CN209843263U - Passive accident waste heat discharging system for sodium-cooled fast reactor intermediate circuit - Google Patents
Passive accident waste heat discharging system for sodium-cooled fast reactor intermediate circuit Download PDFInfo
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- CN209843263U CN209843263U CN201920223010.XU CN201920223010U CN209843263U CN 209843263 U CN209843263 U CN 209843263U CN 201920223010 U CN201920223010 U CN 201920223010U CN 209843263 U CN209843263 U CN 209843263U
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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 utility model belongs to the technical field of the nuclear power station cooling, especially, relate to an active accident waste heat discharge system of sodium-cooled fast reactor intermediate circuit non-, constitute including three return circuits, be respectively: a primary circuit formed by the inside of the sodium pool and the primary side of the intermediate heat exchanger; two loops formed by the secondary side of the intermediate heat exchanger and the tube side of the air heat exchanger, and three loops formed by the air heat exchanger and the atmosphere. And the heat pipe section leading-out branch of the two loops is connected with the expansion tank. The air heat exchanger is arranged in the exhaust chimney. The problem that natural circulation cannot be fully established in a sodium pool under the whole plant outage working condition due to the arrangement mode of independent heat exchangers (DHX) is solved; 4 new residual heat removal circuits are obtained except for 2 circuits of the independent residual heat removal system. Support guarantee is provided on the diversity and redundancy of the safety design of the reactor system. Under the working condition of a whole plant power failure accident, the reactor is effectively cooled for a long time by utilizing natural circulation.
Description
Technical Field
The utility model belongs to the technical field of the nuclear power station cooling, especially, relate to an active accident waste heat discharge system of sodium-cooled fast reactor intermediate circuit non-.
Background
After the reactor is shut down under the working condition of power failure of a whole plant, the intermediate loop cannot discharge the waste heat of the reactor core by means of forced flow, and if a large amount of decay heat cannot be discharged out of the reactor core in time, the damage of the reactor core and even the leakage of radioactive substances are caused, so that the discharge of the waste heat of the reactor core can be guaranteed by a passive system under the working condition of an accident, which is particularly important.
The passive residual heat removal system is one of the special safety facilities of the sodium-cooled fast reactor, the independent residual heat removal system used by the domestic sodium-cooled fast reactor at present comprises 2 independent loops, each loop is provided with 1 sodium-sodium independent heat exchanger (DHX) and one sodium-air heat exchanger (AHX), the independent heat exchangers (DHX) are immersed at the periphery of a hot sodium pool and are connected with the air heat exchangers (AHX) through intermediate loops, three coupling natural circulation loops including a reactor core to DHX, a DHX to air heat exchanger (AHX) and an air heat exchanger (AHX) to atmosphere are formed, and the reactor core residual heat is discharged to the final hot trap atmosphere.
In the passive residual heat removal system, because the independent heat exchanger (DHX) is immersed at the periphery of the hot sodium pool, sodium in the hot sodium pool at the upper part of the reactor container needs to enter the outer area of the hot sodium pool through the overflow window, then flows into the shell side of the independent heat exchanger (DHX) from top to bottom, and exchanges heat with sodium flowing into the tube side of the intermediate loop from bottom to top. This arrangement is primarily intended to ensure less waste of efficiency in normal conditions due to heat being carried away by the independent heat exchanger (DHX), but in accident conditions, it reduces the ability of the independent heat exchanger (DHX) to establish natural circulation.
In addition, under the whole plant outage working condition, if an air door in an independent waste heat discharge system loop cannot be normally opened due to mechanical failure, the core and heat discharge capacity under the accident working condition cannot be completely guaranteed by the remaining independent waste heat discharge system loop, and the method is also a great potential safety hazard in the design of the sodium-cooled fast reactor.
SUMMERY OF THE UTILITY MODEL
To the technical problem, the utility model provides an active accident waste heat discharge system of sodium-cooled fast reactor intermediate circuit non-, constitute including three return circuits, be respectively: a primary circuit formed by the inside of the sodium pool and the primary side of the intermediate heat exchanger; two loops formed by the secondary side of the intermediate heat exchanger and the tube side of the air heat exchanger, and three loops formed by the air heat exchanger and the atmosphere.
And the heat pipe section leading-out branch of the two loops is connected with the expansion tank.
The air heat exchanger is arranged in the exhaust chimney.
The intermediate heat exchanger is also connected with a steam generator in a circulating way, and the steam generator is connected with a steam turbine.
The specific connection mode of the two loops is as follows: the secondary side outlet of the intermediate heat exchanger is connected with the intermediate loop heat pipe section, the intermediate loop passive accident waste heat discharge system heat pipe section is led out from the intermediate loop heat pipe section, the expansion tank branch is led out from the heat pipe section, the intermediate loop passive accident waste heat discharge system heat pipe section is connected with the air heat exchanger pipe side inlet, the air heat exchanger pipe side outlet is connected with the intermediate loop accident waste heat discharge system cold pipe section, the intermediate loop accident waste heat discharge system cold pipe section is connected with the intermediate loop cold pipe section, and the cold pipe section is connected with the secondary side inlet of the intermediate heat exchanger to form a complete intermediate loop passive accident waste heat discharge system loop.
The three loops are connected in a specific manner as follows: the air inlet is connected with the air door, and the air inlet of the air exhaust chimney, the air door, the shell side of the air heat exchanger, the air outlet of the air exhaust chimney and the atmosphere form a three-loop
The air heat exchanger and the exhaust chimney are arranged outside the nuclear island.
The air heat exchanger is arranged higher than the intermediate loop cold and heat pipeline.
The air heat exchanger tube side inlet is higher than the tube side outlet.
The three-loop air door is controlled by an electromagnet, the opening degree is kept at 10% at ordinary times, the magnetic force disappears under the condition of the power failure of the whole plant, and the air door is completely opened under the action of gravity.
The utility model has the advantages that:
the intermediate heat exchanger (IHX) is used as a heat exchanger in the sodium pool in the passive waste heat discharge system, so that the problem that natural circulation cannot be fully established in the sodium pool due to the arrangement mode of independent heat exchangers (DHX) under the power-off working condition of a whole plant is solved; 4 new residual heat removal loops except 2 loops of the independent residual heat removal system are obtained, the working mechanisms of the residual heat removal loops are different, and support and guarantee are provided on the diversity and the redundancy of the safety design of the reactor system; under the working condition of a power failure accident of a whole plant, the passive residual heat removal system realizes long-term and effective cooling by establishing natural circulation for a reactor, so that the residual heat of a reactor core is effectively removed, and the pressure and the temperature in the reactor core are ensured not to exceed the design limit values. Because the intermediate heat exchanger (IHX) is arranged in a mode of penetrating through the hot sodium pool and the cold sodium pool and is closer to the core than an independent heat exchanger (DHX), the heated liquid metal sodium flowing out of the upper part of the core can enter the heat exchanger without passing through an overflow window, and the capacity of establishing natural circulation in the sodium pool is improved
Drawings
Fig. 1 is a schematic structural diagram of the passive residual heat removal system of the intermediate circuit of the present invention.
Fig. 2 is a three loop flow pattern of the intermediate loop passive accident residual heat removal system.
Detailed Description
The embodiments are described in detail below with reference to the accompanying drawings.
Fig. 1 shows a specific structural schematic diagram of the passive residual heat removal system of the intermediate circuit of the present invention. In the figure, an intermediate heat exchanger (IHX)1 in a reactor core is connected with a starting end 4 of an intermediate loop heat pipe section through a secondary side outlet 2, the starting end 4 of the intermediate loop heat pipe section is connected with a pipe side inlet of an air heat exchanger (AHX)6 through a pipe 5, the pipes 4 and 5 jointly form a heat pipe section part of an intermediate loop passive waste heat discharge system, an expansion tank 10 is connected on the heat pipe section 5, the heat pipe section 5 is connected with the pipe side inlet of the air heat exchanger (AHX)6, the arrangement of the natural circulation air heat exchanger (AHX)6 is higher than that of the intermediate loop pipe, the air heat exchanger (AHX)6 is arranged in an exhaust chimney 7 and is arranged outside a nuclear island, an outlet of the air heat exchanger (AHX)6 is connected with an intermediate loop cold section tail end 9 through a pipe 8, the pipe 8 and the intermediate loop cold section tail end 9 jointly form a cold section of the intermediate loop passive waste heat discharge system, the pipe 9 is connected with the secondary side inlet 3 of the intermediate heat exchanger (IHX), so that a complete intermediate loop passive residual heat removal system two loop is formed.
Fig. 2 shows three loop flow directions of the intermediate loop passive accident residual heat removal system.
The flow direction of the primary loop is as follows: cold sodium in the cold sodium pool enters the pump through an inlet of the main pump and enters the grid plate header through an outlet of the main pump, the cold sodium flows upwards through the fuel assembly by the grid plate header to take away decay heat of the assembly, hot sodium heated by the decay heat of the assembly flows into the hot sodium pool, sodium in the hot sodium pool enters the intermediate heat exchanger (IHX) through a primary side inlet of the intermediate heat exchanger (IHX) to exchange heat with secondary side cold sodium to guide reactor core waste heat into an intermediate loop, and the cold sodium pool flows into the cold sodium pool again through a primary side outlet of the intermediate heat exchanger (IHX) to form a complete intermediate loop passive accident waste heat discharge system natural circulation loop.
The flow direction of the two loops is as follows:
the flow direction of the two loops is as follows: the heated sodium after heat exchange with primary side heat sodium flows into the initial end of the intermediate loop heat pipe section from the secondary side outlet of an intermediate heat exchanger (IHX), the intermediate loop waste heat discharge system heat pipe section enters the air heat exchanger (AHX) pipe side through the shell side inlet of the air heat exchanger (AHX), the heat of the intermediate loop is transferred to the intermediate loop passive accident waste heat discharge system three loops after heat exchange is carried out between the hot sodium and the air at the shell side of the air heat exchanger (AHX), the cooled sodium flows out from the pipe side outlet of the air heat exchanger (AHX), flows into the tail end of the intermediate loop cold section through the intermediate loop waste heat discharge system cold pipe section, and finally enters the intermediate heat exchanger (IHX) through the secondary side inlet of the intermediate heat exchanger (IHX) to form a complete intermediate loop passive accident waste heat discharge system natural circulation two loops.
The flow directions of the three loops are as follows:
air flows into the exhaust chimney through the air door and an inlet at the bottom of the exhaust chimney, flows upwards through the shell side of the air heat exchanger under the pressure difference of an inlet and an outlet, exchanges heat with sodium at the tube side of the air heat exchanger, takes away the heat of the two loops, and finally enters the final hot-trap atmosphere through an outlet at the top of the exhaust chimney to form a complete natural circulation three loops of the intermediate loop passive accident waste heat discharge system.
The present invention is not limited to the above embodiments, and any changes or substitutions that can be easily conceived by those skilled in the art within the technical scope of the present invention are also covered by the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (10)
1. The utility model provides an active accident waste heat discharge system of sodium-cooled fast reactor intermediate circuit non-which characterized in that, includes that three return circuits are constituteed, is respectively: a primary circuit formed by the inside of the sodium pool and the primary side of the intermediate heat exchanger; two loops formed by the secondary side of the intermediate heat exchanger and the tube side of the air heat exchanger, and three loops formed by the air heat exchanger and the atmosphere.
2. The system of claim 1, wherein the heat pipe section outlet branch of the two circuits is connected to an expansion tank.
3. The system of claim 1, wherein the air heat exchanger is disposed within an exhaust stack.
4. The system of claim 1, wherein the intermediate heat exchanger is further coupled to a steam generator circuit, the steam generator being coupled to a steam turbine.
5. The system of claim 1, wherein the two loops are specifically connected in a manner that: the secondary side outlet of the intermediate heat exchanger is connected with the intermediate loop heat pipe section, the intermediate loop passive accident waste heat discharge system heat pipe section is led out from the intermediate loop heat pipe section, the expansion tank branch is led out from the heat pipe section, the intermediate loop passive accident waste heat discharge system heat pipe section is connected with the air heat exchanger pipe side inlet, the air heat exchanger pipe side outlet is connected with the intermediate loop accident waste heat discharge system cold pipe section, the intermediate loop accident waste heat discharge system cold pipe section is connected with the intermediate loop cold pipe section, and the cold pipe section is connected with the secondary side inlet of the intermediate heat exchanger to form a complete intermediate loop passive accident waste heat discharge system loop.
6. The system of claim 1, wherein the three loops are specifically connected in a manner that: the air inlet is connected with the air door, and the air inlet of the air exhaust chimney, the air door, the shell side of the air heat exchanger, the air outlet of the air exhaust chimney and the atmosphere form three loops.
7. The system of claim 1, wherein the air heat exchanger and exhaust stack are disposed outside the nuclear island.
8. The system of claim 1, wherein the air heat exchanger is disposed above the intermediate circuit cold and hot conduits.
9. The system of claim 1, wherein the air heat exchanger tube side inlet is higher than the tube side outlet.
10. The system of claim 6, wherein the three-circuit damper is controlled by an electromagnet, the three-circuit damper is normally kept at 10% opening, and in case of power failure of a whole plant, the magnetic force disappears and the damper is completely opened under the action of gravity.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920223010.XU CN209843263U (en) | 2019-02-22 | 2019-02-22 | Passive accident waste heat discharging system for sodium-cooled fast reactor intermediate circuit |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920223010.XU CN209843263U (en) | 2019-02-22 | 2019-02-22 | Passive accident waste heat discharging system for sodium-cooled fast reactor intermediate circuit |
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| CN209843263U true CN209843263U (en) | 2019-12-24 |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109830316A (en) * | 2019-02-22 | 2019-05-31 | 华北电力大学 | A kind of passive accident afterheat discharge system of sodium-cooled fast reactor intermediate loop |
| CN113838587A (en) * | 2021-08-30 | 2021-12-24 | 西安交通大学 | Small-size villiaumite pile passive surplus row system based on integral type heat exchanger |
-
2019
- 2019-02-22 CN CN201920223010.XU patent/CN209843263U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109830316A (en) * | 2019-02-22 | 2019-05-31 | 华北电力大学 | A kind of passive accident afterheat discharge system of sodium-cooled fast reactor intermediate loop |
| CN113838587A (en) * | 2021-08-30 | 2021-12-24 | 西安交通大学 | Small-size villiaumite pile passive surplus row system based on integral type heat exchanger |
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