CN117637200A - Passive cooling system and method for high-temperature gas cooled reactor and steam generator - Google Patents
Passive cooling system and method for high-temperature gas cooled reactor and steam generator Download PDFInfo
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- CN117637200A CN117637200A CN202311362569.8A CN202311362569A CN117637200A CN 117637200 A CN117637200 A CN 117637200A CN 202311362569 A CN202311362569 A CN 202311362569A CN 117637200 A CN117637200 A CN 117637200A
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- 238000001816 cooling Methods 0.000 title claims abstract description 85
- 238000000034 method Methods 0.000 title claims abstract description 23
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 80
- 239000007789 gas Substances 0.000 claims description 22
- 239000001307 helium Substances 0.000 claims description 19
- 229910052734 helium Inorganic materials 0.000 claims description 19
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 19
- 239000007788 liquid Substances 0.000 claims description 9
- 239000000203 mixture Substances 0.000 claims description 9
- 239000002699 waste material Substances 0.000 claims description 9
- 239000002918 waste heat Substances 0.000 claims description 6
- 230000005484 gravity Effects 0.000 claims description 4
- 230000001105 regulatory effect Effects 0.000 claims description 4
- 238000010521 absorption reaction Methods 0.000 claims description 3
- 230000002285 radioactive effect Effects 0.000 description 6
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000006837 decompression Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
- 230000001960 triggered effect Effects 0.000 description 1
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a high-temperature gas cooled reactor and a steam generator passive cooling system and a method, wherein the shell side of the steam generator is communicated with the reactor, and the pipe side outlet of the steam generator is divided into two paths, wherein one path is communicated with the inlet of a steam header pipe through a first electric valve; the other path is communicated with the inlet of the check valve through a heat exchanger in the first pneumatic valve and the air cooling tower; the invention can ensure the safety and stability of the reactor and the steam generator under the emergency shutdown working condition of the high-temperature gas cooled reactor.
Description
Technical Field
The invention belongs to the technical field of nuclear power safety facilities, and relates to a passive cooling system and a passive cooling method for a high-temperature gas cooled reactor and a steam generator.
Background
When the high-temperature gas cooled reactor is deviated from the normal operation working conditions such as the burst of a heat transfer tube of a steam generator, the decompression or the overtemperature of a loop coolant, etc., the emergency shutdown is triggered. The emergency shutdown is followed by cooling the reactor and steam generator to release the remaining heat from the reactor to a shutdown condition. The prior design scheme is as follows: after the emergency shutdown, the steam-water mixture at the side of the steam generator pipe starts to be discharged, steam is discharged to the gas collecting container body, and high-temperature water is discharged to the discharge tank pre-stored with cold water for mixed cooling. After the discharge is completed, the water supply pump is driven and small-flow water is injected into the tube side of the steam generator to cool the heat transfer tube of the steam generator and take away heat released by the reactor core. This cooling solution, although capable of guaranteeing the core safety, has at least the following drawbacks: 1. when the heat transfer pipe of the steam generator is broken, the discharged steam-water mixture has radioactivity, radioactive steam needs to be purified, and radioactive feed water is mixed with feed water in a discharge tank, so that the generation of radioactive products is further increased; 2. once extreme abnormal accidents such as power failure of the whole plant occur, the water supply pump and the electric valve device thereof cannot be effectively put into operation, the heat of the reactor core can be led out only by natural cooling, the problems of long time and poor cooling effect exist, and the safe and stable operation of the unit is not facilitated.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provide a passive cooling system and a passive cooling method for a high-temperature gas-cooled reactor and a steam generator, which can ensure the safety and the stability of the reactor and the steam generator under the emergency shutdown working condition of the high-temperature gas-cooled reactor.
In order to achieve the aim, the invention discloses a high-temperature gas-cooled reactor and a steam generator passive cooling system, which comprises a steam generator, a reactor, a first electric valve, a steam header, a first pneumatic valve, an air cooling tower, a check valve, a water supply header, a water supply pump, a second electric valve, a second pneumatic valve, a discharge tank, a third pneumatic valve, a fifth pneumatic valve and a third electric valve;
the shell side of the steam generator is communicated with the reactor, and the outlet of the tube side of the steam generator is divided into two paths, wherein one path is communicated with the inlet of the steam header through a first electric valve; the other path is communicated with the inlet of the check valve through a heat exchanger in the first pneumatic valve and the air cooling tower;
the outlet of the water supply header pipe is communicated with the inlet of the second electric valve through the water supply pump, the outlet of the second electric valve and the outlet of the check valve are divided into two paths after being connected through a pipeline, one path is communicated with the inlet of the water-cooled wall header pipe in the discharge tank through the second pneumatic valve, the outlet of the water-cooled wall header pipe in the discharge tank is communicated with the pipe side inlet of the steam generator through the third pneumatic valve, the other path is communicated with the inlet of the third electric valve and the pipe side inlet of the steam generator through the fifth pneumatic valve, and the outlet of the third electric valve is communicated with the tank body of the discharge tank.
The outlet of the reactor is communicated with the shell side inlet of the steam generator, and the shell side outlet of the steam generator is communicated with the inlet of the reactor through a main helium fan.
The outlet of the water-cooled wall header in the discharge tank is communicated with the waste liquid storage tank through a fourth pneumatic valve.
An air inlet shutter and an air outlet shutter are arranged on the air cooling tower.
The bottom elevation position of the heat exchanger is higher than the top elevation position of the steam generator.
The passive cooling method for the high-temperature gas cooled reactor and the steam generator comprises the steps of passive cooling under the working condition of steam generator heat transfer pipe rupture accident and passive cooling under the working condition of whole plant power failure accident operation.
The specific process of non-kinetic energy cooling under the working condition of the steam generator heat transfer tube rupture accident is as follows:
when a heat transfer pipe of a steam generator is broken, a reactor is in emergency shutdown, a first electric valve, a second electric valve and a fifth pneumatic valve are closed, the first pneumatic valve and a third electric valve are opened, a steam-water mixture at the pipe side of the steam generator starts to be discharged, steam is discharged into a heat exchanger in an air cooling tower through the first pneumatic valve, water is discharged into a discharge tank through the third electric valve, and after water is discharged, the third electric valve is closed;
opening a second pneumatic valve and a fourth pneumatic valve, opening an air inlet shutter and an air outlet shutter, forming a natural circulation cold source in the air cooling tower, condensing steam at the tube side of the heat exchanger and cold air at the shell side into condensed water after heat exchange, enabling the condensed water to enter a water-cooled wall header of a discharge tank through a check valve and the second pneumatic valve, enabling high-temperature hot water output by the discharge tank to enter a waste liquid storage tank through the fourth pneumatic valve, and establishing an passive circulation cooling process until waste heat in the reactor and the steam generator is led out.
The specific process of non-kinetic energy cooling under the operation condition of the whole plant power failure accident is as follows:
when an extreme accident such as whole plant outage or loss of an external alternating current power supply occurs, the reactor is suddenly shut down, the first electric valve and the second electric valve are quickly closed, the third electric valve is opened in a power failure mode, the fifth electric valve is closed, the first electric valve is opened, a steam-water mixture in the pipe side of the steam generator starts to be discharged, steam is discharged into the heat exchanger through the first electric valve, water is discharged into the tank body through the third electric valve, and the third electric valve is closed after water is discharged;
the second pneumatic valve and the fourth pneumatic valve are opened, the air inlet shutter and the air outlet shutter are opened, a natural circulation cold source is formed in the air cooling tower, steam on the tube side of the heat exchanger exchanges heat with cold air on the shell side and then is condensed into condensed water, the opening of the air inlet shutter and the opening of the air outlet shutter are adjusted, the flow of the condensed water are controlled, the condensed water enters the heat of high-temperature hot water in the absorption tank body in the water-cooled wall header pipe through the check valve and the second pneumatic valve, the opening of the second pneumatic valve is adjusted, the temperature of the condensed water meets the cooling temperature allowed by the heat transfer tube in the steam generator, the condensed water flows into the tube side of the steam generator by means of temperature difference and gravity difference, the heat of the core waste heat entering the shell side of the steam generator from the reactor is absorbed and then becomes steam, and the steam is continuously enters the air cooling tower to release heat, so that an passive cooling process is formed, and the cooling process is completed.
The invention has the following beneficial effects:
according to the high-temperature gas-cooled reactor and steam generator passive cooling system and method, when the high-temperature gas-cooled reactor and steam generator passive cooling system and method are specifically operated, the high-temperature gas-cooled reactor and steam generator passive cooling is realized by means of temperature difference and natural circulation cold sources formed in the air cooling tower, and specifically, when a steam generator heat transfer pipe is broken, the high-temperature steam-water mixture with radioactivity in the steam generator is rapidly cooled and recycled through the passive cooling system without depending on an external power source, so that the safety of the reactor and the steam generator is ensured; when the emergency shutdown accident of the reactor caused by the power failure of the whole plant occurs, the heat in the reactor and the steam generator is carried out without depending on an external power source, the flow of condensed water is controlled by adjusting the opening of an air inlet shutter and an air outlet shutter in the cooling process, the temperature entering the steam generator is controlled by adjusting the opening of a pneumatic valve, the problem of larger thermal stress caused by larger temperature difference in the cooling process of a heat transfer pipe is effectively avoided, and compared with the mixed cooling scheme in the original design, the production of radioactive products can be effectively reduced, and the treatment cost is reduced; meanwhile, the radioactive steam is condensed and recycled to the waste liquid storage tank, so that the treatment difficulty of the radioactive steam is reduced. Finally, the invention adopts the pneumatic valve control, and under the extreme operation accident working conditions such as power failure of the whole plant, the system can still be put into operation by means of temperature difference and gravity difference, so that the safety of the unit is ensured.
Drawings
Fig. 1 is a schematic structural view of the present invention.
Wherein 1 is a reactor, 2 is a main helium fan, 3 is a steam generator, 4 is an air cooling tower, 5 is a steam header, 6 is a water supply header, 7 is a water supply pump, 8 is a discharge tank, 9 is a waste liquid storage tank, 10 is a first pneumatic valve, 11 is a first electric valve, 12 is a check valve, 13 is a second electric valve, 14 is a second pneumatic valve, 15 is a third electric valve, 16 is a third pneumatic valve, 17 is a fourth pneumatic valve, 18 is a fifth pneumatic valve, 4-1 is a heat exchanger, 4-2 is an air inlet shutter, 4-3 is an air outlet shutter, 8-2 is a tank body, and 8-1 is a water cooling wall header.
Detailed Description
In order to make the present invention better understood by those skilled in the art, the following description will clearly and completely describe the technical solutions in the embodiments of the present invention with reference to the accompanying drawings, and it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments, but not intended to limit the scope of the present disclosure. In addition, in the following description, descriptions of well-known structures and techniques are omitted so as not to unnecessarily obscure the concepts of the present disclosure. All other embodiments, which can be made by those skilled in the art based on the embodiments of the present invention without making any inventive effort, shall fall within the scope of the present invention.
In the accompanying drawings, there is shown a schematic structural diagram in accordance with a disclosed embodiment of the invention. The figures are not drawn to scale, wherein certain details are exaggerated for clarity of presentation and may have been omitted. The shapes of the various regions, layers and their relative sizes, positional relationships shown in the drawings are merely exemplary, may in practice deviate due to manufacturing tolerances or technical limitations, and one skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions as actually required.
Referring to fig. 1, the passive cooling system for a high temperature gas cooled reactor and a steam generator according to the present invention comprises a reactor 1, a main helium blower 2, a steam generator 3, an air cooling tower 4, a steam header 5, a water supply header 6, a water supply pump 7, a discharge tank 8, a waste liquid storage tank 9, a first pneumatic valve 10, a first electric valve 11, a check valve 12, a second electric valve 13, a second pneumatic valve 14, a third electric valve 15, a third pneumatic valve 16, a fourth pneumatic valve 17 and a fifth pneumatic valve 18;
the outlet of the reactor 1 is communicated with a shell side inlet of the steam generator 3, the shell side outlet of the steam generator 3 is communicated with an inlet of the main helium fan 2, and an outlet of the main helium fan 2 is communicated with the inlet of the reactor 1 to form a high-temperature gas cooled reactor loop; the pipe side outlet of the steam generator 3 is divided into two paths, wherein one path is communicated with the inlet of the steam header 5 through a first electric valve 11; the other path is communicated with a pipe side inlet of a heat exchanger 4-1 in the air cooling tower 4 through a first pneumatic valve 10, and a pipe side outlet of the heat exchanger 4-1 is communicated with an inlet of a check valve 12;
the outlet of the water supply header 6 is communicated with the inlet of the water supply pump 7, the outlet of the water supply pump 7 is communicated with the inlet of the second electric valve 13, the outlet of the second electric valve 13 and the outlet of the check valve 12 are divided into two paths after being connected by a pipeline, one path is communicated with the inlet of the second pneumatic valve 14, the outlet of the second pneumatic valve 14 is communicated with the inlet of the water-cooled wall header 8-1 in the discharge tank 8, the outlet of the water-cooled wall header 8-1 in the discharge tank 8 is communicated with the inlet of the third pneumatic valve 16, the outlet of the third pneumatic valve 16 is communicated with the pipe side inlet of the steam generator 3, the other path is communicated with the inlet of the fifth pneumatic valve 18, the outlet of the fifth pneumatic valve 18 is communicated with the inlet of the third electric valve 15 and the pipe side inlet of the steam generator 3, and the outlet of the third electric valve 15 is communicated with the tank 8-2 of the discharge tank 8;
the outlet of the water-cooled wall header 8-1 in the discharge tank 8 is communicated with the waste liquid storage tank 9 via a fourth pneumatic valve 17.
The air cooling tower 4 is provided with an air inlet shutter 4-2 and an air outlet shutter 4-3, the air cooling tower 4 is placed at a high position, the bottom elevation position of the heat exchanger 4-1 is higher than the top elevation position of the steam generator 3, and the discharge tank 8 comprises a tank body 8-2 and a water-cooled wall header 8-1 arranged on the surface of the tank body 8-2.
Referring to fig. 1, the passive cooling method for the high-temperature gas-cooled reactor and the steam generator according to the invention comprises the following steps:
1. normal operation condition of the unit:
in the initial state of the system, the reactor 1, the main helium blower 2 and the feed pump 7 are not operated, the first electric valve 11, the second electric valve 13 and the fifth pneumatic valve 18 are opened, and the first pneumatic valve 10, the second pneumatic valve 14, the third pneumatic valve 16, the third electric valve 15 and the fourth pneumatic valve 17 are closed.
1) The reactor 1 is normally started, a main helium blower 2 is started, cold helium gas is conveyed to the reactor core of the reactor 1 through the main helium blower 2 to absorb heat to become hot helium gas, the hot helium gas enters the shell side of the steam generator 3 to exchange heat with pipe side water supply to become cold helium gas, and the cold helium gas returns to the reactor core of the reactor 1 to absorb heat to form a circulation loop of the reactor 1;
2) The feed pump 7 is started, the feed water output by the feed water header 6 is delivered to the tube side of the steam generator 3 through the feed water pump 7, the heat of the hot helium gas in the steam generator 3 is absorbed and then becomes steam, and the generated steam enters the steam header 5.
2. Normal reactor 1 shutdown condition:
system initial state: the reactor 1, the main helium blower 2 and the feed pump 7 are operated, the first electric valve 11, the second electric valve 13 and the fifth pneumatic valve 18 are opened, and the first pneumatic valve 10, the second pneumatic valve 14, the third pneumatic valve 16, the third electric valve 15 and the fourth pneumatic valve 17 are closed.
The reactor 1 is normally stopped, the main helium blower 2 is stopped, the water supply pump 7 is stopped, the first electric valve 11 and the second electric valve 13 are closed, the first air valve 10 is opened, steam output by the pipe side of the steam generator 3 enters the pipe side of the heat exchanger 4-1 in the air cooling tower 4 through the first air valve 10, the air inlet louver 4-2 and the air outlet louver 4-3 are opened, a natural circulation cold source is formed in the air cooling tower 4, the steam on the pipe side of the heat exchanger 4-1 exchanges heat with cold air on the shell side and is condensed into condensed water, the condensed water enters the pipe side of the steam generator 3 through the check valve 12, the core waste heat entering the shell side of the steam generator 3 from the reactor 1 is absorbed and then becomes steam, and the steam continues to enter the air cooling tower 4 for heat release, so that an passive cooling process is formed, until the cooling process of the reactor 1 and the steam generator 3 is completed, and the reactor 1 enters a cold stop state.
3. Steam generator 3 heat transfer tube rupture accident conditions:
system initial state: the reactor 1, the main helium blower 2 and the feed pump 7 are operated, the first electric valve 11, the second electric valve 13 and the fifth pneumatic valve 18 are opened, and the first pneumatic valve 10, the second pneumatic valve 14, the third pneumatic valve 16, the third electric valve 15 and the fourth pneumatic valve 17 are closed.
When the heat transfer pipe of the steam generator 3 is broken, the reactor 1 is in emergency shutdown, the first electric valve 11, the second electric valve 13 and the fifth pneumatic valve 18 are closed, the first pneumatic valve 10 and the third electric valve 15 are opened, the steam-water mixture at the pipe side of the steam generator 3 starts to be discharged, steam is discharged into the pipe side of the heat exchanger 4-1 in the air cooling tower 4 through the first pneumatic valve 10, the water supply is discharged into the discharge tank 8 through the third electric valve 15, and after the water supply is discharged, the third electric valve 15 is closed.
The second pneumatic valve 14 and the fourth pneumatic valve 17 are opened, the air inlet shutter 4-2 and the air outlet shutter 4-3 are opened, a natural circulation cold source is formed in the air cooling tower 4, steam at the tube side of the heat exchanger 4-1 exchanges heat with cold air at the shell side and is condensed into condensed water, the condensed water enters the water-cooled wall header 8-1 of the discharge tank 8 through the check valve 12 and the second pneumatic valve 14, high-temperature hot water output by the discharge tank 8 enters the waste liquid storage tank 9 through the fourth pneumatic valve 17, and an passive circulation cooling process is established until waste heat in the reactor 1 and the steam generator 3 is led out.
4. Operation conditions of power failure accidents of the whole plant:
system initial state: the reactor 1, the main helium blower 2 and the feed pump 7 are operated, the first electric valve 11, the second electric valve 13 and the fifth pneumatic valve 18 are opened, and the first pneumatic valve 10, the second pneumatic valve 14, the third pneumatic valve 16, the third electric valve 15 and the fourth pneumatic valve 17 are closed.
When an extreme accident such as whole plant outage or loss of an off-plant alternating current power supply occurs, the reactor 1 is suddenly shut down, the first electric valve 11 and the second electric valve 13 are quickly closed, the third electric valve 15 is opened in a power failure mode, the fifth pneumatic valve 18 is closed, the first pneumatic valve 10 is opened, a steam-water mixture in the pipe side of the steam generator 3 begins to be discharged, steam is discharged into the pipe side of the heat exchanger 4-1 through the first pneumatic valve 10, and water is discharged into the tank body 8-2 through the third electric valve 15; after the water supply is discharged, the third motor valve 15 is closed.
The second pneumatic valve 14 and the fourth pneumatic valve 17 are opened, the air inlet louver 4-2 and the air outlet louver 4-3 are opened, a natural circulation cold source is formed in the air cooling tower 4, steam at the tube side of the heat exchanger 4-1 exchanges heat with cold air at the shell side and is condensed into condensed water, the opening of the air inlet louver 4-2 and the opening of the air outlet louver 4-3 are regulated, the flow rate of the condensed water is controlled, the condensed water enters the heat of high-temperature hot water in the absorption tank 8-2 in the water-cooling wall header 8-1 through the check valve 12 and the second pneumatic valve 14, the opening of the second pneumatic valve 14 is regulated, the condensed water temperature meets the cooling temperature allowed by the heat transfer tube in the steam generator 3, the condensed water flows into the tube side of the steam generator 3 by means of temperature difference and gravity difference, the residual heat entering the shell side of the steam generator 3 from the reactor 1 is absorbed and then becomes steam, the condensed water continuously enters the air cooling tower 4 for heat release, and a passive cooling process is formed until the reactor 1 and the steam generator 3 completes the cooling process.
Finally, it should be noted that: the above embodiments are only for illustrating the technical aspects of the present invention and not for limiting the same, and although the present invention has been described in detail with reference to the above embodiments, it should be understood by those of ordinary skill in the art that: modifications and equivalents may be made to the specific embodiments of the invention without departing from the spirit and scope of the invention, which is intended to be covered by the claims.
Claims (8)
1. The passive cooling system for the high-temperature gas cooled reactor and the steam generator is characterized by comprising a steam generator (3), the reactor (1), a first electric valve (11), a steam header (5), a first pneumatic valve (10), an air cooling tower (4), a check valve (12), a water supply header (6), a water supply pump (7), a second electric valve (13), a second pneumatic valve (14), a discharge tank (8), a third pneumatic valve (16), a fifth pneumatic valve (18) and a third electric valve (15);
the shell side of the steam generator (3) is communicated with the reactor (1), and the pipe side outlet of the steam generator (3) is divided into two paths, wherein one path is communicated with the inlet of the steam header (5) through a first electric valve (11); the other path is communicated with the inlet of a check valve (12) through a first pneumatic valve (10) and a heat exchanger (4-1) in the air cooling tower (4);
the outlet of the water supply header (6) is communicated with the inlet of a second electric valve (13) through a water supply pump (7), the outlet of the second electric valve (13) and the outlet of a check valve (12) are divided into two paths after being connected by a pipeline, one path is communicated with the inlet of a water-cooled wall header (8-1) in a discharge tank (8) through a second pneumatic valve (14), the outlet of the water-cooled wall header (8-1) in the discharge tank (8) is communicated with the pipe side inlet of a steam generator (3) through a third pneumatic valve (16), the other path is communicated with the inlet of a third electric valve (15) and the pipe side inlet of the steam generator (3) through a fifth pneumatic valve (18), and the outlet of the third electric valve (15) is communicated with a tank body (8-2) of the discharge tank (8).
2. The passive cooling system of the high-temperature gas cooled reactor and the steam generator according to claim 1, wherein an outlet of the reactor (1) is communicated with a shell side inlet of the steam generator (3), and a shell side outlet of the steam generator (3) is communicated with an inlet of the reactor (1) through a main helium fan (2).
3. The passive cooling system for the high-temperature gas cooled reactor and the steam generator according to claim 1, wherein an outlet of a water-cooled wall header (8-1) in the discharge tank (8) is communicated with the waste liquid storage tank (9) through a fourth pneumatic valve (17).
4. The passive cooling system for the high-temperature gas cooled reactor and the steam generator according to claim 1, wherein an air inlet louver (4-2) and an air outlet louver (4-3) are arranged on the air cooling tower (4).
5. The passive cooling system for a high temperature gas cooled reactor and a steam generator according to claim 1, wherein the bottom elevation position of the heat exchanger (4-1) is higher than the top elevation position of the steam generator (3).
6. The passive cooling method for the high-temperature gas cooled reactor and the steam generator is characterized by comprising the passive cooling under the working condition of a steam generator (3) heat transfer pipe rupture accident and the passive cooling under the working condition of a whole plant power failure accident based on the passive cooling system for the high-temperature gas cooled reactor and the steam generator of claim 4.
7. The passive cooling method for the high-temperature gas cooled reactor and the steam generator according to claim 6, wherein the specific process of the passive cooling under the working condition of the steam generator (3) heat transfer pipe rupture accident is as follows:
when a heat transfer pipe of the steam generator (3) is broken, the reactor (1) is in emergency shutdown, the first electric valve (11), the second electric valve (13) and the fifth electric valve (18) are closed, the first electric valve (10) and the third electric valve (15) are opened, a steam-water mixture at the pipe side of the steam generator (3) starts to be discharged, steam is discharged into a heat exchanger (4-1) in the air cooling tower (4) through the first electric valve (10), water is discharged into a discharge tank (8) through the third electric valve (15), and after water is discharged, the third electric valve (15) is closed;
the second pneumatic valve (14) and the fourth pneumatic valve (17) are opened, the air inlet shutter (4-2) and the air outlet shutter (4-3) are opened, a natural circulation cold source is formed in the air cooling tower (4), steam at the tube side of the heat exchanger (4-1) exchanges heat with cold air at the shell side and then is condensed into condensed water, the condensed water enters the water-cooled wall header (8-1) of the discharge tank (8) through the check valve (12) and the second pneumatic valve (14), high-temperature hot water output by the discharge tank (8) enters the waste liquid storage tank (9) through the fourth pneumatic valve (17), and an passive circulation cooling process is established until waste heat in the reactor (1) and the steam generator (3) is led out.
8. The passive cooling method for the high-temperature gas cooled reactor and the steam generator according to claim 6, wherein the specific process of the passive cooling under the operation condition of the power failure accident of the whole plant is as follows:
when an extreme accident such as whole plant outage or loss of an external alternating current power supply occurs, the reactor (1) is in emergency shutdown, the first electric valve (11) and the second electric valve (13) are in quick closing, the third electric valve (15) is in quick closing, the fifth pneumatic valve (18) is closed, the first pneumatic valve (10) is opened, a steam-water mixture in the pipe side of the steam generator (3) starts to be discharged, steam is discharged into the heat exchanger (4-1) through the first pneumatic valve (10), water is discharged into the tank body (8-2) through the third electric valve (15), and after water is discharged, the third electric valve (15) is closed;
the second pneumatic valve (14) and the fourth pneumatic valve (17) are opened, the air inlet shutter (4-2) and the air outlet shutter (4-3) are opened, a natural circulation cold source is formed in the air cooling tower (4), steam on the tube side of the heat exchanger (4-1) exchanges heat with cold air on the shell side and then condenses into condensed water, the opening degree of the air inlet shutter (4-2) and the opening degree of the air outlet shutter (4-3) are regulated, the flow rate of the condensed water is controlled, the condensed water enters the absorption tank (8-2) in the water cooling wall header (8-1) through the check valve (12) and the second pneumatic valve (14), the opening degree of the second pneumatic valve (14) is regulated, the condensed water temperature meets the allowable cooling temperature of the heat transfer tube in the steam generator (3), the condensed water flows into the tube side of the steam generator (3) depending on the temperature difference and the gravity difference, the waste heat entering the shell side of the steam generator (3) from the reactor (1) is absorbed and then becomes steam, and the heat is continuously discharged into the air cooling tower (4) until the non-dynamic cooling process (1) and the reactor core (3) completes the cooling process.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202311362569.8A CN117637200A (en) | 2023-10-19 | 2023-10-19 | Passive cooling system and method for high-temperature gas cooled reactor and steam generator |
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| CN202311362569.8A CN117637200A (en) | 2023-10-19 | 2023-10-19 | Passive cooling system and method for high-temperature gas cooled reactor and steam generator |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
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2023
- 2023-10-19 CN CN202311362569.8A patent/CN117637200A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
| CN109767852B (en) * | 2019-02-22 | 2024-06-04 | 西安热工研究院有限公司 | Two-loop safety system for reactor emergency shutdown and working method thereof |
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