CN117637219A - Passive water-break protection system and method for high-temperature gas cooled reactor steam generator - Google Patents
Passive water-break protection system and method for high-temperature gas cooled reactor steam generator Download PDFInfo
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- CN117637219A CN117637219A CN202311364317.9A CN202311364317A CN117637219A CN 117637219 A CN117637219 A CN 117637219A CN 202311364317 A CN202311364317 A CN 202311364317A CN 117637219 A CN117637219 A CN 117637219A
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 72
- 238000001816 cooling Methods 0.000 claims abstract description 28
- 230000001502 supplementing effect Effects 0.000 claims abstract description 15
- 238000009825 accumulation Methods 0.000 claims abstract description 7
- 230000002159 abnormal effect Effects 0.000 claims description 9
- 230000001105 regulatory effect Effects 0.000 claims description 5
- 230000005484 gravity Effects 0.000 claims description 4
- 239000013589 supplement Substances 0.000 claims 1
- 239000007789 gas Substances 0.000 description 8
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 4
- 229910052757 nitrogen Inorganic materials 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
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- 230000007547 defect Effects 0.000 description 1
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Abstract
The invention discloses a passive water-break protection system and a passive water-break protection method for a high-temperature gas cooled reactor steam generator, wherein a pipe side outlet of the steam generator is divided into two paths, one path is communicated with an inlet of a high-pressure cylinder of a steam turbine, an outlet of the high-pressure cylinder of the steam turbine is communicated with an inlet of a low-pressure cylinder of the steam turbine, and an output shaft of the low-pressure cylinder of the steam turbine is communicated with a driving shaft of a generator; the other path is communicated with a pipe side inlet of a heat exchanger in the air cooling tower, and a pipe side outlet of the heat exchanger in the air cooling tower is communicated with a pipe side inlet of a steam generator; the outlet of the low-pressure cylinder of the steam turbine is communicated with the inlet of the condenser, and the outlet of the condenser is divided into two paths, wherein one path is communicated with the pipe side inlet of the steam generator; the other path is communicated with a pipe side inlet of the steam generator, and an outlet of the pressure accumulation water supplementing tank is communicated with the pipe side inlet of the steam generator.
Description
Technical Field
The invention belongs to the technical field of nuclear power safety facilities, and relates to a passive water-break protection system and method for a high-temperature gas cooled reactor steam generator.
Background
When the water supply system is abnormal and the water supply flow of the steam generator cannot be provided in the running process of the unit, the heat of the reactor core cannot be carried out, and in the extreme case, the reactor core is damaged. Therefore, the existing design enters an emergency shutdown operating condition after the water supply system is abnormal, and the reactor and the steam generator stop operating. The shutdown design scheme can ensure the safety of the reactor core, but has at least the following disadvantages: the emergency shutdown belongs to the abnormal operation condition of the unit, and once the water supply system is unstable and frequently fails abnormally, the frequent emergency shutdown can influence the service life of the steam generator and the reactor core; in addition, when the water supply system is abnormal and is caused by the power failure of the whole plant or the loss of an off-plant alternating current power supply, the steam generator and the reactor core accident cooling system cannot normally operate, heat in the reactor core and the steam generator after emergency shutdown is led out by natural cooling, the problems of long required 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 provides a passive water-break protection system and a passive water-break protection method for a high-temperature gas-cooled reactor steam generator, which can ensure safe and stable operation of a unit under the abnormal condition of a water supply system.
In order to achieve the aim, the invention discloses an passive water-break protection system of a high-temperature gas cooled reactor steam generator, which comprises a steam generator, a first electric valve, a turbine high-pressure cylinder, a turbine low-pressure cylinder, a generator, a first pneumatic valve, an air cooling tower, a condenser, a second pneumatic valve, a second electric valve and an accumulated water supplementing tank;
the pipe side outlet of the steam generator is divided into two paths, wherein one path is communicated with the inlet of the high-pressure cylinder of the steam turbine through a first electric valve, the outlet of the high-pressure cylinder of the steam turbine is communicated with the inlet of the low-pressure cylinder of the steam turbine, and the output shaft of the low-pressure cylinder of the steam turbine is communicated with the driving shaft of the generator; the other path is communicated with a pipe side inlet of a heat exchanger in the air cooling tower through a first pneumatic valve, and a pipe side outlet of the heat exchanger in the air cooling tower is communicated with a pipe side inlet of a steam generator; the outlet of the low-pressure cylinder of the steam turbine is communicated with the inlet of the condenser, and the outlet of the condenser is divided into two paths, wherein one path is communicated with the pipe side inlet of the steam generator through a second pneumatic valve; the other path is communicated with a pipe side inlet of the steam generator through a second electric valve, and an outlet of the pressure accumulation water supplementing tank is communicated with the pipe side inlet of the steam generator.
The pipe side outlet of the heat exchanger in the air cooling tower is communicated with the pipe side inlet of the steam generator through a first check valve.
The outlet of the second pneumatic valve is communicated with the pipe side inlet of the steam generator through a second check valve.
The second electric valve is communicated with a pipe side inlet of the steam generator through a water supply pump and a third electric valve in sequence.
The outlet of the pressure accumulation water supplementing tank is communicated with the pipe side inlet of the steam generator through a third 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 water-break protection method for the high-temperature gas cooled reactor steam generator comprises the following steps:
during the operation of the steam generator, when the water supply system is abnormal, the first electric valve, the second electric valve and the third electric valve are closed, the generator is stopped, the rotor of the high-pressure cylinder of the steam turbine and the rotor of the low-pressure cylinder of the steam turbine are idle until the rotating speed reaches zero, and then the first pneumatic valve, the second pneumatic valve and the third pneumatic valve are opened;
the steam reserved in the outlet pipeline of the first electric valve flows into the high-pressure cylinder and the low-pressure cylinder of the steam turbine in sequence, is discharged into the condenser, is condensed in the condenser and is injected into the pipe side inlet of the steam generator through the second pneumatic valve, so that the water supply of the steam generator is ensured;
the steam in the steam generator is discharged into the heat exchanger through the first pneumatic valve, the heat is absorbed by cold air in the air cooling tower in the heat exchanger to form condensed water, the condensed water is injected into a pipe side inlet of the steam generator, the heat on the shell side of a loop of the steam generator is continuously absorbed to form steam, the steam is continuously discharged into the heat exchanger to release heat, and the whole circulation process is carried out by means of temperature difference and gravity difference to form an passive circulation water supply loop;
when the power source driving the passive circulation water supply circuit is weakened, the water supply in the pressure accumulating water replenishing tank is injected into the pipe side inlet of the steam generator to replenish the water supply of the steam generator.
An air inlet shutter and an air outlet shutter are arranged on the air cooling tower.
The water supply flow of the steam generator is regulated by regulating the opening degrees of the air inlet shutter and the air outlet shutter.
The invention has the following beneficial effects:
according to the passive water-break protection system and method for the high-temperature gas cooled reactor steam generator, when the water supply system of the steam generator is abnormal during specific operation, the condensed water in the condenser is rapidly supplied to the steam generator, so that the water-break accident of the steam generator is effectively avoided; meanwhile, the water is put into an air cooling tower to form a passive circulating water supply loop of the steam generator, so that the water supply stability of the steam generator is further ensured; and the water supply quantity of the steam generator is timely supplemented through the pressure accumulation water supplementing tank, the steam generator is guaranteed not to have water interruption accidents through multiple loops, the water supply reliability of the steam generator is greatly improved, and therefore the damage probability of a reactor core is reduced.
Furthermore, in the invention, various operation loops of the steam generator are isolated from each other and the water supply flow path by arranging the check valve, so that the steam generator can be automatically put into each stage of water-break protection of the steam generator, and the system reliability is higher.
Furthermore, under the extreme accident condition that the whole plant is powered off or the off-plant alternating current power supply is lost, the standby diesel generator set is shut down, the passive water-break protection system adopts a pneumatic valve, and the passive water supply of the steam generator is realized through the temperature difference and the gravity difference, so that the safety of the set is ensured.
Drawings
Fig. 1 is a schematic structural view of the present invention.
Wherein, 1 is a steam generator, 2 is an air cooling tower, 3 is a high-pressure cylinder of a steam turbine, 4 is a low-pressure cylinder of the steam turbine, 5 is a generator, 6 is a condenser, 7 is a water supply pump, 8 is a pressure accumulation water supplementing tank, 9 is a first air valve, 10 is a first electric valve the air inlet shutter is characterized in that the air inlet shutter is arranged in the air inlet shutter and the air outlet shutter are arranged in the air inlet shutter, wherein the air inlet shutter is arranged in the air inlet shutter, the air outlet shutter is arranged in the air inlet shutter, and the air outlet shutter is arranged in the air inlet shutter.
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 water-break protection system of a high-temperature gas cooled reactor steam generator comprises a steam generator 1, an air cooling tower 2, a turbine high-pressure cylinder 3, a turbine low-pressure cylinder 4, a generator 5, a condenser 6, a water supply pump 7, a pressure accumulation water supplementing tank 8, a first pneumatic valve 9, a first electric valve 10, a first check valve 11, a second electric valve 12, a second pneumatic valve 13, a second check valve 14, a third electric valve 15 and a third pneumatic valve 16;
the pipe side outlet of the steam generator 1 is divided into two paths, wherein one path is communicated with the inlet of the high-pressure cylinder 3 of the steam turbine through a first electric valve 10, the outlet of the high-pressure cylinder 3 of the steam turbine is communicated with the inlet of the low-pressure cylinder 4 of the steam turbine, and the output shaft of the low-pressure cylinder 4 of the steam turbine is communicated with the driving shaft of the generator 5; the other path is communicated with a pipe side inlet of a heat exchanger 2-1 in the air cooling tower 2 through a first pneumatic valve 9, a pipe side outlet of the heat exchanger 2-1 in the air cooling tower 2 is communicated with an inlet of a first check valve 11, and an outlet of the first check valve 11 is communicated with a pipe side inlet of the steam generator 1; the outlet of the low-pressure cylinder 4 of the steam turbine is communicated with the inlet of the condenser 6, the outlet of the condenser 6 is divided into two paths, wherein one path is communicated with the inlet of the second pneumatic valve 13, the outlet of the second pneumatic valve 13 is communicated with the inlet of the second check valve 14, and the outlet of the second check valve 14 is communicated with the pipe side inlet of the steam generator 1; the other path is communicated with an inlet of a second electric valve 12, an outlet of the second electric valve 12 is communicated with an inlet of a water feeding pump 7, an outlet of the water feeding pump 7 is communicated with an inlet of a third electric valve 15, an outlet of the third electric valve 15 is communicated with a pipe side inlet of the steam generator 1, an outlet of a third pneumatic valve 16 is communicated with a pipe side inlet of the steam generator 1, and an inlet of the third pneumatic valve 16 is communicated with an outlet of an accumulated water supplementing tank 8.
The air cooling tower 2 is internally provided with a heat exchanger 2-1, the air cooling tower 2 is provided with an air inlet shutter 2-2 and an air outlet shutter 2-3, the air cooling tower 2 is placed at a high position, and the elevation position of the bottom of the heat exchanger 2-1 is higher than the elevation position of the top of the steam generator 1.
The pressure-accumulating water-replenishing tank 8 stores water, and the pressure thereof is maintained by high-pressure nitrogen.
Referring to fig. 1, the invention discloses a passive water cut-off protection method for a high temperature gas cooled reactor steam generator based on a system of typical operation conditions of the high temperature gas cooled reactor steam generator, which comprises the following steps:
during the operation of the steam generator 1, when the water supply system is abnormal, for example, a whole plant outage or a loss of an off-plant alternating current power supply occurs, the standby diesel generator set is shut down, or an emergency operation accident such as that the water supply pump 7 cannot normally work occurs, the first electric valve 10, the second electric valve 12 and the third electric valve 15 are closed, the generator 5, the rotor of the high-pressure turbine cylinder 3 and the rotor of the low-pressure turbine cylinder 4 are shut down until the rotation speed reaches zero, and the first pneumatic valve 9, the second pneumatic valve 13 and the third pneumatic valve 16 are opened.
The steam reserved in the outlet pipeline of the first electric valve 10 flows into the high-pressure cylinder 3 and the low-pressure cylinder 4 of the steam turbine in sequence, is discharged into the condenser 6, is condensed in the condenser 6, is injected into the pipe side inlet of the steam generator 1 through the second pneumatic valve 13 and the second check valve 14, and is used as a rapid water supply loop after the water cut-off of the steam generator 1.
The steam in the steam generator 1 is discharged into the heat exchanger 2-1 through the first pneumatic valve 9, the heat is absorbed by cold air in the air cooling tower 2 in the heat exchanger 2-1 to become condensed water, the condensed water is injected into a pipe side inlet of the steam generator 1 through the first check valve 11, the condensed water is continuously absorbed by the heat of a first loop shell side of the steam generator 1 to become steam, and the steam is continuously discharged into the heat exchanger 2-1 to release heat, the whole circulation process is carried out by means of temperature difference and gravity difference, a power source is not needed, an passive circulation water supply loop is formed, and the steam condensation amount is controlled by adjusting the opening of the air inlet louver 2-2 and the air outlet louver 2-3 in the process, so that the water supply flow of the steam generator 1 is adjusted.
With the continuous release of heat at the shell side of the primary circuit of the steam generator 1, when the power source driving the passive circulation water supply circuit is weakened, the water supply in the pressure accumulating water supplementing tank 8 is injected into the pipe side inlet of the steam generator 1, and the circuit is used as a water supplementing circuit after the water interruption of the steam generator 1, and the water supplementing flow of the steam generator 1 is regulated by the high-pressure nitrogen pressure in the pressure accumulating water supplementing tank 8.
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 (10)
1. The passive water-break protection system of the high-temperature gas cooled reactor steam generator is characterized by comprising a steam generator (1), a first electric valve (10), a turbine high-pressure cylinder (3), a turbine low-pressure cylinder (4), a generator (5), a first pneumatic valve (9), an air cooling tower (2), a condenser (6), a second pneumatic valve (13), a second electric valve (12) and an accumulated water supplementing tank (8);
the pipe side outlet of the steam generator (1) is divided into two paths, wherein one path is communicated with the inlet of the high-pressure cylinder (3) of the steam turbine through a first electric valve (10), the outlet of the high-pressure cylinder (3) of the steam turbine is communicated with the inlet of the low-pressure cylinder (4) of the steam turbine, the output shaft of the low-pressure cylinder (4) of the steam turbine is communicated with the driving shaft of the generator (5), the other path is communicated with the pipe side inlet of the heat exchanger (2-1) in the air cooling tower (2) through a first pneumatic valve (9), the pipe side outlet of the heat exchanger (2-1) in the air cooling tower (2) is communicated with the pipe side inlet of the steam generator (1), the outlet of the low-pressure cylinder (4) of the steam turbine is communicated with the inlet of the condenser (6), the outlet of the condenser (6) is divided into two paths, one path is communicated with the pipe side inlet of the steam generator (1) through a second pneumatic valve (13), the other path is communicated with the pipe side inlet of the heat accumulator (2-1) through a second electric valve (12), and the outlet of the heat accumulator (2-1) is communicated with the pipe side inlet of the water tank (1).
2. The passive water-break protection system of the high-temperature gas cooled reactor steam generator according to claim 1, wherein a pipe side outlet of the heat exchanger (2-1) in the air cooling tower (2) is communicated with a pipe side inlet of the steam generator (1) through a first check valve (11).
3. The passive water-break protection system of the high-temperature gas cooled reactor steam generator according to claim 1, wherein the outlet of the second pneumatic valve (13) is communicated with the pipe side inlet of the steam generator (1) through the second check valve (14).
4. The passive water-break protection system of the high-temperature gas cooled reactor steam generator according to claim 1, wherein the second electric valve (12) is communicated with a pipe side inlet of the steam generator (1) through the water supply pump (7) and the third electric valve (15) in sequence.
5. The passive water-break protection system of the high-temperature gas cooled reactor steam generator according to claim 4, wherein the outlet of the pressure accumulation water supplementing tank (8) is communicated with the pipe side inlet of the steam generator (1) through a third pneumatic valve (16).
6. The passive water-break protection system of the high-temperature gas cooled reactor steam generator according to claim 1, wherein an air inlet shutter (2-2) and an air outlet shutter (2-3) are arranged on the air cooling tower (2).
7. The passive water cut-off protection system of the high temperature gas cooled reactor steam generator according to claim 1, wherein the bottom elevation position of the heat exchanger (2-1) is higher than the top elevation position of the steam generator (1).
8. The passive water-break protection method for the high-temperature gas cooled reactor steam generator is characterized by comprising the following steps of:
during the operation of the steam generator (1), when a water supply system is abnormal, the first electric valve (10), the second electric valve (12) and the third electric valve (15) are closed, the generator (5) is stopped, the rotor of the high-pressure cylinder (3) of the steam turbine and the rotor of the low-pressure cylinder (4) of the steam turbine are idle until the rotating speed reaches zero, and then the first pneumatic valve (9), the second pneumatic valve (13) and the third pneumatic valve (16) are opened;
the steam reserved in the outlet pipeline of the first electric valve (10) flows into the high-pressure cylinder (3) and the low-pressure cylinder (4) of the steam turbine in sequence, is discharged into the condenser (6), is condensed in the condenser (6), and is injected into the pipe side inlet of the steam generator (1) through the second pneumatic valve (13) so as to ensure that the water is supplied to the steam generator (1);
the steam in the steam generator (1) is discharged into the heat exchanger (2-1) through the first pneumatic valve (9), the heat is absorbed by cold air in the air cooling tower (2) in the heat exchanger (2-1) to become condensed water, the condensed water is injected into a pipe side inlet of the steam generator (1), the heat on the shell side of a loop of the steam generator (1) is continuously absorbed to become steam, the steam is continuously discharged into the heat exchanger (2-1) to release heat, and the whole circulation process is carried out by means of temperature difference and gravity difference to form an passive circulation water supply loop;
when the power source driving the passive circulation water supply circuit is weakened, the water supply in the pressure accumulating water supplementing tank (8) is injected into the pipe side inlet of the steam generator (1) to supplement the water supply of the steam generator (1).
9. The passive water-break protection system of the high-temperature gas cooled reactor steam generator according to claim 8, wherein an air inlet shutter (2-2) and an air outlet shutter (2-3) are arranged on the air cooling tower (2).
10. The passive water-break protection method for the high-temperature gas cooled reactor steam generator according to claim 9, wherein the water supply flow rate of the steam generator (1) is regulated by regulating the opening degrees of the air inlet louver (2-2) and the air outlet louver (2-3).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311364317.9A CN117637219A (en) | 2023-10-19 | 2023-10-19 | Passive water-break protection system and method for high-temperature gas cooled reactor steam generator |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311364317.9A CN117637219A (en) | 2023-10-19 | 2023-10-19 | Passive water-break protection system and method for high-temperature gas cooled reactor steam generator |
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| CN117637219A true CN117637219A (en) | 2024-03-01 |
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| CN202311364317.9A Pending CN117637219A (en) | 2023-10-19 | 2023-10-19 | Passive water-break protection system and method for high-temperature gas cooled reactor 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 CN202311364317.9A patent/CN117637219A/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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