15
- 238000012546 transfer Methods 0.000 claims description 13
- 238000001704 evaporation Methods 0.000 claims description 5
- 230000008020 evaporation Effects 0.000 claims description 5
- 238000013480 data collection Methods 0.000 claims description 3
- 238000005507 spraying Methods 0.000 claims description 3
- 239000002826 coolant Substances 0.000 claims description 2
- 239000012857 radioactive material Substances 0.000 claims 2
- 238000007726 management method Methods 0.000 claims 1
- 238000007789 sealing Methods 0.000 description 9
- 239000000443 aerosol Substances 0.000 description 7
- 238000013508 migration Methods 0.000 description 7
- 230000005012 migration Effects 0.000 description 7
- 238000003466 welding Methods 0.000 description 6
- 229910001220 stainless steel Inorganic materials 0.000 description 5
- 239000010935 stainless steel Substances 0.000 description 5
- 238000010586 diagram Methods 0.000 description 4
- 238000005406 washing Methods 0.000 description 4
- 230000008859 change Effects 0.000 description 3
- 238000001914 filtration Methods 0.000 description 3
- 238000012544 monitoring process Methods 0.000 description 3
- 238000011160 research Methods 0.000 description 3
- 230000000717 retained effect Effects 0.000 description 3
- 238000005070 sampling Methods 0.000 description 3
- 239000010865 sewage Substances 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 230000001276 controlling effect Effects 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000007599 discharging Methods 0.000 description 2
- 230000017525 heat dissipation Effects 0.000 description 2
- 230000000149 penetrating effect Effects 0.000 description 2
- 238000003904 radioactive pollution Methods 0.000 description 2
- 238000004062 sedimentation Methods 0.000 description 2
- 239000002351 wastewater Substances 0.000 description 2
- 230000001174 ascending effect Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
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- 238000004364 calculation method Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000000498 cooling water 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
- 230000004927 fusion Effects 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
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- 230000007704 transition Effects 0.000 description 1
- 230000005514 two-phase flow Effects 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
Classifications
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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
Abstract
The invention provides an experimental system for researching the retention characteristics of radioactive substances in a steam generator, which mainly comprises a secondary side liquid phase environment simulation system, a secondary side water supplementing system, a gas and radioactive substance simulation distribution system and a measurement system.
Description
Technical Field
The invention relates to an experimental system for researching the detention 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 the migration detention phenomenon of the radioactive substances in the steam generator when serious accidents occur in the nuclear power plant.
Background
With the continuous development of society, the energy demand of various industries is increasingly serious, and nuclear power is widely applied worldwide as a clean and efficient energy source. However, because of the great danger, strict danger assessment is required for serious accidents caused by the runaway of the nuclear power plant, and the most serious threat is radioactive pollution caused by the leakage of radioactive substances, so that the research on the migration characteristics of the radioactive substances under the serious accident condition of the nuclear power plant is the key point of the current research. Pool filtration, in turn, is an important physical phenomenon involved in the progress of severe reactor accidents, and is present in a variety of reactor facilities, the most typical of which is steam generator heat transfer tube break-through accidents (SGTR). In the process, radioactive substances generated due to core fusion and the like enter a liquid phase along with non-condensable gas or water vapor, a part of the radioactive substances can stay in the liquid phase, a part of the radioactive substances also enter a gas space, the released radioactive substances can cause the risk of radioactive pollution of the whole two-loop system and even a factory building, and the stay characteristic of the radioactive substances in the liquid phase can have important influence on the radioactive concentration in a safety shell at the later stage of an accident, so that the stay 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 safety shell under the accident working condition and formulating corresponding accident relief measures.
According to the different accident processes, the pool washing and filtering phenomena are different, and the literature Technical Bases and User's Manual for the Prototype of a Suppression Pool Aerosol Removal Code (SPARC), (Owczarski, P.C., schreck, R.I. 1985) proposes that the pool washing and filtering phenomena can be divided into three parts, namely, high-temperature mixed gas is discharged into a liquid phase from a gas phase space under the drive of pressure difference, the gas forms jet flow conditions at a discharge pipe orifice due to higher pressure of the discharged gas in an initial contact stage with the liquid phase, namely, an obvious gas phase core area exists in the jet flow area, and the gas-liquid two phases in the jet flow area have complex mass, momentum and energy exchange processes due to the different density differences, speed differences and temperature differences, so that radioactive substances carried in the gas phase can be contacted with the liquid phase in the process to be retained. Along with the development of jet flow form, the energy of main flow gas is continuously dissipated, the final speed is reduced and dispersed into discrete bubbles with different dimensions, the bubbles upwards move under the action of self-buoyancy to form a pool-type bubbling condition, and in the whole process that the bubbles pass through a liquid phase, radioactive substances carried in a gas phase can generate mass transfer phenomena at a gas-liquid interface under the action of multiple 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 float to the liquid surface area, the micro liquid drops formed by the liquid film breaking are possibly carried by the ascending air flow into the air space, so that the radioactive substances are released secondarily. However, due to different accidents, other radioactive substances can be retained and released, for example, in the event of a crack of a heat transfer tube of a steam generator, a large amount of steam bubbles still exist because the heat transfer tube is not failed, and the secondary release of radioactivity can be caused. Because of the complex gas-liquid two-phase environment and boundary conditions in the pool washing process, how to simulate the gas-phase and liquid-phase environment in the accident phenomenon is the key of experimental performance.
The literature Aerosol retention in low-subcooling pools under realistic accident conditions (Dehbi, 2001) designs an experimental device for researching the aerosol water washing phenomenon based on the serious accident, wherein the experimental device is mainly a tank body with the height of 5m and the diameter of 1m and is mainly used for simulating the migration and sedimentation characteristics of radioactive aerosols under large space conditions, the experimental working condition design is mainly based on stable liquid phase conditions, the condition of intense heat exchange is not considered, and the phenomenon of liquid drop entrainment generated under the condition of high apparent gas velocity is not considered, so that the experimental device is also an important path for the migration of radioactive substances under the serious accident condition. The literature of ARTIST: an international patent project investigating aerosol retention in a ruptured steam generator (Guntay, 2002) designs an experimental device for researching the aerosol retention phenomenon in a heat transfer tube bundle area based on the break accident of a heat transfer tube of a steam generator, and can truly reflect the migration and sedimentation characteristics of the aerosol in an actual steam generator, but the experimental device is mainly designed to take the severe two-phase flow phenomenon under the conditions of drying and cold water re-flooding of the steam generator in the later period of the accident into consideration.
The invention provides an experimental system for researching the 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 supplementing system, a gas and radioactive substance distribution system and a measuring system.
Disclosure of Invention
The invention aims to design an experimental system for researching the radioactive substance retention environment in a steam generator of a nuclear power plant, which is applicable to wider experimental conditions, thereby realizing the research on the radioactive substance retention characteristics in the steam generator under different accident process conditions.
The purpose of the invention is realized in the following way: the system comprises a gas distribution system, a secondary side water supplementing system, a secondary side liquid phase environment simulation system and a measurement system, wherein the secondary side liquid phase environment simulation system comprises an upper end socket, a mixing straight section, a heating section cylinder, a lower end socket and a PID control device which are arranged from top to bottom; the gas distribution system is communicated with the air inlet nozzle through a pipeline, the secondary side water supplementing system is communicated with the water inlet pipe, a pressure sensor is arranged on the exhaust pipe, a temperature measuring device is arranged on the side face of the mixing straight section and the side face of the heating section cylinder body, the measuring system comprises a collection system aiming at flow, temperature, pressure and concentration data, and data collection is carried out on temperature, pressure and flow measuring points in the secondary side liquid phase environment simulation system and the gas and radioactive simulation material 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 summarizing pipeline, wherein the summarizing pipeline connects the air distribution loop, the steam distribution loop and the radioactive simulant distribution loop together, and is finally connected with an air inlet nozzle through flanges respectively, and temperature and pressure measuring points are arranged on the pipe wall of the summarizing pipeline.
2. The secondary side water supplementing system comprises a water supplementing tank, a regulating valve, a water supplementing pump and an electric heating device, wherein the water supplementing tank, the regulating valve and the water supplementing pump are sequentially connected, the electric heating device is arranged in the water supplementing tank, the water supplementing pump is connected with a water feeding pipe through a management and valve body, and the water supplementing 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 face of the mixing straight section, and an upper measuring point and a lower measuring point which are arranged on the side face of the heating section cylinder body, and is used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions.
4. The heating rod in the electric heating device is arranged at the lower part of the whole system through a circular opening of the lower seal head, and the electric heating device is connected with the PID control device and the pressure sensor through a control circuit; the exhaust pipe is provided with a regulating valve which can be matched with an electric heating device to control the pressure of the system and the evaporation amount of water.
Compared with the prior art, the invention has the beneficial effects that: the experimental device adopts PID control, is provided with pressure control and power control modes, can switch modes according to different experimental simulation working conditions, and is applicable to simulation of different accident processes. The experimental device adopts the variable cross-section design of the upper cylinder and the lower cylinder, can simulate 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 the radioactive simulant. The experimental device adopts the design of the rod-bundle type electric heating device as a simulator of the heat transfer tube of the steam generator, can simulate the migration process of radioactive substances in the boiling heat transfer region in the rod bundle, and can simulate the accident of the heat transfer tube of the steam generator more comprehensively compared with other experimental devices. The experimental device has comprehensive system design, combines 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 schematic diagram of a secondary side liquid phase environment simulation system.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
The experimental system design of the invention mainly comprises a secondary side liquid phase environment simulation system, a secondary side water supplementing system, a gas and radioactive simulation object 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 supplementing system adopts intelligent control logic and is used for supplementing a specific flow of solution 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 experiments.
The secondary side liquid phase environment simulation system consists of a heating section cylinder 1.11, a mixing straight section 1.12, a lower sealing head 1.13, an upper sealing head 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 system is combined and matched by an upper sealing head 1.14, a mixing straight section 1.12, a heating section cylinder 1.11 and a lower sealing head 1.13 in sequence from top to bottom, all the structures are connected through flanges, and are pressure-bearing boundaries of the whole secondary side liquid phase environment simulation system, and heat-insulating materials are arranged on the outer sides of the structures so as 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 of the lower part of the whole secondary side liquid phase environment simulation system, and is used for creating a liquid phase environment with severe heat exchange in a heat transfer tube bundle area. The rod cluster type electric heating device 1.15 is arranged in the electric heater, the electric heating device 1.15 is sealed and fixed through the lower sealing head 1.13, and the height and the diameter of the heating section cylinder are designed by combining the proportional relation of the heating power and the cylinder size in order to avoid the damage of the heater caused by the overhigh local air content when the electric heater runs at full power. The side surface of the water supply pipe is provided with a water supply pipe 1.22 which is connected with a secondary side water supply system so as to avoid liquid phase temperature fluctuation caused by water in other positions.
The electric heating device 1.15 is arranged at the lower part of the secondary side liquid phase environment simulation system and comprises fifteen cylindrical electric heating rods, wherein the fifteen cylindrical electric heating rods are divided into five groups, namely a plurality of groups of fixed-power heating rods and 1 group of variable-power heating rods, and the fixed-power heating rods and the variable-power heating rods are uniformly distributed in the heating section cylinder 1.11 through round holes of the lower sealing head 1.13. The shape of the steam generator adopts a cylindrical structural design to simulate the geometric structure of the steam generator heat transfer tube, and meanwhile, the influence of the geometric structure and the boiling heat exchange phenomenon on the migration behavior of radioactive substances can be simulated under the normal working condition of the heat transfer tube by combining the proportional relation of the size of the heating section cylinder and the heating power. The system is designed into two working modes, namely a power mode, wherein the total heating power can be directly set for control, and a pressure mode, the electric heating power can be controlled through the PID control device 1.16 according to the feedback signal of the pressure sensor, and the system pressure is further controlled. The liquid phase can be heated by constant power heating at first at the beginning of the experiment, the temperature and the pressure in the system are regulated, and the working mode is regulated 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 cylinder body, and is an upper pressure-bearing boundary of the whole secondary side liquid phase environment simulation system. The cylinder diameter design is calculated according to the maximum designed electric heating power and the highest apparent gas velocity in the steam generator, so that a complex gas-liquid two-phase environment with higher volume gas content and high apparent gas velocity in the steam generator can be simulated, and meanwhile, the electric heater power in a limited space such as the heating section cylinder 1.11 is also ensured to be suitable and can work normally based on the electric heating power design. The diameter of the cylinder body of the heating section obtained through calculation is larger than that of the cylinder body of the mixing straight section, and in order to ensure that the section is uniformly changed so as to avoid generating higher local air content, a variable section cylinder body is designed to be connected with the cylinder body 1.11 of the heating section.
The upper sealing head 1.14 is arranged at the upper part of the secondary side liquid phase environment simulation system and is directly connected with the mixing straight section 1.12. The device is designed into a conical tapered structure, the uppermost part of the device is directly connected with the exhaust pipe 1.18, so that the uniform replacement of the radioactive simulant penetrating through the liquid phase and the gas at the upper part is ensured, the loss of the radioactive simulant in the system is reduced, and meanwhile, an adjusting valve is arranged at an outlet of the device, so that the device can be matched with a constant-power mode of an electric heater for use, and the pressure of a tank body and the evaporation capacity of a solution are adjusted.
The liquid level meter 1.19 is arranged on the side surface of the secondary side liquid phase environment simulation system, and the upper part and the lower part of the liquid level meter are connected in a pipeline welding mode, so that the liquid level meter is mainly used for directly reading liquid level in the experimental process. The liquid level signal measuring device 1.20 is also arranged on the side surface of the secondary side liquid phase environment simulation system, is connected with the PID control device 1.16 and the water supplementing pump 2.2 through a control circuit and a signal wire, can obtain a liquid level signal according to the pressure difference of water levels at two sides in an experiment, further controls the secondary side water supplementing system to work through program setting of the liquid level, and utilizes the water feeding pipe 1.22 to feed 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 face of the mixing straight section 1.12, and an upper measuring point and a lower measuring point which are arranged on the side face of the heating section cylinder 1.11, and the temperature measuring device is used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions. The upper, middle and lower three positions of the air inlet nozzle 1.24 are arranged on the side part of the mixing straight section 1.12 and used for simulating different break positions, meanwhile, the structure, the size and the orientation of the nozzle can be changed according to different experimental working conditions, and a valve before the air inlet nozzle can be opened after the temperature and the pressure of the system are controlled stably in an experiment, so that a spraying experiment is carried out. The liquid discharge pipe 1.21 is respectively arranged at the upper part, the middle part and the lower part of the secondary side liquid phase environment simulation system and is used for taking out solutions at different positions in experiments and analyzing physical parameters, and meanwhile, the concentration and the particle size distribution of sediment or dissolved matters remained in the liquid discharge pipe can be measured. After the experiment is finished, the drain pipe 1.23 arranged at the lowest part can be used for discharging wastewater and sewage.
The secondary side water supplementing system is characterized by comprising a water supplementing tank 2.11, a water supplementing pump 2.12, a regulating valve 2.13 and an electric heating device 2.14. The water replenishing tank 2.11 is used for providing a solution replenishing the secondary side liquid phase environment simulation system, and is also a main body of the secondary side water replenishing system, a certain amount of deionized water or specific solution is filled in the water replenishing tank, and the water replenishing tank is connected with the secondary side liquid phase environment simulation system through the water feeding pipe 1.22. The water supplementing pump 2.12 is used for supplementing water to the secondary side liquid phase environment simulation system, adopts an automatic frequency conversion design and intelligent control logic, is connected with the PID control device 1.16 through a control circuit, and can control water supplementing flow and water level change according to the feedback signal of the liquid level signal measuring device 1.20. The design of the device has two working modes of manual control and automatic control, in the experiment, the upper water is firstly regulated by manual control to clean the tank body, then the liquid level is set by a PID control device 1.16 by utilizing a liquid level automatic control mode, and the working frequency and the switch of the water supplementing pump 2.12 are regulated by a liquid level signal fed back by a liquid level signal measuring device 1.20 so as to ensure the liquid level to be stable. The electric heating device 2.14 is arranged in the water supplementing tank 2.11 and comprises an electric heating device, a temperature measuring device and a temperature control device, and an electric heating rod is used for heating a water body and controlling the temperature of a solution in the water supplementing tank 2.11, so that pressure and temperature fluctuation generated in a secondary side liquid phase environment simulation system due to the fact that excessive cooling water is supplemented in an experiment process are reduced.
The gas and radioactive simulation distribution system is characterized by comprising an air distribution loop 3.11, a steam distribution loop 3.12 and a radioactive simulation distribution 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, three pipelines with different diameters are respectively arranged on each loop to meet the requirements of different flow conditions, vortex streets or mass flow meters with different measuring ranges are respectively arranged on each loop, different pipelines can be selected according to the requirements of experimental flow, and flow meters with proper measuring ranges are used for measurement, and each pipeline is provided with a regulating valve, a vortex streets or mass flow meter and a pressure sensor to obtain the volume flow and the mass flow of steam or air. After the air distribution loop 3.11, the steam distribution loop 3.12 and the radioactive simulation distribution loop 3.13 are connected together, the three loops are finally connected with the air inlet nozzle 1.24 through a flange, and temperature and pressure measuring points are arranged 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 air and steam mass flow is regulated by the upstream flowmeter indication, then the pressure sensor on the collecting circuit is used as an 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 a collection system for flow, temperature, pressure and concentration data, and in experiments, data collection needs to be carried out on temperature, pressure and flow measuring points in a secondary side liquid phase environment simulation system and a gas and radioactive analog distribution system, and meanwhile, corresponding measurement systems are arranged for different radioactive analog, and sampling monitoring is carried out at different positions of the whole system.
Fig. 1 shows an overall design diagram of an experimental device, and from left to right, the experimental device comprises a gas distribution system, a secondary side makeup water system, a secondary side liquid phase environment simulation system and a measurement system 4 in sequence. Fig. 2 is a schematic diagram of a secondary side liquid phase environment simulation system, which comprises 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 in sequence 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 surfaces of the upper seal head, the mixing straight section and the heating section cylinder 1.11. The main structures of the system are connected through flanges, a sealing ring is arranged at the joint, a pressure-bearing boundary of the secondary side liquid phase environment simulation system is formed, and a heat insulation material is arranged on the outer side of the secondary side liquid phase environment simulation system for reducing heat dissipation. The upper sealing head 1.14 is directly welded with the exhaust pipe 1.18 by adopting a conical design, so that the loss of a radioactive analog in a tank body can be reduced, and an adjusting valve arranged in the exhaust pipe 1.18 can be matched with the electric heating device 1.15 to control the pressure of the system and the evaporation amount of water. The side surface of the mixing straight section 1.12 is provided with a hole and welded with a short pipe with a section of external flange, the short pipe can be matched with the flange of the air inlet pipe of the converging loop 3.14, the sections of the two flanges are provided with grooves, the circular plate-shaped structure of the inlet of the air inlet nozzle 1.24 can be fixed, the middle of the plate-shaped structure is provided with an air inlet, the diameter of the air inlet is the same as that of the air inlet pipe of the converging loop 3.14, 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 upper part of the side surface of the heating section cylinder body 1.11 is provided with a hole and welded with a water feeding pipe 1.22, and the water feeding pipe is directly connected with a water supplementing tank 2.11, a water supplementing pump 2.12 and a regulating valve 2.13 through pipelines for controlling the liquid level in the experimental process. The blow-down pipe 1.23 is welded at the lower part of the lower seal head 1.13 through an opening, and is used for discharging wastewater and sewage. The heating rod in the electric heating device 1.15 is arranged at the lower part of the whole system through a circular opening of the lower seal head 1.13, is 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 arranged on the side surface 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 perforating and welding pipelines, and the liquid level change can be reflected through the change of the magnetic turning plate based on the principle of a communicating vessel, so that the liquid level meter is mainly used for directly reading the liquid level in the experimental process. The liquid level signal measuring device 1.20 is arranged on the side face of the secondary side liquid phase environment simulation system, holes are formed in the upper side wall and the lower side wall of the secondary side liquid phase environment simulation system respectively, stainless steel pipes are welded to serve as pressure taking ports, a buffer tank and a water supplementing valve are arranged at the uppermost part of each stainless steel pipe, a differential pressure sensor is arranged at the lower part of each stainless steel pipe, and the differential pressure sensor is connected with the PID control device 1.16 and the water supplementing pump 2.2 through a control circuit and a signal wire. The liquid discharge pipe 1.21 is respectively arranged at the upper, middle and lower parts of the secondary side liquid phase environment simulation system and comprises a ball valve and a stainless steel pipe 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 forming holes in the side wall and welding the 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, and an upper measuring point and a lower measuring point which are arranged on the side surface of the heating section cylinder 1.11, wherein a main body K-type thermocouple is arranged in a gas space and liquid and is connected with the measuring system 4.
The main body of the secondary side water supplementing system is composed of a water supplementing tank 2.11 in which water or solution is stored and is used for supplementing liquid level to the secondary side liquid phase environment simulation system, an inlet of a water feeding pipe 1.22 is connected with the secondary side liquid phase environment simulation system through an opening on the outer wall and welding, a water supplementing pump 2.12 and a regulating valve 2.13 are also arranged on a pipeline of the secondary side water supplementing system and are used for regulating water supplementing flow, and meanwhile, the water supplementing pump 2.12 is connected with a liquid level signal measuring device 1.20 and a PID control device 1.16 through a control circuit. The electric heating device 2.14 is mounted on the side of the water replenishing tank 2.11 by means of a threaded joint through holes in the side wall and welding a threaded base.
The gas distribution system comprises an air distribution circuit 3.11, a steam distribution circuit 3.12 and a radioactive simulation distribution circuit 3.13. The air distribution loop 3.11 and the heating steam loop 3.12 are respectively provided with three diameter pipelines, vortex street or mass flow meters with different measuring ranges are respectively arranged on the pipelines, regulating valves are respectively arranged at the front and the back of the pipelines for stabilizing the flow, and thermocouples and pressure sensors are arranged at the outlets of the valves so as to calculate the density of steam or air. The summarizing 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 installed on the side wall openings of the pipeline, then the pipelines are connected with the air inlet nozzle 1.24 through a welding flange on the outlet pipe, 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.
The measurement system 4 comprises an acquisition system aiming at flow, temperature, pressure and concentration data, the signal acquisition system is connected with a secondary side liquid phase environment simulation system and temperature, pressure and flow measurement points in a gas distribution system through signal lines, corresponding measurement devices are installed aiming at different radioactive simulants, and sampling ports are installed at different positions of the system to sample and measure gas.
Claims (7)
1. An experimental system for studying the retention characteristics of radioactive substances in a steam generator, characterized in that: the system comprises a gas and radioactive analog distribution system, a secondary side makeup water system, a secondary side liquid phase environment simulation system and a measurement system, wherein the secondary side liquid phase environment simulation system comprises an upper end socket, a mixing straight section, a heating section cylinder, a lower end socket and a PID control device which are arranged from top to bottom; the gas and radioactive simulant distribution system is communicated with the air inlet nozzle through a pipeline, the secondary side water supplementing system is communicated with the water inlet pipe, a pressure sensor is arranged on the exhaust pipe, a temperature measuring device is arranged on the side face of the mixing straight section and the heating section cylinder body, the measuring system comprises a collection system aiming at flow, temperature, pressure and concentration data, and data collection 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 secondary side liquid phase environment simulation system adopts a variable cross section design 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 supplementing system adopts intelligent control logic and is used for supplementing a specific flow of solution 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 heating section cylinder body comprises a majority of liquid phase environment in the cylinder 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 intense heat exchange in a heat transfer tube bundle area; the mixing straight section comprises a gas phase environment and a part of liquid phase environment in the tank body, and is an upper pressure-bearing boundary of the whole secondary side liquid phase environment simulation system; the diameter design of the cylinder is calculated according to the maximum designed electric heating power and the maximum apparent gas velocity in the steam generator so as to ensure that a complex gas-liquid two-phase environment with higher volume gas content and high apparent gas velocity in the steam generator can be simulated; the air inlet nozzle is arranged at the side part of the mixing straight section in an upper position, a middle position and a lower position and is used for simulating different break positions; the gas and radioactive simulation delivery system comprises an air delivery loop, a steam delivery loop, a radioactive simulation delivery loop and a summarizing pipeline.
2. An experimental system for investigating the retention characteristics of radioactive substances in a steam generator as set forth in claim 1, wherein: the air distribution loop, the steam distribution loop and the radioactive simulator distribution loop are connected together through the summarizing pipeline, and finally are respectively connected with the air inlet nozzle through flanges, and temperature and pressure measuring points are arranged on the pipe wall of the summarizing pipeline.
3. An experimental system for investigating the retention characteristics of radioactive substances in a steam generator according to claim 1 or 2, characterized in that: the secondary side water supplementing system comprises a water supplementing tank, a regulating valve, a water supplementing pump and an electric heating device, wherein the water supplementing tank, the regulating valve and the water supplementing pump are sequentially connected, the electric heating device is arranged in the water supplementing tank, the water supplementing pump is connected with a water feeding pipe through a management and valve body, and the water supplementing pump is further connected with a PID control device.
4. An experimental system for investigating the retention properties of radioactive materials in a steam generator as claimed in claim 3, characterized in that: the temperature measuring device comprises an upper measuring point, a middle measuring point and a lower measuring point which are arranged on the side face of the mixing straight section, and an upper measuring point and a lower measuring point which are arranged on the side face of the heating section cylinder body, and is used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions.
5. An experimental system for investigating the retention characteristics of radioactive substances in a steam generator according to claim 1 or 2, characterized in that: the temperature measuring device comprises an upper measuring point, a middle measuring point and a lower measuring point which are arranged on the side face of the mixing straight section, and an upper measuring point and a lower measuring point which are arranged on the side face of the heating section cylinder body, and is used for measuring the liquid phase temperature and the gas phase temperature under different liquid level conditions.
6. An experimental system for investigating the retention properties of radioactive materials in a steam generator as claimed in claim 3, characterized in that: the heating rod in the electric heating device is arranged at the lower part of the whole system through a circular opening of the lower seal head, and the electric heating device is connected with the PID control device and the pressure sensor through a control circuit; the exhaust pipe is provided with a regulating valve which can be matched with an electric heating device to control the pressure of the system and the evaporation amount of water.
7. An experimental system for investigating the retention properties of a radioactive substance in a steam generator as set forth in claim 4, wherein: the heating rod in the electric heating device is arranged at the lower part of the whole system through a circular opening of the lower seal head, and the electric heating device is connected with the PID control device and the pressure sensor through a control circuit; the exhaust pipe is provided with a regulating valve which can be matched with an electric heating device to control the pressure of the system and the evaporation amount of water.
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