CN113380432A - 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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- CN113380432A CN113380432A CN202110688314.5A CN202110688314A CN113380432A CN 113380432 A CN113380432 A CN 113380432A CN 202110688314 A CN202110688314 A CN 202110688314A CN 113380432 A CN113380432 A CN 113380432A
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- superheater
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/08—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from moderating material
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
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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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- Control Of Steam Boilers And Waste-Gas Boilers (AREA)
Abstract
The invention discloses a forced cooling system after 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 invention belongs to the field of nuclear reactor accident shutdown cooling, and relates to a forced cooling system after a sodium-cooled fast reactor loses all water supply.
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.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a forced cooling system after all water supply of a sodium-cooled fast reactor is lost, which can avoid the problems of low residual heat discharge rate and design redundancy when a non-kinetic energy residual heat discharge system discharges residual heat of a reactor core.
In order to achieve the aim, the forced cooling system of the sodium-cooled fast reactor after all water supply is lost comprises an auxiliary boiler, an auxiliary steam system, a first isolation valve, a second isolation valve, a start and shutdown cooling system, a main steam system, a bypass 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 invention has the following beneficial effects:
when the forced cooling system of the sodium-cooled fast reactor loses all water supply, an active cooling, heat exchange and cooling mode is adopted, auxiliary steam with lower parameters generated by an auxiliary boiler is introduced into a superheater to absorb heat of metal sodium for heat exchange and temperature rise, and then the auxiliary steam is sent into a side exhaust system for temperature reduction and pressure reduction, or is directly exhausted into the atmosphere through an atmosphere release valve group, so that the problems of low waste heat discharge rate and design redundancy when a non-kinetic energy waste heat discharge system discharges waste heat of a reactor core are solved, the abnormity caused by common mode fault is avoided, the fault safety of unit design is improved, the waste heat discharge rate of a primary loop and a secondary loop of the sodium-cooled fast reactor is improved, additional equipment is not required, the equipment is not required to operate in a mode exceeding design parameters, and the cost is low.
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 solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, not all of the embodiments, and are not intended to limit the scope of the present disclosure. 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. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
There is shown in the drawings a schematic block diagram of a disclosed embodiment in accordance with the invention. 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 comprises 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 working process of the invention is as follows:
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 |
|---|---|---|---|
| CN202110688314.5A CN113380432A (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 |
|---|---|---|---|
| CN202110688314.5A CN113380432A (en) | 2021-06-21 | 2021-06-21 | Forced cooling system after sodium-cooled fast reactor loses all feedwater |
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| Publication Number | Publication Date |
|---|---|
| CN113380432A true CN113380432A (en) | 2021-09-10 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110688314.5A Pending CN113380432A (en) | 2021-06-21 | 2021-06-21 | Forced cooling system after sodium-cooled fast reactor loses all feedwater |
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| Country | Link |
|---|---|
| CN (1) | CN113380432A (en) |
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2021
- 2021-06-21 CN CN202110688314.5A patent/CN113380432A/en active Pending
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