CN215069282U - Forced cooling system after sodium-cooled fast reactor loses all feedwater - Google Patents
Forced cooling system after sodium-cooled fast reactor loses all feedwater Download PDFInfo
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- CN215069282U CN215069282U CN202121384098.7U CN202121384098U CN215069282U CN 215069282 U CN215069282 U CN 215069282U CN 202121384098 U CN202121384098 U CN 202121384098U CN 215069282 U CN215069282 U CN 215069282U
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The utility model discloses a forced cooling system after the sodium-cooled fast reactor loses all water supply, the outlet of an auxiliary boiler is communicated with the inlet of an auxiliary steam system, the outlet of the auxiliary steam system is divided into two paths, one path is communicated with an inlet of the start-up and shutdown cooling system, the other path is communicated with a side discharge system through a main steam system, a pipeline between the side discharge system and the main steam system is communicated with one end of a superheater outlet valve group, the other end of the superheater outlet valve group is communicated with an atmosphere release valve group through a heater, outlets of the start-up and shutdown cooling system are divided into two paths, one path is communicated with a pipeline between the superheater and the atmospheric release valve group, the other path is communicated with the heat absorption side of the evaporator, the system can avoid the problems of low waste heat discharge rate and design redundancy when the non-kinetic energy waste heat discharge system discharges the waste heat of the reactor core.
Description
Technical Field
The utility model belongs to nuclear reactor accident shutdown cooling field relates to a forced cooling system after sodium-cooled fast reactor loses whole feedwater.
Background
After the three loops of the sodium-cooled fast reactor lose all water supply cooling, the reactor is automatically stopped, and the reactor core waste heat is discharged to the atmosphere by a passive waste heat discharge system in a loop sodium pool. The loop passive residual heat removal system has a redundant design, but has the following defects: due to the lack of diversity design, common mode faults of redundancy design are one of the problems to be avoided in accident safety analysis; compared with forced circulation, natural circulation has low heat exchange efficiency and low waste heat discharge rate.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to overcome above-mentioned prior art's shortcoming, provide a sodium-cooled fast reactor and lose the whole forced cooling system who supplies water after, the waste heat discharge rate that appears when this system can avoid non-kinetic energy waste heat discharge system to discharge the reactor core waste heat is low and there is the redundant problem of design.
In order to achieve the purpose, the forced cooling system of the sodium-cooled fast reactor after losing all water supply comprises an auxiliary boiler, an auxiliary steam system, a first isolating valve, a second isolating valve, a start and shutdown cooling system, a main steam system, a side discharge system and a plurality of evaporator/superheater modules;
each evaporator/superheater module comprises a superheater outlet valve bank, a superheater, an atmospheric release valve bank, an evaporator and an evaporator inlet valve bank;
the outlet of the auxiliary boiler is communicated with the inlet of the auxiliary steam system, the outlet of the auxiliary steam system is divided into two paths, wherein one path is communicated with the inlet of the start-up and shutdown cooling system, the other path is communicated with the side-discharge system through the main steam system, a pipeline between the side-discharge system and the main steam system is communicated with one end of a superheater outlet valve group, the other end of the superheater outlet valve group is communicated with an atmosphere release valve group through a heater, the outlet of the start-up and shutdown cooling system is divided into two paths, one path is communicated with a pipeline between the superheater and the atmosphere release valve group, and the other path is communicated with the heat absorption side of the evaporator.
The outlet of the auxiliary steam system is communicated with the main steam system through a first isolation valve.
The outlet of the auxiliary steam system is communicated with the start-up and shutdown cooling system through a second isolation valve.
An external water supply system is communicated with the inlet of the evaporator.
The external water supply system is communicated with the inlet of the evaporator through the evaporator inlet valve bank.
When the water supply loss accident occurs, the reactor is shut down, the evaporator inlet valve set is automatically closed to isolate the water supply system and the evaporator/superheater module, the auxiliary boiler is started, and the steam generated by the auxiliary boiler is supplied to the auxiliary steam system.
When the circulating water system is available, steam in the auxiliary steam system enters the start-up and shutdown cooling system, then enters the superheater, absorbs heat of metal sodium in the superheater for heat exchange and temperature rise, the heated steam flow enters the bypass system through the outlet valve bank of the superheater for temperature reduction and pressure reduction, then enters the condenser, meanwhile, the first isolation valve is closed to isolate the auxiliary steam system from the main steam system, and the atmosphere release valve bank is in a closed state.
When the circulating water system is unavailable, the second isolation valve is closed to isolate the auxiliary steam system and start and stop the cooling system, the side-discharge system is closed, steam output by the auxiliary steam system enters the main steam system, then enters the superheater after passing through the outlet valve bank of the superheater, absorbs heat of the metal sodium in the superheater to carry out heat exchange and temperature rise, and the steam after temperature rise is discharged to the atmosphere through the atmosphere release valve bank.
The utility model discloses following beneficial effect has:
the sodium-cooled fast reactor lose the whole forced cooling system after supplying water when concrete operation, adopt the mode of initiative cooling heat transfer cooling, use the lower supplementary steam of parameter that auxiliary boiler produced, let in its heat that absorbs metal sodium in the over heater and carry out the heat transfer and heat up, then send into and carry out the temperature reduction and pressure reduction in the other exhaust system, perhaps directly arrange to the atmosphere through the atmospheric release valves, waste heat discharge rate that appears when avoiding non-kinetic energy waste heat discharge system exhaust reactor core waste heat is low and there is the redundant problem of design, avoid the unusual because of common mode fault leads to, improve the fail-safe nature in the unit design, improve the waste heat discharge rate in two return circuits of sodium-cooled fast reactor simultaneously, and need not to increase extra equipment, also need not the mode operation of equipment in order to exceed design parameter, and is with low costs.
Drawings
Fig. 1 is a schematic structural diagram of the present invention.
Wherein, 1 is an auxiliary boiler, 2 is an auxiliary steam system, 3 is a main steam system, 4 is a superheater outlet valve bank, 5 is a superheater, 6 is an atmosphere release valve bank, and 7 is an evaporator; 8 is an evaporator inlet valve group, 9 is a start-up and shutdown cooling system, 10 is an evaporator/superheater module, and 11 is a bypass system.
Detailed Description
In order to make the technical solution of the present invention better understood, the following figures in the embodiments of the present invention are combined to clearly and completely describe the technical solution in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments, and do not limit the scope of the present invention. Moreover, in the following description, descriptions of well-known structures and techniques are omitted so as to not unnecessarily obscure the concepts of the present disclosure. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts shall belong to the protection scope of the present invention.
A schematic structural diagram according to an embodiment of the present disclosure is shown in the drawings. The figures are not drawn to scale, wherein certain details are exaggerated and possibly omitted for clarity of presentation. The shapes of various regions, layers and their relative sizes and positional relationships shown in the drawings are merely exemplary, and deviations may occur in practice due to manufacturing tolerances or technical limitations, and a person skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions, according to actual needs.
Referring to fig. 1, the forced cooling system after the sodium-cooled fast reactor loses all water supply of the present invention includes an auxiliary boiler 1, an auxiliary steam system 2, a first isolation valve, a second isolation valve, a start-up and shutdown cooling system 9, a main steam system 3, a bypass system 11 and a plurality of evaporator/superheater modules 10;
each evaporator/superheater module 10 comprises a superheater outlet valve bank 4, a superheater 5, an atmospheric release valve bank 6, an evaporator 7 and an evaporator inlet valve bank 8;
the outlet of the auxiliary boiler 1 is communicated with the inlet of the auxiliary steam system 2, the outlet of the auxiliary steam system 2 is divided into two paths, wherein one path is communicated with the inlet of the start-up and shutdown cooling system 9 through a second isolation valve, the other path is communicated with the side exhaust system 11 through a first isolation valve and the main steam system 3, a pipeline between the side exhaust system 11 and the main steam system 3 is communicated with one end of a superheater outlet valve group 4, the other end of the superheater outlet valve group 4 is communicated with an atmosphere release valve group 6 through a heater 5, the outlet of the start-up and shutdown cooling system 9 is divided into two paths, one path is communicated with a pipeline between the superheater 5 and the atmosphere release valve group 6, the other path is communicated with the heat absorption side of the evaporator 7, and an external water supply system is communicated with the inlet of the evaporator 7 through an evaporator inlet valve group 8.
The utility model discloses a working process does:
when a water supply loss accident occurs, the reactor is shut down, the evaporator inlet valve group 8 is automatically closed to isolate the water supply system from the evaporator/superheater module 10, the auxiliary boiler 1 is started, and steam with the pressure of 2.1MPa and the temperature of 280 ℃ generated by the auxiliary boiler 1 is supplied to the auxiliary steam system 2.
When the circulating water system is available, steam in the auxiliary steam system 2 enters the start-up and shutdown cooling system 9, then enters the superheater 5, absorbs heat of metal sodium in the superheater 5 to perform heat exchange and temperature rise, the heated steam flow enters the bypass system 11 through the heater outlet valve bank 4 to perform temperature reduction and pressure reduction, and then enters the condenser, meanwhile, the first isolation valve is closed to isolate the auxiliary steam system 2 from the main steam system 3, and the atmosphere release valve bank 6 is in a closed state.
When the circulating water system is unavailable, the second isolation valve is closed to isolate the auxiliary steam system 2 and the start and shutdown cooling system 9, the side discharge system 11 is closed, steam output by the auxiliary steam system 2 enters the main steam system 3, then enters the superheater 5 after passing through the superheater outlet valve bank 4, absorbs heat of metal sodium in the superheater 5 to carry out heat exchange and temperature rise, and the steam after temperature rise is discharged to the atmosphere through the atmosphere release valve bank 6.
In the forced circulation cooling process of the three loops, the sodium pump of the first loop and the second loop keeps a low-speed running state, the heat exchange capacity among the three loops is enhanced, the heat input brought by the sodium pump is reduced, and meanwhile, the temperature and the flow of auxiliary steam supply are gradually adjusted and reduced along with the gradual reduction of the temperature of metal sodium of the first loop and the second loop of the reactor, so that forced cooling of the sodium-cooled fast reactor after all water supply is lost is realized.
Claims (8)
1. A forced cooling system after a sodium-cooled fast reactor loses all water supply is characterized by comprising an auxiliary boiler (1), an auxiliary steam system (2), a first isolation valve, a second isolation valve, a start and shutdown cooling system (9), a main steam system (3), a bypass system (11) and a plurality of evaporator/superheater modules (10);
each evaporator/superheater module (10) comprises a superheater outlet valve bank (4), a superheater (5), an atmosphere release valve bank (6), an evaporator (7) and an evaporator inlet valve bank (8);
the outlet of the auxiliary boiler (1) is communicated with the inlet of an auxiliary steam system (2), the outlet of the auxiliary steam system (2) is divided into two paths, one path is communicated with the inlet of a start-up and shutdown cooling system (9), the other path is communicated with a side exhaust system (11) through a main steam system (3), a pipeline between the side exhaust system (11) and the main steam system (3) is communicated with one end of a superheater outlet valve group (4), the other end of the superheater outlet valve group (4) is communicated with an atmosphere release valve group (6) through a heater (5), the outlet of the start-up and shutdown cooling system (9) is divided into two paths, one path is communicated with a pipeline between the superheater (5) and the atmosphere release valve group (6), and the other path is communicated with the heat absorption side of an evaporator (7).
2. A forced cooling system after the sodium-cooled fast reactor loses all water supply according to claim 1, characterized in that the outlet of the auxiliary steam system (2) is communicated with the main steam system (3) through a first isolation valve.
3. A forced cooling system after the sodium-cooled fast reactor loses all water supply according to claim 1, characterized in that the outlet of the auxiliary steam system (2) is communicated with the start-up and shutdown cooling system (9) through a second isolation valve.
4. A forced cooling system after the sodium-cooled fast reactor loses all water supply according to claim 1, characterized in that an external water supply system is communicated with the inlet of the evaporator (7).
5. A forced cooling system after sodium-cooled fast reactor loses all water supply according to claim 4, characterized in that, the external water supply system is communicated with the inlet of the evaporator (7) through the evaporator inlet valve group (8).
6. A forced cooling system after the sodium-cooled fast reactor loses all water supply, which is characterized in that when the water supply loss accident happens, the reactor is shut down, an evaporator inlet valve group (8) is automatically closed to isolate a water supply system from an evaporator/superheater module (10), an auxiliary boiler (1) is started, and steam generated by the auxiliary boiler (1) is supplied to an auxiliary steam system (2).
7. The forced cooling system of the sodium-cooled fast reactor after all water supply is lost according to claim 1, characterized in that when a circulating water system is available, steam in the auxiliary steam system (2) enters the start-up and shutdown cooling system (9), then enters the superheater (5), and absorbs heat of metal sodium in the superheater (5) to carry out heat exchange and temperature rise, the steam flow after temperature rise enters the bypass system (11) through the heat outlet valve bank (4) to carry out temperature reduction and pressure reduction, then enters the condenser, and meanwhile, the first isolation valve is closed to isolate the auxiliary steam system (2) from the main steam system (3), and the atmospheric release valve bank (6) is in a closed state.
8. The forced cooling system of the sodium-cooled fast reactor after all water supply is lost according to claim 1, characterized in that when a circulating water system is unavailable, a second isolation valve is closed to isolate the auxiliary steam system (2) and the start-up and shutdown cooling system (9), a bypass system (11) is closed, steam output by the auxiliary steam system (2) enters the main steam system (3), then enters the superheater (5) after passing through a superheater outlet valve group (4), absorbs heat of metal sodium in the superheater (5) for heat exchange and temperature rise, and the steam after temperature rise is discharged to the atmosphere through an atmosphere release valve group (6).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121384098.7U CN215069282U (en) | 2021-06-21 | 2021-06-21 | Forced cooling system after sodium-cooled fast reactor loses all feedwater |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121384098.7U CN215069282U (en) | 2021-06-21 | 2021-06-21 | Forced cooling system after sodium-cooled fast reactor loses all feedwater |
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| CN215069282U true CN215069282U (en) | 2021-12-07 |
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| CN202121384098.7U Active CN215069282U (en) | 2021-06-21 | 2021-06-21 | Forced cooling system after sodium-cooled fast reactor loses all feedwater |
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- 2021-06-21 CN CN202121384098.7U patent/CN215069282U/en active Active
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