CN112614602B - Modeling experiment system and method for stirring characteristics of outlet impact jet flow of sodium-cooled fast reactor core - Google Patents
Modeling experiment system and method for stirring characteristics of outlet impact jet flow of sodium-cooled fast reactor core Download PDFInfo
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Abstract
The invention discloses a sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system and a sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment method. The experiment main loop mainly comprises equipment such as a high-pressure plunger pump, a heat regenerator, a preheating section, an experiment section, a condenser, a water tank and the like and pipe network accessories; the secondary cooling loop mainly comprises a condenser, a circulating water pump, a cooling water tank, pipe network accessories and the like; the data measurement system mainly comprises a mass flow meter, a quick response thermocouple and a particle image velocimetry system; the geometric design of the jet flow outlet of the experimental section is based on the actual structure of the component head at the outlet of the reactor core of the sodium-cooled fast reactor, the experimental system and the method have the advantages of visual experimental process, high experimental precision, simple and easy working condition switching and the like, and have important significance for researching the mixing characteristic of the impact jet flow at the outlet of the reactor core of the sodium-cooled fast reactor.
Description
Technical Field
The invention belongs to the technical field of sodium-cooled fast reactor cores, and particularly relates to a modeling experiment system and method for the outlet impact jet flow mixing characteristic of a sodium-cooled fast reactor core.
Background
The sodium-cooled fast reactor is one of the fast reactor types developed in the fourth-generation advanced reactor due to the advantages of the sodium-cooled fast reactor in the aspects of inherent safety, fertile nuclear fuel, transmutation long-life radioactive waste and the like. The pool type sodium-cooled fast reactor adopts liquid metal sodium as a coolant, most equipment is placed in a pool in the design, a reactor core adopts a box type design and is a typical closed fuel assembly, and an outlet area of the fast reactor assembly comprises an assembly head, a flow guide pipe, a honeycomb type positioning grid frame, a measuring probe and other complex structures.
The complex reactor core outlet structure causes extremely complex flow state of an outlet area, obvious impact jet flow mixing phenomenon appears at the reactor core outlet, temperature fluctuation is severe, the temperature of a coolant in the running process of the sodium-cooled fast reactor is high, temperature oscillation generated by liquid sodium impact jet flow is easier to transfer to a solid structure due to large heat conductivity coefficient of liquid metal sodium, severe thermal fatigue hazard is brought to the reactor core outlet area structure, the safety and reliability of the reactor are affected, and the sodium-cooled fast reactor core outlet area structure failure event generated due to long-term severe temperature oscillation has occurred for many times internationally. Therefore, the coolant impinging jets with different temperatures in the outlet area of the sodium-cooled fast reactor core are important thermal hydraulic phenomena which need to be considered in the design of the fast reactor structure, and are hot spots of fast reactor research in the international world.
For the jet mixing research work of fluid, research is mostly carried out at home and abroad by using an impact jet process of a simple channel, for example, zhang Dongwei discloses a published document (Zhang Dongwei, he Yaling, wang Yong, ceramic bolt).
A document published by the university of Zhukov et al (A.V.Zhukov, E.P.Ivanov, S.N.Kovtun, et al.experiments on mixing of sodium jet of a differential temperature in space above fuel pins in a fast reactor subassemby of BN-350and BN-600type J. State Scientific Center Institute of Physics and Power Engineering, obning, russia, 1994.) has made experimental studies on the mixing of different temperature sodium jets in the chamber above the head of an Russian BN series fast reactor fuel rod assembly. The main purpose of the experiment is to study the sodium temperature control and liquid sodium temperature fluctuation condition in the upper cavity of the reactor core under the steady state condition.
However, although there are many studies on jet mixing phenomenon at home and abroad, the study is mostly carried out by using the impact jet process of a simple channel, for a sodium-cooled fast reactor, the impact jet phenomenon is closely related to the design structure of the reactor core outlet of the fast reactor and the operation characteristics of the whole reactor, and the study on the impact jet phenomenon of the simple channel cannot meet the design requirements of the sodium-cooled fast reactor. In addition, liquid metal sodium is active in chemical property, inflammable and explosive, the impact jet process under a complex structure of a reactor core outlet of a fast reactor is very complex, the problems in measurement and control are solved directly on a sodium loop rack, and meanwhile, due to the extremely poor light transmittance of the liquid metal, a visual experiment cannot be carried out in the experimental process, and the visual reproduction of jet mixing details is difficult.
Therefore, in order to accurately master the impact jet characteristics of the outlet of the fast reactor core under a complex structure, a special scaling prototype experiment bench needs to be designed based on a similar principle aiming at the design form of a specific outlet to carry out a modeling experiment system.
Disclosure of Invention
The invention aims to provide a modeling experiment system and a modeling experiment method for impingement jet mixing characteristics of a sodium-cooled fast reactor core outlet, which are a scaling prototype experiment bench modeling experiment system aiming at a specific outlet design form based on a similar principle and are used for researching the impingement jet mixing phenomenon of the sodium-cooled fast reactor core outlet under a complex structure.
In order to achieve the purpose, the invention adopts the following technical scheme:
a sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system comprises an experiment main loop, an experiment section, a secondary cooling loop and a data measurement system;
the experimental main loop comprises a deionized water machine 18, a water replenishing tank 19, a first ball valve 20, a first water replenishing pump 21, a second ball valve 22, a first water tank 15, a first stop valve 17, a cooler 16, a second stop valve 14, a first pre-valve filter 13, a first plunger pump 12, a first pressure sensor 36, a second pressure sensor 35, a third stop valve 11, a fourth stop valve 10, a mass flow meter 9, a fifth stop valve 8, a sixth stop valve 23, a seventh stop valve 7, a regenerative heat regenerator 6 pipe outer area, a preheating section 5 and a direct current power supply 4; the experiment main loop is used for providing enough deionized cooling water for the whole experiment system, incoming water of the experiment main loop is divided into two paths, the first path is that the incoming water from the outside is directly supplemented into the loop, and the other path is working medium water flowing through the experiment loop, and the working medium water flows out of the experiment section, is treated and then is supplemented into the experiment main loop;
the first path of external incoming water is supplemented into an experimental main loop, firstly flows into a deionized water machine 18 to remove impurity ions, the back of the deionized water machine is connected with a water supplementing tank 19, the downstream of the water supplementing tank 19 is sequentially connected with a first ball valve 20, a first water supplementing pump 21 and a second ball valve 22, the downstream of the second ball valve 22 is connected with a first water tank 15, and the amount of the deionized water pumped into the first water tank 15 is controlled by adjusting the first ball valve 20 and the second ball valve 22 to maintain the water content in the first water tank 15; the downstream of the first water tank 15 is divided into two paths, one path is a bypass flow path designed for regulating flow and pressure, a first stop valve 17 and a cooler 16 on the bypass flow path are sequentially connected to the downstream of the first water tank 15, the other path on the downstream of the first water tank is sequentially connected with a second stop valve 14, a first pre-valve filter 13 and a first plunger pump 12, a first pressure sensor 36 and a second pressure sensor 35 are respectively arranged between the first pre-valve filter 13 and the first plunger pump 12 and on the downstream of the first plunger pump 12, and the upstream and downstream pressures of the first plunger pump 12 are measured; the third stop valve 11 is connected downstream of the second sensor 35, and the pipe downstream of the cooler 16 on the bypass flow path is reconnected between the second pressure sensor 35 and the third stop valve 11;
the downstream of the third stop valve 11 is three parallel sub-channels, each sub-channel is sequentially provided with a fourth stop valve 10, a mass flow meter 9 and a fifth stop valve 8, the mass flow meter 9 measures the flow of the working medium entering the experimental section, and the fourth stop valve 10 and the fifth stop valve 8 in front of and behind the mass flow meter are adjusted according to the experimental requirements for flow adjustment; the difference is that two channels are connected with the downstream of the fifth stop valve 8 on one of the parallel sub-channels, one channel directly leads the working medium into the preheating section 5 through a sixth stop valve 23 connected with the downstream of the fifth stop valve 8, the other channel is connected with a seventh stop valve 7 behind the fifth stop valve 8, the rest working medium is led into the outer tube area of the regenerative heat regenerator 6 to be heated by adjusting the seventh stop valve 7, the regenerative heat regenerator 6 is divided into an inner tube area and an outer tube area, and the outer tube area outlet of the regenerative heat regenerator 6 is connected with the preheating section 5; the downstream of a fifth stop valve 8 on the other two parallel sub-channels is directly connected with a preheating section 5; the direct current power supply 4 provides a heating energy source for the preheating section 5, and the working medium enters the experimental section after being heated to the required temperature in the preheating section 5;
the experimental section is connected with the preheating section 5, the experimental section is a plurality of groups of component heads 1 arranged in a downstream pipeline of the preheating section 5, the geometric design of the component heads 1 is based on the actual structure of the outlet component head of the sodium-cooled fast reactor core, and the working medium enters the downstream pipeline through the component heads 1 in a jet flow mode and flows out of the experimental section;
after being sprayed out from the outlet of the assembly head 1 of the experimental section, the working medium enters the pipe-in area of the regenerative heat regenerator 6 at the downstream of the experimental section and is cooled by cold water outside the pipe; the downstream of the pipe inner area of the regenerative heat regenerator 6 is connected with a condenser 24 and enters a secondary cooling loop; the inner area of the condenser 24 is also divided into an inner area and an outer area, the inner area is circulated with hot working medium from the regenerative heat regenerator 6, and the outer area is circulated with cold working medium from the second water tank 31;
the secondary cooling loop is a circulation loop and comprises a condenser 24, a cooling tower 32, a second water tank 31, an eighth stop valve 30, a cooling water pump 29, a third pre-valve filter 28, a second pre-valve filter 25, a ninth stop valve 26, a tenth stop valve 27 and a third ball valve 34; the main function of the cooling device is to cool the experimental working medium of the main loop of the experiment, provide sufficient cooling water working medium for the experimental section and ensure the long-time safe and stable operation of the loop; the secondary cooling loop is specifically composed of: the water from the experimental section passes through the pipe-in area of the condenser 24 and enters a cooling tower 32 connected with the outlet of the pipe-in area for further cooling, the downstream of the cooling tower is sequentially connected with a second water tank 31, an eighth stop valve 30, a cooling water pump 29 and a third pre-valve filter 28, the downstream of the third pre-valve filter 28 is connected with the inlet of the pipe-out area of the condenser 24, the outlet of the pipe-out area of the condenser 24 is connected with the second pre-valve filter 25, the downstream of the second pre-valve filter 25 is connected with a ninth stop valve 26 and a tenth stop valve 27 which are arranged in parallel, the downstream of the ninth stop valve 26 and the tenth stop valve 27 is connected with a first water tank 15, the working medium is supplemented into the first water tank, and therefore, the second incoming water of the experimental main loop is formed; in addition, a branch is divided between the downstream of the ninth stop valve 26 and the tenth stop valve 27 which are arranged in parallel and the middle of the first water tank 15, a third ball valve 34 is installed on the branch, namely a sewage draining outlet, and after the experiment is carried out for a period of time, the experiment working medium is discharged through the third ball valve 34;
the data measurement system consists of a mass flowmeter 9, a quick-response thermocouple 33 and a particle image velocimetry system; the mass flow meter 9 is arranged on three sub-channels of the experiment main loop system, is positioned behind the third stop valve 10 and in front of the fourth stop valve 8 and is used for measuring the flow of the deionized water entering the experiment section; a plurality of groups of rapid reaction thermocouples 33 are arranged along the axial direction and the circumferential direction of the head part pipeline of the experimental section assembly, and the energy exchange characteristic in the jet flow process is reflected by monitoring the temperature field distribution information; the particle image velocimetry system comprises a sheet light source 2 and a high-speed camera 3, and the sheet light source and the high-speed camera are connected into a data acquisition system of a computer for subsequent data acquisition and processing.
The experiment section is that the subassembly head 1 is the multiunit, can make up according to the experiment needs, carries out multiplex condition experiment simulation.
In the experimental section, after the working medium is sprayed out from the component head 1, a strong turbulence state is presented, the component head 1 is based on the actual structure of the component head at the outlet of the real sodium-cooled fast reactor core, and the outlet structure is complex, so that the working medium state which is more attached to the outlet of the real fast reactor core can be obtained.
The experimental working medium of the experimental system is water.
The whole of experiment section adopts the organic glass board to make, is convenient for adopt particle image system of testing the speed to trail and visual shooting impact efflux process flow field detail.
The direct current power supply 4 is a plurality of groups of low-voltage large-current direct current power supplies.
The regenerative heat exchanger 6 is a double pipe heat exchanger.
The preheating section 5 is a stainless steel snake-shaped coil pipe structure arranged in parallel, and an experimental working medium is heated by utilizing a joule heat effect generated by electrifying a resistance of a pipe wall.
According to the experimental method of the sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experimental system, in an experiment, water is adopted to replace liquid metal sodium as an experimental working medium, in order to ensure that key phenomena in the impact jet flow mixing under the water working medium are consistent with the liquid sodium working medium, a partial similarity theory is adopted in the experiment, a similarity criterion with small influence on the flow problem is ignored, on the premise that the geometric conditions are similar, the Reynolds number in the flow process and the dimensionless power spectrum number in the mixing are ensured to be similar, so that the obtained experimental data are ensured to have referential property on a real sodium-cooled fast reactor, namely, the liquid metal sodium and the experimental working medium water are ignored to have obvious different high thermal conductivity, and under the strong turbulence state of an outlet of a component head 1, the forced flow with high Reynolds number is mainly dominant in the energy exchange process, the influence on the thermal conductivity is reduced, and the component head 1 structure of the real sodium-cooled fast reactor is adopted, so that the initial conditions, the boundary conditions, the geometric conditions and the similarity of the real sodium-cooled fast reactor are ensured; during the whole experiment, the deionized water machine 18 supplies deionized water to the water replenishing tank 19, and the first ball valve 20 and the second ball valve 22 are adjusted as required to replenish the deionized water to the first water tank 15 through the second plunger pump 21; deionized water is pumped into the first water tank 15 through a second stop valve 14 and a first pre-valve filter 13 and then is divided into two paths through a first plunger pump 12, wherein one path is a bypass system designed for regulating flow and pressure and consists of a cooler 16 and a first stop valve 17; the flow of the deionized water entering the experimental section is adjusted through the first stop valve 17 and the third stop valve 11 as required; in the first sub-channel, deionized water enters the regenerative heat exchanger 6 after passing through the mass flow meter 9, the regenerative heat exchanger 6 is in a sleeve pipe form, the deionized water absorbs heat of a high-temperature working medium from the experimental section, the deionized water is heated to a required temperature through the preheating section 5 and then enters the experimental section from the lower part, and the working medium in the remaining two sub-channels directly flows into the preheating section 5 after passing through the mass flow meter and is heated to the required temperature; the deionized water from the experimental section is fed again via the secondary cooling circuit into the water tank 15 via the recuperative heat exchanger 6 and the condenser 24.
The invention has the following advantages and beneficial effects:
1. the geometric design of the jet flow outlet of the experimental section is based on the actual structure of the component head at the outlet of the sodium-cooled fast reactor core, and has important significance for the research on the impact jet flow mixing characteristic of the outlet of the sodium-cooled fast reactor core;
2. two groups and a plurality of groups of impact jet experiment outlet devices are arranged in the experiment section, so that the function of rapidly switching the experiment working conditions is realized;
3. on the basis of a similarity principle, on the premise of geometric similarity, the key phenomenon in impact jet flow mixing under water working medium is ensured to be consistent with sodium working medium by ensuring that the Reynolds number in the flowing process and the dimensionless power frequency spectrum number in the thermal mixing are similar. On one hand, the experiment cost is reduced, on the other hand, the safety of the experiment is greatly improved, and the possibility is provided for visualization;
4. the experiment system adopts a particle image speed measurement technology, can obtain full-field flow data at one time, and has high measurement precision and high visualization degree.
Drawings
FIG. 1 is a schematic diagram of an experimental system of the present invention.
Wherein: 1. an assembly head; 2. a sheet light source; 3. a high-speed camera; 4. a direct current power supply; 5. a preheating section; 6. a regenerative heat exchanger; 7. a seventh stop valve; 8. a fifth stop valve; 9. a mass flow meter; 10. a fourth stop valve; 11. a third stop valve; 12. a first plunger pump; 13. a first pre-valve filter; 14. a second stop valve; 15. a first water tank; 16. a cooler; 17. a first shut-off valve; 18. a deionized water machine; 19. a water replenishing tank; 20. a first ball valve; 21. a second plunger pump; 22. a second ball valve; 23. a sixth stop valve; 24. a condenser; 25. a second pre-valve filter; 26. a ninth cut-off valve; 27. a tenth stop valve; 28. a third pre-valve filter; 29. a cooling water pump; 30. an eighth stop valve; 31. a second water tank; 32. a cooling tower; 33. fast reaction thermocouple, 34, third ball valve, 35, second pressure sensor, 36, first pressure sensor.
FIG. 2 is a geometric schematic diagram of a sodium-cooled fast reactor core outlet assembly.
Wherein, 1-1, first biological shielding; 2-1. First shielding; 3-1. Second biological shielding;
4-1. A second shield; 5-1. Sodium pool space; 6-1. A central measuring column; 7-1, a control rod guide tube;
8-1, measuring the probe and the catheter; 1. and assembling the assembly head.
Detailed Description
The invention is described in further detail below with reference to the accompanying drawings:
referring to fig. 1, the sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system comprises four parts, namely an experiment main loop, an experiment section, a secondary cooling loop and a data measurement system;
the experimental main loop comprises a deionized water machine 18, a water replenishing tank 19, a first ball valve 20, a first water replenishing pump 21, a second ball valve 22, a first water tank 15, a first stop valve 17, a cooler 16, a second stop valve 14, a first pre-valve filter 13, a first plunger pump 12, a first pressure sensor 36, a second pressure sensor 35, a third stop valve 11, a fourth stop valve 10, a mass flow meter 9, a fifth stop valve 8, a sixth stop valve 23, a seventh stop valve 7, an outer pipe area of a regenerative heat regenerator 6, a preheating section 5 and a direct-current power supply 4; the experiment main loop is used for providing enough deionized cooling water for the whole experiment system, incoming water of the experiment main loop is divided into two paths, the first path is that the incoming water from the outside is directly supplemented into the loop, and the other path is working medium water flowing through the experiment loop, and the working medium water flows out of the experiment section, is treated and then is supplemented into the experiment main loop;
the first path of external incoming water is supplemented into an experimental main loop, firstly flows into a deionized water machine 18 to remove impurity ions, the back of the deionized water machine is connected with a water supplementing tank 19, the downstream of the water supplementing tank 19 is sequentially connected with a first ball valve 20, a first water supplementing pump 21 and a second ball valve 22, the downstream of the second ball valve 22 is connected with a first water tank 15, and the amount of the deionized water pumped into the first water tank 15 is controlled by adjusting the first ball valve 20 and the second ball valve 22 to maintain the water content in the first water tank 15; the downstream of the first water tank 15 is divided into two paths, one path is a bypass flow path designed for regulating flow and pressure, a first stop valve 17 and a cooler 16 on the bypass flow path are sequentially connected to the downstream of the first water tank 15, the other path on the downstream of the first water tank is sequentially connected with a second stop valve 14, a first pre-valve filter 13 and a first plunger pump 12, a first pressure sensor 36 and a second pressure sensor 35 are respectively arranged between the first pre-valve filter 13 and the first plunger pump 12 and on the downstream of the first plunger pump 12, and the upstream and downstream pressures of the first plunger pump 12 are measured; the third stop valve 11 is connected downstream of the second sensor 35, and the pipe downstream of the cooler 16 on the bypass flow passage is reconnected between the second pressure sensor 35 and the third stop valve 11;
three parallel sub-channels are arranged at the downstream of the third stop valve 11, a fourth stop valve 10, a mass flow meter 9 and a fifth stop valve 8 are sequentially arranged on each sub-channel, the mass flow meter 9 measures the flow of the working medium entering the experimental section, and the fourth stop valve 10 and the fifth stop valve 8 in front of and behind the mass flow meter are adjusted according to the experimental requirement to adjust the flow; the difference is that two channels are connected with the downstream of the fifth stop valve 8 on one of the parallel sub-channels, one channel directly leads the working medium into the preheating section 5 through a sixth stop valve 23 connected with the downstream of the fifth stop valve 8, the other channel is connected with a seventh stop valve 7 behind the fifth stop valve 8, the rest working medium is led into the outer tube area of the regenerative heat regenerator 6 to be heated by adjusting the seventh stop valve 7, the regenerative heat regenerator 6 is divided into an inner tube area and an outer tube area, and the outer tube area outlet of the regenerative heat regenerator 6 is connected with the preheating section 5; the downstream of a fifth stop valve 8 on the other two parallel sub-channels is directly connected with a preheating section 5; the direct current power supply 4 provides a heating energy source for the preheating section 5, and the working medium is heated to the required temperature in the preheating section 5 and then enters the experiment section;
the experimental section is connected with the preheating section 5, the experimental section is a plurality of groups of component heads 1 arranged in a downstream pipeline of the preheating section 5, the geometric design of the component heads 1 is based on the actual structure of the outlet component head of the sodium-cooled fast reactor core, and the working medium enters the downstream pipeline through the component heads 1 in a jet flow mode and flows out of the experimental section;
after being sprayed out from the outlet of the assembly head 1 of the experimental section, the working medium enters the pipe-in area of the regenerative heat regenerator 6 at the downstream of the experimental section and is cooled by cold water outside the pipe; the downstream of the pipe inner area of the regenerative heat regenerator 6 is connected with a condenser 24 and enters a secondary cooling loop; the inner area of the condenser 24 is also divided into an inner area and an outer area, the inner area is circulated with hot working medium from the regenerative heat regenerator 6, and the outer area is circulated with cold working medium from the second water tank 31;
the secondary cooling loop is a circulation loop and comprises a condenser 24, a cooling tower 32, a second water tank 31, an eighth stop valve 30, a cooling water pump 29, a third pre-valve filter 28, a second pre-valve filter 25, a ninth stop valve 26, a tenth stop valve 27 and a third ball valve 34; the main function of the cooling device is to cool the experimental working medium of the main loop of the experiment, provide sufficient cooling water working medium for the experimental section and ensure the long-time safe and stable operation of the loop; the secondary cooling loop specifically consists of: the water from the experimental section passes through the pipe-in area of the condenser 24 and enters a cooling tower 32 connected with the outlet of the pipe-in area for further cooling, the downstream of the cooling tower is sequentially connected with a second water tank 31, an eighth stop valve 30, a cooling water pump 29 and a third pre-valve filter 28, the downstream of the third pre-valve filter 28 is connected with the inlet of the pipe-out area of the condenser 24, the outlet of the pipe-out area of the condenser 24 is connected with the second pre-valve filter 25, the downstream of the second pre-valve filter 25 is connected with a ninth stop valve 26 and a tenth stop valve 27 which are arranged in parallel, the downstream of the ninth stop valve 26 and the tenth stop valve 27 is connected with a first water tank 15, the working medium is supplemented into the first water tank, and therefore, the second incoming water of the experimental main loop is formed; in addition, a branch is divided between the downstream of the ninth stop valve 26 and the tenth stop valve 27 which are arranged in parallel and the middle of the first water tank 15, a third ball valve 34 is installed on the branch, namely a sewage draining outlet, and after the experiment is carried out for a period of time, the experiment working medium is discharged through the third ball valve 34;
the data measurement system consists of a mass flowmeter 9, a quick response thermocouple 33 and a particle image velocimetry system; the mass flow meters 9 are arranged on three sub-channels of the experiment main loop system, are positioned behind the third stop valve 10 and in front of the fourth stop valve 8 and are used for measuring the flow of the deionized water entering the experiment section; a plurality of groups of rapid reaction thermocouples 33 are arranged along the axial direction and the circumferential direction of the head part pipeline of the experimental section assembly, and the energy exchange characteristic in the jet flow process is reflected by monitoring the temperature field distribution information; the particle image velocimetry system comprises a sheet light source 2 and a high-speed camera 3, and the sheet light source and the high-speed camera are connected into a data acquisition system of a computer for subsequent data acquisition and processing. The particle image velocimetry method is a non-intrusive measurement method, does not bring additional influence to a measured flow field, and the particle image velocimetry technology can obtain full-field flow data at one time.
As a preferred embodiment of the invention, the experimental section, namely the assembly head 1, is a plurality of groups, and can be combined according to experimental needs to perform multi-working condition experimental simulation.
In the experimental section, after the working medium is sprayed out from the component head 1, a strong turbulence state is presented, the component head 1 is based on the actual structure of the component head at the outlet of the real sodium-cooled fast reactor core, and the outlet structure is complex, so that the working medium state which is more attached to the outlet of the real fast reactor core can be obtained.
The experimental working medium of the experimental system is water, and the liquid metal sodium is active in chemical property, inflammable and explosive and can bring great potential safety hazard to experimental research easily.
As a preferred embodiment of the invention, the whole experimental section is made of an organic glass plate, so that the particle image velocimetry system can be conveniently adopted to track and visually shoot the details of the flow field in the process of impact jet flow.
As a preferred embodiment of the present invention, the dc power supply 4 is a plurality of sets of low-voltage large-current dc power supplies, so that the current does not change periodically, is more stable, can stably and continuously heat the preheating section, and keeps the power stable.
In a preferred embodiment of the present invention, the regenerative heat exchanger 6 is a double pipe heat exchanger, and thus, the heat exchanger is divided into two areas, i.e., an area inside and outside the pipe, in which cold water from the water tank flows outside the pipe, and an area inside and outside the pipe, in which high-temperature water flowing out from the experimental section flows inside the pipe, and the cold water is heated by the high-temperature water, thereby saving energy and preheating the cold water flowing into the experimental section.
As a preferred embodiment of the present invention, the preheating section 5 is a stainless steel serpentine coil structure disposed in parallel, and the experimental working medium is heated by using joule heat effect generated by energizing the resistance of the pipe wall, so that the flow of water in the pipe is more sufficient and the heating is more sufficient and uniform due to the serpentine coil structure.
The invention relates to an experimental method of a sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experimental system, which comprises the following steps:
preparation work: the invention adopts the particle image velocimetry technology, so that the experiment loop needs to be washed by clear water before the experiment to remove impurities in the loop and residual tracing particles of the particle image velocimetry. Deionized water and Particle Image Velocimetry (PIV) tracer particles are added into the first water tank 15, and the first plunger pump 12 is started to accelerate the mixing uniformity of the PIV tracer particles and the gas separation in the water. At this point, the preparation before the experiment was completed.
The experimental process comprises the following steps: in the experiment, water is adopted to replace liquid metal sodium as an experimental working medium, in order to ensure that the key phenomenon in the impact jet flow mixing under the water working medium is consistent with the liquid sodium working medium, the experiment adopts a partial similarity theory, neglects a similarity criterion with small influence on the flow problem, and ensures that the Reynolds number in the flow process and the dimensionless power frequency spectrum number in the mixing are similar under the premise of similar geometric conditions, so that the obtained experimental data has reference to the real sodium-cooled fast reactor, namely neglects the high thermal conductivity of the liquid metal sodium and the conventional experimental working medium water which are obviously different, and under the strong turbulent flow state of an outlet of a component head 1, the forced flow with high Reynolds number is mainly dominated in the energy exchange process, the influence of the thermal conductivity is reduced, and the structure of the component head 1 of the real sodium-cooled fast reactor is adopted, so that the initial condition, the boundary condition, the geometric condition and the similarity of the real sodium-cooled fast reactor are ensured; during the whole experiment, the deionized water machine 18 provides the deionized water to the water replenishing tank 19, and the first ball valve 20 and the second ball valve 22 are adjusted as required to replenish the deionized water to the first water tank 15 through the second plunger pump 21; deionized water is pumped into the first plunger pump 12 from a first water tank 15 after passing through a second stop valve 14 and a first pre-valve filter 13, and then is divided into two paths, wherein one path is a bypass system designed for regulating flow and pressure and consists of a cooler 16 and a first stop valve 17; the flow of the deionized water entering the experimental section is adjusted through a first stop valve 17 and a third stop valve 11 as required; in the first sub-channel, deionized water enters the regenerative heat exchanger 6 after passing through the mass flow meter 9, the regenerative heat exchanger 6 is in a sleeve pipe form, the deionized water absorbs heat of a high-temperature working medium from the experimental section, the deionized water is heated to a required temperature through the preheating section 5 and then enters the experimental section from the lower part, and the working medium in the remaining two sub-channels directly flows into the preheating section 5 after passing through the mass flow meter and is heated to the required temperature; the deionized water from the experimental section is fed again via the secondary cooling circuit into the water tank 15 via the recuperative heat exchanger 6 and the condenser 24.
As shown in figure 2, the head of the actual pool type sodium-cooled fast reactor component and the surrounding structure thereof are shown, 1 is the actual structure of the head of the sodium-cooled fast reactor component, a working medium from a sodium-cooled fast reactor core flows through the head 1 of the component and is injected into a sodium pool space 5-1 at the upper part of the sodium-cooled fast reactor in a jet flow mode, the working medium is surrounded by a first biological shield 1-1, a first shield 2-1, a second biological shield 3-1 and a second shield 4-1 which are biological shields around a hot pool, a central measuring column 6-1 and a control rod guide pipe 7-1 are arranged above the outlet of the head 1 of the component, and a measuring probe and a guide pipe 8-1 are arranged on the central measuring column.
While the invention has been described in further detail with reference to specific preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (9)
1. The utility model provides a sodium-cooled fast reactor core export impact jet stirs characteristic modeling experiment system which characterized in that: the system comprises an experiment main loop, an experiment section, a secondary cooling loop and a data measurement system;
the experiment main loop comprises a deionized water machine (18), a water supplementing tank (19), a first ball valve (20), a first water supplementing pump (21), a second ball valve (22), a first water tank (15), a first stop valve (17), a cooler (16), a second stop valve (14), a first pre-valve filter (13), a first plunger pump (12), a first pressure sensor (36), a second pressure sensor (35), a third stop valve (11), a fourth stop valve (10), a mass flow meter (9), a fifth stop valve (8), a sixth stop valve (23), a seventh stop valve (7), an outer pipe area of the regenerative heat exchanger (6), a preheating section (5) and a direct-current power supply (4); the experiment main loop is used for providing enough deionized cooling water for the whole experiment system, the water coming from the experiment main loop is divided into two paths, the first path is directly supplemented into the loop by external incoming water, and the other path is working medium water flowing through the experiment loop, and the working medium water flows out of the experiment section, is treated and is supplemented into the experiment main loop;
the first path of external incoming water is supplemented into an experimental main loop, firstly flows into a deionized water machine (18) to remove impurity ions, the back of the deionized water machine is connected with a water supplementing tank (19), the downstream of the water supplementing tank (19) is sequentially connected with a first ball valve (20), a first water supplementing pump (21) and a second ball valve (22), the downstream of the second ball valve (22) is connected with a first water tank (15), and the amount of the deionized water pumped into the first water tank (15) is controlled by adjusting the first ball valve (20) and the second ball valve (22) to maintain the water content in the first water tank (15); the downstream of the first water tank (15) is divided into two paths, one path is a bypass flow path designed for regulating flow and pressure, a first stop valve (17) and a cooler (16) on the bypass flow path are sequentially connected to the downstream of the first water tank (15), the other path is connected to the downstream of the first water tank, a second stop valve (14), a first pre-valve filter (13) and a first plunger pump (12) are sequentially connected to the other path of the downstream of the first water tank, a first pressure sensor (36) and a second pressure sensor (35) are respectively installed between the first pre-valve filter (13) and the first plunger pump (12) and at the downstream of the first plunger pump (12), and upstream and downstream pressures of the first plunger pump (12) are measured; a third stop valve (11) is connected downstream of the second pressure sensor (35), and a pipeline downstream of the cooler (16) on the bypass flow passage is connected between the second pressure sensor (35) and the third stop valve (11) again;
the downstream of the third stop valve (11) is provided with three parallel sub-channels, each sub-channel is sequentially provided with a fourth stop valve (10), a mass flow meter (9) and a fifth stop valve (8), the mass flow meter (9) measures the flow of the working medium entering the experimental section, and the fourth stop valve (10) and the fifth stop valve (8) in front of and behind the mass flow meter are adjusted according to the experimental requirements for flow adjustment; the difference is that two channels are connected to the downstream of the fifth stop valve (8) on one of the parallel sub-channels, one channel directly guides the working medium into the preheating section (5) through a sixth stop valve (23) connected with the downstream of the fifth stop valve (8), the other channel is connected with a seventh stop valve (7) behind the fifth stop valve (8), the rest working medium is guided into the outer tube area of the regenerative heat exchanger (6) to be heated by adjusting the seventh stop valve (7), the regenerative heat exchanger (6) is divided into the inner tube area and the outer tube area, and the outer tube area outlet of the regenerative heat exchanger (6) is connected with the preheating section (5); the downstream of a fifth stop valve (8) on the other two parallel sub-channels is directly connected with a preheating section (5); the direct current power supply (4) provides a heating energy source for the preheating section (5), and the working medium enters the experiment section after being heated to the required temperature in the preheating section (5);
the experimental section is connected with the preheating section (5), the experimental section is a plurality of groups of component heads (1) arranged in a downstream pipeline of the preheating section (5), the geometric design of the component heads (1) is based on the actual structure of the component heads at the outlet of the sodium-cooled fast reactor core, and the working medium enters the downstream pipeline through the component heads (1) in a jet flow mode and flows out of the experimental section;
after being sprayed out from the outlet of the assembly head (1) of the experimental section, the working medium enters the in-pipe area of the regenerative heat exchanger (6) at the downstream of the experimental section and is cooled by cold water outside the pipe; the downstream of the inner area of the regenerative heat exchanger (6) is connected with a condenser (24) and enters a secondary cooling loop; the inner area of the condenser (24) is also divided into an inner area and an outer area, the inner area is circulated with hot working medium from the regenerative heat exchanger (6), and the outer area is circulated with cold working medium from the second water tank (31);
the secondary cooling loop is a circulation loop and comprises a condenser (24), a cooling tower (32), a second water tank (31), an eighth stop valve (30), a cooling water pump (29), a third pre-valve filter (28), a second pre-valve filter (25), a ninth stop valve (26), a tenth stop valve (27) and a third ball valve (34); the main function of the cooling device is to cool the experimental working medium of the main loop of the experiment, provide sufficient cooling water working medium for the experimental section and ensure the long-time safe and stable operation of the loop; the secondary cooling loop specifically consists of: water from the experimental section passes through the pipe-in area of the condenser (24) and enters a cooling tower (32) connected with an outlet of the pipe-in area for further cooling, a second water tank (31), an eighth stop valve (30), a cooling water pump (29) and a third valve pre-filter (28) are sequentially connected to the downstream of the cooling tower, the downstream of the third valve pre-filter (28) is connected with an inlet of the pipe-out area of the condenser (24), an outlet of the pipe-out area of the condenser (24) is connected with a second valve pre-filter (25), a ninth stop valve (26) and a tenth stop valve (27) which are connected in parallel are connected to the downstream of the second valve pre-filter (25), a first water tank (15) is connected to the downstream of the ninth stop valve (26) and the tenth stop valve (27), working medium is supplemented into the first water tank, and therefore, a second incoming water of the experimental main loop is formed; in addition, a branch is divided between the downstream of the ninth stop valve (26) and the tenth stop valve (27) which are arranged in parallel and the first water tank (15), a third ball valve (34) is arranged on the branch, namely a sewage draining outlet, and after the experiment is carried out for a period of time, the experiment working medium is discharged through the third ball valve (34);
the data measurement system consists of a mass flowmeter (9), a quick-response thermocouple (33) and a particle image velocimetry system; the mass flow meter (9) is arranged on three sub-channels of the experiment main loop system, is positioned behind the fourth stop valve (10) and in front of the fifth stop valve (8) and is used for measuring the flow of the deionized water entering the experiment section; a plurality of groups of rapid reaction thermocouples (33) are arranged along the axial direction and the circumferential direction of the pipeline at the head part of the experimental section assembly, and the energy exchange characteristic in the jet flow process is reflected by monitoring the temperature field distribution information; the particle image velocimetry system comprises a sheet light source (2) and a high-speed camera (3), and the particle image velocimetry system is accessed into a data acquisition system of a computer for subsequent data acquisition and processing.
2. The sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system of claim 1 is characterized in that: the experiment section is that subassembly head (1) is the multiunit, can make up according to the experiment needs, carries out multiplex condition experiment simulation.
3. The sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system of claim 1 is characterized in that: in the experimental section, after the working medium is sprayed out from the component head (1), a strong turbulence state is presented, the component head (1) is based on the actual structure of the component head at the outlet of the real sodium-cooled fast reactor core, and the outlet structure is complex, so that the working medium state which is more attached to the outlet of the real fast reactor core can be obtained.
4. The sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system of claim 1 is characterized in that: the experimental working medium of the experimental system is water.
5. The sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system of claim 1 is characterized in that: the whole of experiment section adopts the organic glass board to make, is convenient for adopt particle image velocimetry system to trail and visual shooting impact efflux process flow field detail.
6. The sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system of claim 1 is characterized in that: the direct current power supply (4) is a plurality of groups of low-voltage large-current direct current power supplies.
7. The sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system of claim 1 is characterized in that: the regenerative heat exchanger (6) is a double-pipe heat exchanger.
8. The sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experiment system of claim 1 is characterized in that: the preheating section (5) is a stainless steel snake-shaped coil pipe structure which is arranged in parallel, and the experimental working medium is heated by using the joule heat effect generated by electrifying the resistance of the pipe wall.
9. The experimental method of the sodium-cooled fast reactor core outlet impact jet flow mixing characteristic modeling experimental system of any one of claims 1 to 8 is characterized in that: in the experiment, water is adopted to replace liquid metal sodium as an experimental working medium, in order to ensure that the key phenomenon in the impact jet flow mixing under the water working medium is consistent with the liquid sodium working medium, the experiment adopts a partial similarity theory, neglects a similarity criterion with small influence on the flow problem, and ensures that the Reynolds number in the flow process and the dimensionless power frequency spectrum number in the mixing are similar under the premise of similarity of the geometric conditions, so that the obtained experimental data has reference to the real sodium-cooled fast reactor, namely neglects the high thermal conductivity of the liquid metal sodium and the experimental working medium water which are obviously different, and under the strong turbulent flow state of an outlet of a component head (1), the forced flow with the high Reynolds number is mainly dominated in the energy exchange process, the influence of the thermal conductivity is reduced, and the structure of the component head (1) of the real sodium-cooled fast reactor is adopted, so that the initial condition, the boundary condition, the geometric condition and the similarity of the real sodium-cooled fast reactor are ensured; in the whole experiment process, the deionized water machine (18) supplies the deionized water to the water replenishing tank (19), and the first ball valve (20) and the second ball valve (22) are adjusted as required to replenish the deionized water to the first water tank (15) through the second plunger pump (21); deionized water is pumped into the two paths by a first plunger pump (12) after passing through a second stop valve (14) and a first pre-valve filter (13) from a first water tank (15), wherein one path is a bypass system designed for regulating flow and pressure and consists of a cooler (16) and a first stop valve (17); the flow of the deionized water entering the experimental section is adjusted through a first stop valve (17) and a third stop valve (11) according to requirements; in the first sub-channel, deionized water enters a regenerative heat exchanger (6) after passing through a mass flow meter (9), the regenerative heat exchanger (6) is in a sleeve pipe form, the deionized water absorbs heat of a high-temperature working medium coming out of the experimental section, the deionized water is heated to a required temperature through a preheating section (5) and then enters the experimental section from the lower part, and the working medium in the remaining two sub-channels directly flows into the preheating section (5) after passing through the mass flow meter and is heated to the required temperature; the deionized water from the experimental section is fed through the recuperative heat exchanger (6) and the condenser (24) via the secondary cooling circuit into the first water tank (15) again.
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