CN112687408A - Experimental model for sodium-cooled pool type fast reactor natural circulation experiment - Google Patents
Experimental model for sodium-cooled pool type fast reactor natural circulation experiment Download PDFInfo
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Abstract
The invention belongs to the technical field of reactor simulation experiments, and particularly relates to an experimental model for a sodium-cooled pool type fast reactor natural circulation experiment. The device comprises a cylindrical shell formed by sealing an upper end enclosure, an upper barrel, a lower barrel and a lower end enclosure which are sequentially connected from top to bottom, wherein the upper end enclosure and the upper barrel form a hot pool, the lower barrel and the lower end enclosure form a cold pool, a simulation reactor core positioned at the center of the shell, a central measuring column simulation piece positioned above the simulation reactor core, a large grid plate header simulation piece positioned below the simulation reactor core, a DR type heat exchanger simulation piece arranged in the hot pool, a DL type heat exchanger simulation piece arranged in the cold pool and an M type heat exchanger simulation piece arranged between the hot pool and the cold pool in a penetrating manner; the working medium in the cold pool can provide power through an external circulating pump to sequentially enter the large grid plate header simulation part and the simulation reactor core into the hot pool, and then returns to the cold pool again after heat exchange is carried out on the working medium from the M-type heat exchanger simulation part.
Description
Technical Field
The invention belongs to the technical field of reactor simulation experiments, and particularly relates to an experimental model for a sodium-cooled pool type fast reactor natural circulation experiment.
Background
After the sodium-cooled pool type fast reactor has an accident, whether the coolant of a primary loop system can establish natural circulation and whether the natural circulation capacity can take away decay heat generated by a reactor core is one of the problems which need to be considered in the design of the reactor. The accident waste heat removal system has complex thermodynamic and hydraulic phenomena. Meanwhile, the operational characteristics of the passive waste heat removal system under the working conditions that the power failure of the whole plant of the sodium-cooled pool type fast reactor occurs and the steam generator loses water supply accidents need to be searched, a design and analysis program model is evaluated, the design effectiveness and the reasonability of the passive waste heat removal system of the sodium-cooled pool type fast reactor are verified, and a basis is provided for the design and the safety analysis of the sodium-cooled pool type fast reactor. Through natural circulation experiments, the capacity of a primary circuit system for discharging the reactor core waste heat by means of natural circulation of a coolant under the working condition of a reactor accident is researched and verified, the flowing and temperature distribution conditions in a sodium pool under the working condition of waste heat discharge are comprehensively mastered, and the problem of uncertainty in design and analysis of the reactor accident waste heat discharge system is solved. When the accident waste heat discharge system is used for safety analysis, uncertainty exists, so that a primary loop natural circulation capability test research for design verification of the accident waste heat discharge system needs to be developed.
For an experiment medium, the sodium-cooled tank type fast reactor cooling medium is liquid sodium, and the sodium has very active chemical properties, so that the model processing difficulty is increased, the test technology in the experiment is complex, the price of a measuring instrument is high, the operation of the sodium experiment is complex, the safety risk is higher, and the experiment cost is higher. For the proportion of the experimental model, the larger the experimental model is, the higher the construction cost of the experimental model is, and along with the increase of the proportion, the construction cost is exponentially increased. If the experimental model is very small, the processing and experimental measurement of the experimental model can be very difficult. Therefore, the ratio of the experimental model needs to consider the aspects of cost performance, difficulty and the like. After the experimental model proportion is selected, the components in the experimental model need to be redesigned.
There is no document that satisfies the above-mentioned problems. The only few documents and data can not simulate the interaction of components in the actual reactor and can not complete the content of a loop natural circulation capability verification experiment.
Disclosure of Invention
In view of the above problems, the present invention aims to provide an experimental model for a sodium-cooled pool type fast reactor natural circulation experiment, which can truly simulate the situation of a primary loop system of a reactor, and ensure the accuracy and reliability of experimental measurement results.
In order to achieve the above purposes, the technical scheme adopted by the invention is an experimental model for a sodium-cooled tank type fast reactor natural circulation experiment, wherein the experimental model comprises a cylindrical shell formed by sealing an upper end enclosure, an upper cylinder, a lower cylinder and a lower end enclosure which are sequentially connected from top to bottom, the upper end enclosure and the upper cylinder form a hot tank, the lower cylinder and the lower end enclosure form a cold tank, a simulation reactor core positioned at the center of the shell, a central measuring column simulation piece positioned above the simulation reactor core, a large grid plate header simulation piece positioned below the simulation reactor core, a DR type heat exchanger simulation piece arranged in the hot tank, a DL type heat exchanger simulation piece arranged in the cold tank, and an M type heat exchanger simulation piece arranged between the hot tank and the cold tank in a penetrating manner; working media in the cold pool can sequentially enter the large grid plate header simulation piece and the simulation reactor core into the hot pool by providing power through an external circulating pump, and then return to the cold pool after exchanging heat from the M-type heat exchanger simulation piece; the M-type heat exchanger simulation piece is used for simulating heat discharge of an intermediate heat exchanger under the normal operation working condition of a reactor, the DR-type heat exchanger simulation piece is used for simulating heat discharge of an accident waste heat exchanger arranged in the hot pool under the accident working condition of the reactor, and the DL-type heat exchanger simulation piece is used for simulating heat discharge of the accident waste heat exchanger arranged in the cold pool under the accident working condition of the reactor.
Furthermore, a partition plate is arranged between the upper cylinder body and the lower cylinder body, the DL-type heat exchanger simulation piece is arranged in the partition cylinder, the bottom end of the partition cylinder is communicated with the partition plate, and the top end of the partition cylinder is positioned in the hot pool; the top plate of the large grid plate header simulation piece, the partition plate and the partition cylinder jointly form a partition boundary between the cold water tank and the hot water tank.
Furthermore, the simulated reactor core is composed of a plurality of electric heating elements, the total heating power is about 1000kW, the heating of the actual reactor core is simulated, and the working medium from the large grid plate header simulation part enters the simulated reactor core and is heated by the electric heating elements to raise the temperature.
The shielding simulation part comprises an annular upper shielding simulation part, an annular middle shielding simulation part and an annular lower shielding simulation part which are coaxially arranged from top to bottom in sequence; working medium from an outlet of the simulated reactor core passes through the clearance space of the upper shielding column simulator to reach an inlet of the M-class heat exchanger;
the upper shielding simulation piece, the middle shielding simulation piece and the lower shielding simulation piece are respectively composed of a plurality of shielding columns, the shielding columns are perpendicular to the upper surface of the simulated reactor core, and any three adjacent shielding columns are arranged in a triangular mode;
further comprising a radial shield simulator positioned between the lower shield simulator and the simulated core.
Further, in the present invention,
the hot pool system is characterized by further comprising a main pump simulation piece arranged in the hot pool, the bottom of the main pump simulation piece is arranged on the partition plate, the bottom of the main pump simulation piece is provided with a suction port simulation hole and a main pipeline simulation piece outlet pipe penetrating into the cold pool, and the top end of the main pipeline simulation piece outlet pipe positioned in the main pump simulation piece is provided with an impeller elevation simulation piece; a main pipeline simulation part inlet pipe is arranged at the bottom of the large grid plate header simulation part, working medium in the cold pool enters the main pump simulation part through the main pipeline simulation part outlet pipe, and enters the large grid plate header simulation part through the main pump simulation part inlet pipe;
working medium of the cold pool enters the main pump simulation piece through the suction port simulation hole, enters the outlet pipe of the main pipeline simulation piece through the impeller elevation simulation piece, and enters the inlet pipe of the main pipeline simulation piece under the action of an external circulating pump.
Furthermore, three layers of cylinders are arranged on the periphery of the main pump simulation piece in the circumferential direction and are divided into two coolant channels, wherein the inner side of each coolant channel is an uplink channel, and the outer side of each coolant channel is a downlink channel; the working medium of the cold pool enters the ascending channel through the opening at the lower part of the ascending channel, enters the descending channel at the outer side through the opening at the upper part of the ascending channel and returns to the cold pool; the ascending channel and the descending channel are used for simulating a pump supporting and cooling system in an actual reactor, taking away heat conducted by the heat pool and reducing the temperature of the main pump.
Furthermore, the large grid plate header simulation part is connected with the simulation reactor core, and the working medium from the main pipeline simulation part inlet pipe enters the large grid plate header simulation part and is distributed to each simulation assembly of the simulation reactor core above after being collected.
Furthermore, the central measuring column simulation piece is hung below the upper end enclosure, and a plurality of pipelines are arranged in the central measuring column simulation piece and serve as lead channels of temperature measuring points in the experiment model.
Further, the M-type heat exchanger simulation piece, the DR-type heat exchanger simulation piece and the DL-type heat exchanger simulation piece adopt a straight tube bundle to replace an actual spiral tube bundle, so that the resistance of corresponding parts of the reactor is simulated while the heat exchange capacity is met.
Further, the number of the M-type heat exchanger simulation pieces is 4; the number of the DR heat exchanger simulation pieces is 2; the number of the DL-type heat exchanger simulation pieces is 2; the number of the main pump simulation parts is 2.
The invention has the beneficial effects that:
1. in a practical reactor, heat generated by a reactor core is taken away by means of forced circulation flow of a main pump soaked in the reactor. Under the condition of accident shutdown, the main pump idles until the main pump stops; flow is generated by an external circulating pump in the experimental model, the main pump soaked in the cold pool is replaced to realize functions, and experimental cost and equipment research and development difficulty are greatly reduced.
2. The model uses the lower and upper openings (30 mm in diameter) of the upgoing channel 29 to simulate the resistance of the actual reactor pump support cooling system, greatly simplifying construction.
3. The large grid plate header simulation part 12 has the function of a small grid plate header pin and can simulate the resistance of the small grid plate header pin, so that the structure of the small grid plate header is reasonably simplified, and the experiment cost and the equipment research and development difficulty are reduced.
4. The larger the experimental model is, the higher the construction cost of the experimental model is, and along with the increase of the proportion, the construction cost is exponentially increased, so that the proportion is reduced and the capital investment is reduced; the cooling medium is water, sodium has very active chemical properties, so that the processing difficulty of the model is increased, the price of a measuring instrument is high, and the experiment cost is high, therefore, the experiment cost is reduced by selecting water as the medium.
5. And equipment support is provided for the development of a loop natural circulation capability verification experiment. The design requirements of experiments are met, and equipment guarantee is provided for verifying the reasonability of the design of the demonstration fast reactor passive waste heat removal system.
6. The difficulty of the processing technology is reduced, the sizes of various components are adjusted, the sizes of a reactor core simulation piece, a cooler simulation piece and the like are adjusted, and the difficulty of the processing technology of an experimental model is reduced.
Drawings
FIG. 1 is a schematic diagram of an experimental model for a sodium-cooled pool type fast reactor natural circulation experiment according to an embodiment of the present invention;
FIG. 2 is a top view of an experimental model for a sodium-cooled pool type fast reactor natural circulation experiment according to an embodiment of the present invention;
FIG. 3 is a sectional view taken along line A-A of FIG. 1;
FIG. 4 is a sectional view taken along line B-B of FIG. 2;
FIG. 5 is a cross-sectional view taken along line C-C of FIG. 2;
FIG. 6 is a cross-sectional view taken along line D-D of FIG. 2;
FIG. 7 is a sectional view taken along line E-E of FIG. 2;
fig. 8 is a schematic structural diagram of the class M heat exchanger simulating member 6, the class DR heat exchanger simulating member 7 and the class DL heat exchanger simulating member 8 according to the embodiment of the present invention;
fig. 9 is a schematic structural view of the main pump simulating assembly 18 according to the embodiment of the present invention;
FIG. 10 is a schematic view of a shielding simulator according to an embodiment of the present invention;
FIG. 11 is a schematic view of a central measurement column simulator 17 according to an embodiment of the present invention;
in the figure: 1-upper end enclosure, 2-lower end enclosure, 3-upper cylinder, 4-lower cylinder, 5-shell, 6-M type heat exchanger analog, 7-DR type heat exchanger analog, 8-DL type heat exchanger analog, 9-upper shielding analog, 10-middle shielding analog, 11-lower shielding analog, 12-large grid plate header analog, 13-analog reactor core, 14-partition plate, 15-radial shielding analog, 16-partition cylinder, 17-central measuring column analog, 18-main pump analog, 19-main pipe analog outlet pipe, 20-main pipe analog inlet pipe, 21-primary side inlet, 22-primary side outlet, 23-secondary side inlet, 24-secondary side outlet, 25-heat exchange pipe, 26-a pump support simulation piece, 27-an impeller elevation simulation piece, 28-a suction port simulation hole, 29-an ascending channel, 30-a descending channel, 31-a shielding column, 32-a pipeline and 33-a support lug.
Detailed Description
The invention is further described below with reference to the figures and examples.
As shown in figures 1 to 7, the experimental model for the sodium-cooled tank type fast reactor natural circulation experiment provided by the invention comprises an upper end enclosure 1, an upper cylinder 3, a lower cylinder 4 and a lower end enclosure 2 which are sequentially connected from top to bottom and are sealed to form a cylindrical shell 5 (the components form an outer boundary shell of the whole experimental model and play important roles of enveloping experimental components and working media, the model mainly has the external dimensions of 3500mm in diameter and 3600mm in height), the upper end enclosure 1 and the upper cylinder 3 form a hot tank, the lower cylinder 4 and the lower end enclosure 2 form a cold tank, a simulation reactor core 13 positioned at the center of the shell 5, a central measuring column simulation piece 17 positioned above the simulation reactor core 13, a large grid plate header simulation piece 12 positioned below the simulation reactor core 13, a DR type heat exchanger simulation piece 7 arranged in the hot tank, and a DL type heat exchanger simulation piece 8 arranged in the cold tank, a class-M heat exchanger simulator 6 disposed between the hot and cold ponds; working media in the cold pool can sequentially enter the large grid plate header simulation part 12 and the simulation reactor core 13 into the hot pool by providing power through an external circulating pump, and then return to the cold pool after exchanging heat from the M-type heat exchanger simulation part 6; the M-type heat exchanger simulation piece 6 is used for simulating heat discharge of an intermediate heat exchanger under the normal operation working condition of a reactor, the DR-type heat exchanger simulation piece 7 is used for simulating heat discharge of an accident waste heat exchanger arranged in a hot pool under the accident working condition of the reactor, and the DL-type heat exchanger simulation piece 8 is used for simulating heat discharge of the accident waste heat exchanger arranged in a cold pool under the accident working condition of the reactor.
A partition plate 14 is arranged between the upper barrel 3 and the lower barrel 4, the DL-type heat exchanger simulation piece 8 is arranged in a partition barrel 16, the bottom end of the partition barrel 16 is communicated with the partition plate 14, and the top end of the partition barrel 16 is positioned in a hot pool; the top plate of the large grid header simulation 12 and the divider plate 14 and the divider cylinder 16 together form the dividing boundary between the hot and cold tanks.
The simulated reactor core 13 has an outer diameter of about 900mm and a height of about 1500mm, and is composed of a plurality of (about 1500) electric heating elements, the outer diameter of each electric heating element is about 8mm, the length of each heating segment is about 400mm, the total heating power is about 1000kW, the heating of the actual reactor core is simulated, and the working medium from the large grid plate header simulation part 12 enters the simulated reactor core 13 and is heated by the electric heating elements.
The device also comprises shielding simulators which are arranged around the periphery of the central measuring column simulator 17 and the simulated reactor core 13, wherein the shielding simulators comprise an annular upper shielding simulator 9, a middle shielding simulator 10 and a lower shielding simulator 11 which are coaxially arranged from top to bottom in sequence; the working medium from the outlet of the simulated reactor core 13 needs to pass through the clearance space of the upper shielding simulator 9 to reach the inlet of the M-class heat exchanger;
the upper shielding simulator 9, the middle shielding simulator 10 and the lower shielding simulator 11 are respectively composed of a plurality of shielding columns 31, the shielding columns 31 are perpendicular to the upper surface of the simulated reactor core 13, any three adjacent shielding columns 31 are arranged in a triangular shape (as shown in fig. 10), the heights of the shielding columns 31 in the upper shielding simulator 9, the middle shielding simulator 10 and the lower shielding simulator 11 are respectively about 980mm,600mm and 630mm, the outer diameter of each shielding column 31 is about 35mm, the grid distance is 37mm, and the number of each layer of shielding columns 31 is about 420; the outer diameter of the shielding column 31 is reasonably adjusted in the model, so that the resistance of the shielding column gap in the actual reactor can be simulated;
a radial shield simulator 15 is also included between the lower shield simulator 11 and the simulated core 13.
The hot pool system also comprises a main pump simulation piece 18 arranged in the hot pool, the bottom of the main pump simulation piece 18 is arranged on the partition plate 14, the bottom of the main pump simulation piece 18 is provided with a suction port simulation hole 28 and a main pipeline simulation piece outlet pipe 19 penetrating into the cold pool, and the top end of the main pipeline simulation piece outlet pipe 19 positioned in the main pump simulation piece 18 is provided with an impeller elevation simulation piece 27; a main pipeline simulation inlet pipe 20 is arranged at the bottom of the large grid plate header simulation part 12, working medium in a cold pool enters the main pump simulation part 18 through a main pipeline simulation outlet pipe 19, and enters the large grid plate header simulation part 12 through the main pump simulation part 18 through the main pipeline simulation inlet pipe 20;
the main pump simulator 18 is constructed as shown in fig. 9, and the working fluid of the cold pool enters the main pump simulator 18 from the cold pool through the suction port simulator hole 28, passes through the impeller level simulator 27, enters the main pipe simulator outlet pipe 19, and enters the main pipe simulator inlet pipe 20 (ports B1 and B2 of the main pipe simulator inlet pipe 20) under the action of the external circulation pump.
The periphery of the main pump simulation part 18 is provided with three layers of cylinders which are divided into two coolant channels, wherein the inner side of each coolant channel is an uplink channel 29, and the outer side of each coolant channel is a downlink channel 30; the working medium of the cold pool enters the ascending channel 29 through the opening at the lower part of the ascending channel 29, enters the descending channel 30 at the outer side through the opening at the upper part of the ascending channel 29 and returns to the cold pool; the up channel 29 and the down channel 30 are used for simulating a pump support cooling system in an actual reactor, and take away heat conducted by a hot pool to reduce the temperature of a main pump.
As shown in fig. 5, during the experiment, the external circulation pump draws the working medium from the cold pool of the experimental model through the a port of the outlet pipe 19 of the main pipe simulator, after the working medium is pressurized by the pump, the working medium symmetrically enters the large grid plate header simulator 12 through the B1 and the B2 ports of the inlet pipe 20 of the main pipe simulator, and then enters the hot pool at the upper part of the simulated reactor core 13 after being heated by the simulated reactor core 13. After that, the cooling liquid passes through the internal gaps of the shielding columns 31 of the shielding simulation member in sequence, enters the upper inlet of the M-class heat exchanger simulation member 6, is cooled by the M-class heat exchanger 6, and then returns to the cold pool from the lower outlet of the M-class heat exchanger simulation member 6, so that forced circulation is completed.
The large grid plate header simulation part 12 is connected with the simulation reactor core 13, and working media from B1 and B2 interfaces of the main pipeline simulation part inlet pipe 20 enter the large grid plate header simulation part 12 to be collected and then redistributed to each simulation component of the simulation reactor core 13 above. In the experimental model, the large grid plate header simulation part 12 has the function of a small grid plate header pin at the same time, and can simulate the resistance of the small grid plate header pin, so that the structure of the small grid plate header is reasonably simplified, and the experimental cost and the research and development difficulty of equipment are reduced.
The central measuring column simulation piece 17 is hung below the upper end enclosure 1, the outer diameter is about 450mm, the height is about 1700mm, and a plurality of (30) pipelines 32 are arranged inside the central measuring column simulation piece 17 and serve as lead channels of temperature measuring points inside the experimental model (see fig. 11). Thermocouple leads inside the simulated core 13 can exit the model through the thermocouple leads to avoid excessive effects on the flow of fluid inside the hot core.
After the model is scaled down, the original tube bundle structure cannot be guaranteed, and when the simulation piece is designed, the M-type heat exchanger simulation piece 6, the DR-type heat exchanger simulation piece 7 and the DL-type heat exchanger simulation piece 8 adopt a straight tube bundle to replace an actual spiral tube bundle form (see fig. 8), so that the resistance of corresponding parts of the reactor is simulated while the heat exchange capacity is met.
Outer diameter of the class M heat exchanger dummy 6: 580mm, height about: 2500mm, the number of heat exchange tubes 25 is about: 6700 the heat exchange power is about 260kW, and the number is 4; outside diameter of DR heat exchanger dummy 7: 200mm, height about: 1800mm, the number of heat exchange tubes 25 is about: 750, the heat exchange power is about 25kW, and the number is 2; outer diameter of DL-class heat exchanger dummy 8: 200mm, height about: 1900mm, the number of heat exchange tubes 25 is about: 750, the heat exchange power is about 25kW, and the number is 2; the number of the main pump simulating assemblies 18 is 2. The M-type heat exchanger simulating piece 6, the DR-type heat exchanger simulating piece 7, the DL-type heat exchanger simulating piece 8 and the main pump simulating piece 18 are arranged to be approximately symmetrically distributed.
The practical application of the invention is as follows:
the experiment model for the sodium-cooled pool type fast reactor natural circulation experiment is used for simulating the normal operation of the reactor, and the external circulating pump is started firstly. The external circulating pump draws working medium from the cold pool of the experimental model through the A interface of the main pipeline simulation part outlet pipe 19, after the pump is pressurized, symmetrically enters the large grid plate header simulation part 12 through the B1 and the B2 ports of the main pipeline simulation part inlet pipe 20, and then enters the hot pool space at the upper part of the simulation reactor core 13 after being heated through the simulation reactor core 13. And then, the water enters an upper inlet of the M-type heat exchanger simulation piece 6 after sequentially passing through internal gaps (an upper shielding simulation piece 9, a middle shielding simulation piece 10 and a lower shielding simulation piece 11) of each shielding column simulation piece, and returns to a cold pool from a lower outlet of the M-type heat exchanger simulation piece 6 after being cooled by the M-type heat exchanger simulation piece 6 to form circulating flow so as to establish flow and temperature distribution in a loop system of the reactor.
After the simulated reactor accident occurs, the flow of the working medium entering the ports B1 and B2 of the main pipeline simulation part inlet pipe 20 is gradually reduced to zero through the frequency conversion control of the external circulating pump. The natural circulation flow established inside the model is observed and the outlet temperature of the simulated core 13 is simulated.
The device according to the present invention is not limited to the embodiments described in the specific embodiments, and those skilled in the art can derive other embodiments according to the technical solutions of the present invention, and also belong to the technical innovation scope of the present invention.
Claims (10)
1. An experimental model for a sodium-cooled pool type fast reactor natural circulation experiment is characterized in that: the device comprises a cylindrical shell (5) formed by sealing an upper end enclosure (1), an upper cylinder body (3), a lower cylinder body (4) and a lower end enclosure (2) which are sequentially connected from top to bottom, wherein the upper end enclosure (1) and the upper cylinder body (3) form a hot pool, the lower cylinder body (4) and the lower end enclosure (2) form a cold pool, a simulation reactor core (13) positioned at the center of the shell (5), a central measuring column simulation piece (17) positioned above the simulation reactor core (13), a large grid plate header simulation piece (12) positioned below the simulation reactor core (13), a DR type heat exchanger simulation piece (7) arranged in the hot pool, a DL type heat exchanger simulation piece (8) arranged in the cold pool, and an M type heat exchanger simulation piece (6) arranged between the hot pool and the cold pool in a penetrating manner; working media in the cold pool can sequentially enter the large grid plate header simulation piece (12) and the simulation reactor core (13) into the hot pool by providing power through an external circulating pump, and then return to the cold pool after exchanging heat from the M-type heat exchanger simulation piece (6); the heat exchanger simulating device comprises an M-type heat exchanger simulating piece (6), a DR-type heat exchanger simulating piece (7) and a DL-type heat exchanger simulating piece (8), wherein the M-type heat exchanger simulating piece is used for simulating heat discharge of an intermediate heat exchanger under the normal operation working condition of a reactor, the DR-type heat exchanger simulating piece is used for simulating heat discharge of an accident waste heat exchanger in a hot pool under the accident working condition of the reactor, and the DL-type heat exchanger simulating piece is used for simulating heat discharge of the accident waste heat exchanger in a cold pool under the accident working condition of the.
2. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 1, wherein: a partition plate (14) is arranged between the upper barrel body (3) and the lower barrel body (4), the DL-type heat exchanger simulation piece (8) is arranged in a partition barrel (16), the bottom end of the partition barrel (16) is communicated with the partition plate (14), and the top end of the partition barrel (16) is positioned in the hot pool; the top plate of the large grid plate header simulation piece (12), the partition plate (14) and the partition cylinder (16) jointly form a partition boundary between the cold water and the hot water.
3. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 2, wherein: the simulated reactor core (13) is composed of a plurality of electric heating elements, the heating of the actual reactor core is simulated, and the working medium from the large grid plate header simulation part (12) enters the simulated reactor core (13) and is heated by the electric heating elements.
4. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 3, wherein: the device also comprises shielding simulators which are arranged around the central measuring column simulator (17) and the periphery of the simulated reactor core (13), wherein the shielding simulators comprise an annular upper shielding simulator (9), a middle shielding simulator (10) and a lower shielding simulator (11) which are coaxially arranged from top to bottom in sequence; working medium from the outlet of the simulated core (13) passes through the clearance space of the upper shielding column simulator (9) to reach the inlet of the M-class heat exchanger;
the upper shielding simulation piece (9), the middle shielding simulation piece (10) and the lower shielding simulation piece (11) are respectively composed of a plurality of shielding columns (31), the shielding columns (31) are perpendicular to the upper surface of the simulated reactor core (13), and any three mutually adjacent shielding columns (31) are arranged in a triangular shape;
further comprising a radial shielding dummy (15) located between the lower shielding dummy (11) and the simulated core (13).
5. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 4, wherein: the hot pool system is characterized by further comprising a main pump simulation piece (18) arranged in the hot pool, the bottom of the main pump simulation piece (18) is arranged on the partition plate (14), a suction port simulation hole (28) and a main pipe simulation piece outlet pipe (19) penetrating into the cold pool are formed in the bottom of the main pump simulation piece (18), and an impeller elevation simulation piece (27) is arranged at the top end of the main pipe simulation piece outlet pipe (19) located inside the main pump simulation piece (18); a main pipeline simulation inlet pipe (20) is arranged at the bottom of the large grid plate header simulation piece (12), working medium in the cold pool enters the main pump simulation piece (18) through the main pipeline simulation outlet pipe (19), and enters the large grid plate header simulation piece (12) through the main pipeline simulation inlet pipe (20) by the main pump simulation piece (18);
working medium of the cold pool enters the main pump simulation piece (18) from the cold pool through the suction port simulation hole (28), enters the main pipeline simulation piece outlet pipe (19) through the impeller elevation simulation piece (27), and enters the main pipeline simulation piece inlet pipe (20) under the action of an external circulating pump.
6. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 5, wherein: the periphery of the main pump simulation piece (18) in the circumferential direction is provided with three layers of cylinders which are divided into two coolant channels, the inner side of each coolant channel is an ascending channel (29), and the outer side of each coolant channel is a descending channel (30); the working medium of the cold pool enters the ascending channel (29) through an opening at the lower part of the ascending channel (29), enters the descending channel (30) at the outer side through an opening at the upper part of the ascending channel (29), and returns to the cold pool; the ascending channel (29) and the descending channel (30) are used for simulating a pump support cooling system in an actual reactor, and heat conducted by the hot pool is taken away, so that the temperature of a main pump is reduced.
7. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 6, wherein: the large grid plate header simulation part (12) is connected with the simulation reactor core (13), and working medium from the main pipeline simulation part inlet pipe (20) enters the large grid plate header simulation part (12) to be collected and then redistributed to each simulation assembly of the simulation reactor core (13) above.
8. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 1, wherein: the central measurement column simulation piece (17) is hung below the upper end enclosure (1), and a plurality of pipelines (32) are arranged in the central measurement column simulation piece (17) and serve as lead channels of temperature measurement points in the experimental model.
9. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 1, wherein: the M-type heat exchanger simulation piece (6), the DR-type heat exchanger simulation piece (7) and the DL-type heat exchanger simulation piece (8) adopt a straight tube bundle to replace an actual spiral tube bundle form, and the resistance of corresponding parts of a reactor is simulated while the heat exchange capacity is met.
10. The experimental model for the sodium-cooled pool type fast reactor natural circulation experiment as claimed in claim 5, wherein: the number of the M-type heat exchanger simulation pieces (6) is 4; the number of the DR heat exchanger simulation pieces (7) is 2; the number of the DL-type heat exchanger simulation pieces (8) is 2; the number of the main pump simulation parts (18) is 2.
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| CN114220571A (en) * | 2021-10-28 | 2022-03-22 | 中国原子能科学研究院 | Natural circulation waste heat discharge system and fast neutron reactor |
| CN114220571B (en) * | 2021-10-28 | 2024-09-06 | 中国原子能科学研究院 | Natural circulation waste heat discharging system and fast neutron reactor |
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| CN112687408B (en) | 2023-05-23 |
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