AU2019101235A4 - Lead-cooled fast reactor waste heat removal system and method - Google Patents
Lead-cooled fast reactor waste heat removal system and method Download PDFInfo
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- AU2019101235A4 AU2019101235A4 AU2019101235A AU2019101235A AU2019101235A4 AU 2019101235 A4 AU2019101235 A4 AU 2019101235A4 AU 2019101235 A AU2019101235 A AU 2019101235A AU 2019101235 A AU2019101235 A AU 2019101235A AU 2019101235 A4 AU2019101235 A4 AU 2019101235A4
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- 239000002918 waste heat Substances 0.000 title claims abstract description 135
- 238000000034 method Methods 0.000 title claims abstract description 21
- 239000002826 coolant Substances 0.000 claims abstract description 50
- 238000001816 cooling Methods 0.000 claims abstract description 27
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 62
- 238000010438 heat treatment Methods 0.000 claims description 27
- 229910001152 Bi alloy Inorganic materials 0.000 claims description 21
- 239000000498 cooling water Substances 0.000 claims description 19
- 239000007788 liquid Substances 0.000 claims description 19
- 230000009471 action Effects 0.000 claims description 13
- 230000005484 gravity Effects 0.000 claims description 6
- 238000009834 vaporization Methods 0.000 claims description 5
- 230000008016 vaporization Effects 0.000 claims description 5
- 230000008569 process Effects 0.000 claims description 3
- 230000000630 rising effect Effects 0.000 claims description 3
- 239000002699 waste material Substances 0.000 claims description 3
- 230000002708 enhancing effect Effects 0.000 abstract description 3
- 239000008400 supply water Substances 0.000 abstract description 3
- 238000011160 research Methods 0.000 abstract description 2
- 229910052797 bismuth Inorganic materials 0.000 description 5
- 238000010586 diagram Methods 0.000 description 5
- 230000003247 decreasing effect Effects 0.000 description 3
- 239000003153 chemical reaction reagent Substances 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- 238000011144 upstream manufacturing Methods 0.000 description 2
- 238000010795 Steam Flooding Methods 0.000 description 1
- 238000007792 addition Methods 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
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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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
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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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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention discloses a lead-cooled fast reactor waste heat removal system and method. The waste heat removal system is composed of three subsystems, namely a magnetic heat exchanger active waste heat removal system, a waste heat-driven passive reactor core cooling system and a passive waste heat removal system, which work independently. The present invention uses a pneumatic pump to supply water to a secondary side of a steam generator, thereby solving a problem that a heat release function of a secondary loop fails when a primary feedwater pump fails to work normally under a power failure condition; at the same time, the present invention uses a magnetic heat exchanger natural circulation cooling loop independent of an active waste heat removal system in the active waste heat removal system, which overcomes a shortcoming that a traditional heat exchanger cannot exchange heat with a reactor core under the power failure condition, and thus greatly increases the flow rate of a coolant in the reactor core, and accelerates the removal of waste heat from the reactor core, thereby safeguarding not only a reactor, but also the research of a nuclear submarine powered by a lead-cooled fast reactor, and achieving the purpose of enhancing the intrinsic safety of the reactor.
Description
LEAD-COOLED FAST REACTOR WASTE HEAT REMOVAL SYSTEM AND METHOD
TECHNICAL FIELD
The present invention belongs to the technical field of nuclear safety control, and particularly relates to an active and passive combined, intrinsically safe integrated lead-cooled fast reactor waste heat removal system and method.
BACKGROUND
In recent years, a lead-cooled fast reactor has a broad application prospect in the nuclear submarine power plant field due to a hard neutron spectrum, a strong heat carrying and transferring capacity of a coolant, and a compact structure. China is also vigorously promoting the development of a nuclear submarine powered by a lead-cooled fast reactor. A new nuclearpowered submarine must meet a safety standard, and one of the first problems is to ensure the release of heat from nuclear fuel under any circumstance.
At present, when a reactor core is shut down, heat energy released by nuclear fuel is mainly removed by a steam generator and a waste heat removal system; a fundamental way to accelerate the removal of the waste heat from the reactor core is to increase a coolant flow rate and a heat exchange efficiency; however, once a power failure condition occurs, the reactor core must be shut down, but at this time, a primary pump, a primary feedwater pump and a waste heat removal pump of the reactor core waste heat removal system will not work normally, resulting in that the heat of the reactor core cannot be removed in time and thus a reactor has a potential safety hazard.
SUMMARY
In view of a problem in the prior art that a reactor core cannot remove heat in time and thus has a safety hazard under a power failure condition, an objective of the present invention is to provide an active and passive combined, intrinsically safe integrated lead-cooled fast reactor waste heat removal system and method, by which, a pneumatic pump supplies water to a secondary side of a steam generator, thereby solving a problem that a heat release function of a secondary loop fails when a primary feedwater pump in an active reactor core cooling system fails to work normally under the power failure condition, and a magnetic heat exchanger natural circulation cooling loop independent of an active waste heat removal system is used in the active waste heat removal system, which overcomes a shortcoming that a traditional heat exchanger cannot exchange heat with the reactor core under the power failure condition, and thus realizes timely removal of the waste heat from the reactor core under the power failure condition.
To achieve the above objective, the present invention adopts the following technical solution:
i
2019101235 09 Oct 2019 a lead-cooled fast reactor waste heat removal system, including a reactor pressure vessel including a reactor core, and a containment vessel, a passive waste heat removal system being disposed above the containment vessel, where a magnetic heat exchanger active waste heat removal system and a waste heat-driven passive reactor core cooling system, which work independently, are further disposed above the containment vessel;
the magnetic heat exchanger active waste heat removal system includes a circulation loop composed of a water tank, a waste heat removal pump and a magnetic heat exchanger, the magnetic heat exchanger being located inside the reactor pressure vessel; and the waste heat-driven passive reactor core cooling system includes a primary loop composed of a primary feedwater pump, a steam generator, a heating pipe and a steam turbine which are interconnected by a pipeline, the heating pipe being located inside the reactor pressure vessel.
As a more preferable aspect of the above solution, the inside of the containment vessel is further provided with a primary pump for driving the flow of a coolant, thereby achieving the purpose of assisting in removing heat of the reactor core.
As a more preferable aspect of the above solution, the passive waste heat removal system includes a cooling water tank, an outlet pipe and a steam pipe; one end of the outlet pipe is connected to the bottom of the cooling water tank, and the other end is extended into the reactor pressure vessel; a steam collecting port of the steam pipe is located inside the reactor pressure vessel, and a tail end of the steam pipe is provided with a check valve, which is located below a liquid level of the cooling water tank.
As a more preferable aspect of the above solution, the waste heat-driven passive reactor core cooling system further includes a secondary loop, which is disposed in parallel with the primary loop, and is composed of a water supply tank, a pneumatic pump, the steam generator and the heating pipe which are interconnected.
When the reactor core is under a power failure condition, the waste heat-driven passive reactor core cooling system will use waste heat after shutdown to drive the pneumatic pump to convert heat energy into mechanical energy, and the pneumatic pump will replace the primary feedwater pump to pump water to a secondary side of the steam generator to ensure that the secondary loop is in a state of being cooled by water, thereby overcoming a shortcoming that the reactor core cooling system fails in the case of power loss, and preventing the leakage of a radioactive material caused by the damage of a plant pipeline.
As a more preferable aspect of the above solution, a water inlet end of the steam generator is connected in parallel with the primary feedwater pump and the pneumatic pump.
2019101235 09 Oct 2019
As a more preferable aspect of the above solution, two sides of the passive waste heat removal system are symmetrically provided with two magnetic heat exchanger active waste heat removal systems.
As a more preferable aspect of the above solution, the magnetic heat exchanger includes a heat exchanger container, an upper end cover, a lower end cover, a magnetic shielding cover, and a spiral heat exchange pipe; the heat exchanger container, the upper end cover and the lower end cover form a hollow cavity by an interference fit; a water inlet and a water outlet of the spiral heat exchange pipe pass through central circular holes of the lower end cover and the upper end cover to communicate with the waste heat removal pump and the water tank respectively; upper and lower ends of the heat exchanger container are connected to the magnetic shielding cover by magnetic attraction; upper and lower end side walls of the heat exchanger container are respectively provided with a plurality of liquid inlets; a lower part of the liquid inlets is provided with a ring for limiting the magnetic shielding cover.
As a more preferable aspect of the above solution, the liquid inlets have a square shape, and the plurality of liquid inlets are uniformly distributed along the same circumference of a side wall of the heat exchanger container.
Another objective of the present invention is to provide a waste heat removal method for the lead-cooled fast reactor waste heat removal system, including the following steps:
51, when a reactor is working normally, transferring heat energy generated in a reactor core to a coolant in a reactor pressure vessel, so that the coolant absorbs heat to rise to exchange heat with water in a heating pipe, and the water in the heating pipe is heated to evaporate into a steam generator for vaporization, and then enters a steam turbine;
52, returning the coolant after the heat exchange in the step SI to a lower part of the reactor core under a driving action of a primary pump; determining whether the reactor core has a normal shutdown condition, and if yes, performing step S3 during heat exchange between the coolant and the steam turbine, otherwise continuing the steps SI and S2;
53, turning a waste heat removal pump on, and involving a magnetic heat exchanger in a heat exchange process to realize waste heat removal; determining whether the reactor core has a power failure condition, and if yes, proceeding to step S4, otherwise continuing the step S3; and
54, sliding a magnetic shielding cover of the magnetic heat exchanger down, and turning on a passive waste heat removal system and a pneumatic pump valve to remove waste heat simultaneously.
As a more preferable aspect of the above solution, the coolant is a lead-bismuth alloy coolant.
As a more preferable aspect of the above solution, the step S4 is specifically:
2019101235 09 Oct 2019 (1) sliding the magnetic shielding cover of the magnetic heat exchanger down, so that the coolant enters the heat exchanger through a channel to maintain part of a waste heat removal capacity under the action of natural circulation;
(2) opening an outlet pipe of the passive waste heat removal system and a valve on the steam pipe, so that water in a cooling water tank flows from the outlet pipe into the reactor core under the action of gravity, and boils after directly coming into contact with the coolant, and returning steam generated from heated water to the cooling water tank through the steam pipe; and (3) enabling the heated rising coolant to exchange heat with a heating pipe of a waste heatdriven passive reactor core cooling system, so that water in the heat pipe is heated to evaporate into the steam turbine, and when a steam pressure in a primary loop is detected to be too low, stopping the steam turbine, and turning the pneumatic pump on to activate a secondary loop, so that water in a water supply tank is carried to the heating pipe for heat exchange.
Compared with the prior art, the present invention has the following beneficial effects:
(1) the waste heat removal system of the present invention is composed of the three subsystems, namely the magnetic heat exchanger active waste heat removal system, the waste heat-driven passive reactor core cooling system and the lead-bismuth and water direct contact passive waste heat removal system, which work independently and effectively avoid a common mode failure;
(2) based on an existing waste heat removal system of a system, the present invention innovatively uses the pneumatic pump to supply water to the secondary side of the steam generator in the active waste heat removal system, solving a problem that a heat release function of the secondary loop fails in the case that the primary feedwater pump in the active waste heat removal system fails under a power failure condition;
(3) based on an N + 1 principle, the active waste heat removal system adopts the magnetic heat exchanger, and innovatively designs a natural circulation cooling loop independent of the active waste heat removal system, and the two waste heat removal systems act independently, overcoming a shortcoming that a traditional heat exchanger cannot exchange heat with the reactor core under a power failure condition, meeting a defense-in-depth principle, and conforming to an international standard; and (4) with the use of the pneumatic pump and the introduction of the independent natural circulation cooling loop of the magnetic heat exchanger, the present invention greatly increases the flow rate of the coolant in the reactor core, and accelerates the removal of the waste heat from the reactor core under a power failure condition, thereby safeguarding not only the reactor, but also the research of a nuclear submarine powered by a lead-cooled fast reactor, and achieving the purpose of enhancing the intrinsic safety of the reactor.
2019101235 09 Oct 2019
BRIEF DESCRIPTION OF THE DRAWINGS
FIG. 1 is a structural schematic diagram of a lead-cooled fast reactor waste heat removal system according to the present invention;
FIG. 2 is a schematic structural diagram of a magnetic heat exchanger active waste heat removal system according to the present invention;
FIG. 3 is a schematic diagram of an explosion structure of a magnetic heat exchanger according to the present invention;
FIG. 4 is a schematic structural diagram of a magnetic heat exchanger under a power-on turned-off state according to the present invention;
FIG. 5 is a schematic structural diagram of a magnetic heat exchanger under a power-off tumed-on state according to the present invention;
FIG. 6 is a flowchart of a waste heat removal method of a lead-cooled fast reactor waste heat removal system under normal work of a reactor;
FIG. 7 is a flowchart of a waste heat removal method of a lead-cooled fast reactor waste heat removal system under a normal shutdown condition of a reactor core; and
FIG. 8 is a flowchart of a waste heat removal method of a lead-cooled fast reactor waste heat removal system under a power failure condition of a reactor core.
In the figures: 1. reactor pressure vessel; 2. reactor core; 3. primary pump; 4. steam generator; 5. magnetic heat exchanger; 501. heat exchanger container; 502. upper end cover; 503. lower end cover; 504. magnetic shielding cover; 505. spiral heat exchange pipe; 506. ring; 507. liquid inlet; 508. circular hole; 509. water inlet; 510. water outlet; 6. water supply tank; 7. pneumatic pump; 8. waste heat removal pump; 9. primary feedwater pump; 10. check valve; 11. cooling water tank; 12. steam collecting port; 13. outlet pipe; 14. containment container; 15. steam turbine; and 16. water tank.
DETAILED DESCRIPTION
To make the objectives, technical solutions, and advantages of the present invention clearer and more understandable, the following describes the present invention in more detail with reference to embodiments. It should be understood that the embodiments described herein are merely intended to explain the present invention, rather than to limit the present invention. Unless otherwise stated, the reagents, methods and devices employed in the present invention are conventional reagents, methods and devices in the art.
Embodiment 1
Referring to FIG. 1 to FIG. 5, a lead-cooled fast reactor waste heat removal system, including a reactor pressure vessel 1 that includes a reactor core 2, and a containment vessel 14, a passive waste heat removal system being disposed above the containment vessel 14, where a magnetic
2019101235 09 Oct 2019 heat exchanger active waste heat removal system and a waste heat-driven passive reactor core 2 cooling system, which work independently, are further disposed above the containment vessel 14;
the magnetic heat exchanger active waste heat removal system includes a circulation loop composed of a water tank 16, a waste heat removal pump 8 and a magnetic heat exchanger 5, the magnetic heat exchanger 5 being located inside the reactor pressure vessel 1; and the waste heat-driven passive reactor core cooling system includes a primary loop composed of a primary feedwater pump 9, a steam generator 4, a heating pipe and a steam turbine which are interconnected by a pipeline, the heating pipe being located inside the reactor pressure vessel 1.
The waste heat-driven passive reactor core cooling system injects water into the heating pipe through the primary feedwater pump 9; the water in the heating pipe exchanges heat with a leadbismuth alloy coolant of the reactor core, and is vaporized in the steam generator 4 to take the heat of the reactor core 2 away; thus, the heat exchange efficiency of the lead-bismuth alloy coolant can be improved; at the same time, after vaporization, cooling water of the whole system can be returned to the water tank 16 for condensation, thereby achieving a closed circulation to prevent leakage of a radioactive material, and thus ensuring the integrity of a reactor boundary, and enhancing the intrinsic safety of a reactor; in addition, due to an increased temperature difference between upper and lower lead-bismuth alloy coolants in the reactor core 2, a density difference between the lead-bismuth alloy coolants is also increased, resulting in an increased pressure difference between the upper and lower lead-bismuth alloy coolants, and thus further improving a natural circulation capacity of the lead-bismuth alloy coolant in the reactor and a heat exchange rate of the coolant with the water in the heating pipe, and accelerating the heat dissipation of the reactor core 2.
The passive waste heat removal system includes a cooling water tank 11, an outlet pipe 13 and a steam pipe; one end of the outlet pipe 13 is connected to the bottom of the cooling water tank 11, and the other end is extended into the reactor pressure vessel 1; a steam collecting port 12 of the steam pipe is located inside the reactor pressure vessel 1, and a tail end of the steam pipe is provided with a check valve 10, which is located below a liquid level of the cooling water tank 11.
After receiving a power failure signal, the outlet pipe 13 of the passive waste heat removal system and upstream and downstream pipeline valves of the steam pipe are opened, and under the action of gravity, water in the cooling water tank 11 flows from the outlet pipe 13 into the reactor core 2; the water directly contacts with the lead-bismuth alloy coolant, boils and evaporates after being heated, returns from the steam collecting port 12 of the steam pipe to the cooling water tank 11 through an upstream pipeline, and can be cooled for recycling; due to the water that absorbs heat by boiling and evaporating, the temperature of the upper lead-bismuth alloy coolant of the
2019101235 09 Oct 2019 reactor core 2 is decreased, and the density difference is increased, so that the natural circulation effect of the coolant is remarkably improved, and the heat removal of the reactor core 2 is accelerated.
Further, the inside of the containment vessel 14 is provided with a primary pump 3 for driving the flow of the lead-bismuth alloy coolant, thereby achieving the purpose of assisting in removing heat of the reactor core.
Specifically, referring to FIG. 3, the magnetic heat exchanger 5 includes a heat exchanger container 501, an upper end cover 502, a lower end cover 503, a magnetic shielding cover 504, and a spiral heat exchange pipe 505; the heat exchanger container 501, the upper end cover 502 and the lower end cover 503 form a hollow cavity by an interference fit; a water inlet 509 and a water outlet 510 of the spiral heat exchange pipe 505 respectively pass through central circular holes 508 of the lower end cover 503 and the upper end cover 502 to communicate with the waste heat removal pump 8 and the water tank 16 respectively; upper and lower ends of the heat exchanger container 501 are connected to the magnetic shielding cover 504 by magnetic attraction; upper and lower end side walls of the heat exchanger container 501 are respectively provided with a plurality of liquid inlets 507; a lower part of the liquid inlets 507 is provided with a ring 504 for limiting the magnetic shielding cover 506.
During normal shutdown, the water tank 16 and the waste heat removal pump 8 of the magnetic heat exchanger active heat removal system are connected to supply water to the spiral heat exchange pipe 505; then the magnetic heat exchanger 5 is powered off, and the magnetic shielding cover 504 loses a magnetic force and is slid open under the action of gravity; an upper edge of the magnetic shielding cover 504 is stopped under the limit of the ring 506, and the lead coolant in the reactor core 2 enters the hollow cavity of the magnetic heat exchanger 5 through the liquid inlets 507 and exchanges heat with the water in the spiral heat exchange pipe 505, so that waste heat in the reactor core 2 is removed.
Under a power failure condition, the waste heat removal pump 8 stops working, and the magnetic shielding cover 504 loses a magnetic force and is opened under the action of gravity; the lead-bismuth alloy coolant in the reactor core 2 enters the hollow cavity of the magnetic heat exchanger 5 through the liquid inlets 507 to ensure the normal work of the magnetic heat exchanger 5, and by means of natural circulation, some functions of the magnetic heat exchanger active heat removal system are maintained, thereby providing a guarantee for the cooling of the reactor core 2 by the waste heat removal, and avoiding a shortcoming that the active waste heat removal system fails under the power failure condition.
2019101235 09 Oct 2019
Further, the liquid inlets 507 have a square shape, and the plurality of liquid inlets 507 are uniformly distributed along the same circumference of a side wall of the heat exchanger container 501.
When a reactor normally works, a waste heat removal method of the lead-cooled fast reactor waste heat removal system, as shown in FIG. 6, includes the following steps:
51, transfer heat energy generated in a reactor core 2 to a lead-bismuth coolant in a reactor pressure vessel 1, so that the lead-bismuth alloy coolant absorbs heat to rise to exchange heat with water in a heating pipe, and the water in the heating pipe is heated to evaporate into a steam generator 4 for vaporization, and then enters a steam turbine 15 to generate electricity; and
52, return the lead-bismuth alloy coolant with a lower temperature and a greater density after the heat exchange in the step S1 to a lower part of the reactor core 2 under a driving action of a primary pump 3 to realize circulation of the lead-bismuth alloy coolant;
when the reactor core 2 has a normal shutdown condition, the waste heat removal method of the lead-cooled fast reactor waste heat removal system, as shown in FIG. 7, includes the following steps:
51, transfer heat energy generated in the reactor core 2 to a lead-bismuth coolant in a reactor pressure vessel 1, so that the lead-bismuth coolant absorbs heat to rise to exchange heat with water in a heating pipe, and the water in the heating pipe is heated to evaporate into a steam generator 4 for vaporization, and then enters a steam turbine 15 to generate electricity;
52, return the lead-bismuth alloy coolant with a lower temperature and a greater density after the heat exchange in the step S1 to a lower part of the reactor core 2 under a driving action of a primary pump 3, so that the heat power of the reactor core 2 is further decreased, and the temperature of the lead-bismuth alloy coolant is obviously decreased, and stop the steam generator 4; and
53, turn a waste heat removal pump 8 on, involve a magnetic heat exchanger 5 in a heat exchange process to take away decay heat and sensible heat of the reactor core 2, and maintain the reactor in a normal shutdown state to realize waste heat removal;
when the reactor core 2 has a power failure condition, the step S4 of the waste heat removal method of the lead-cooled fast reactor waste heat removal system, as shown in FIG. 8, is specifically:
a primary pump 3, a primary feedwater pump 9 and a waste heat removal pump 8 cannot work normally due to power loss, and fail after one minute of idling; at the moment of the power failure, as a magnetic heat exchanger 5 of an active waste heat removal system loses power, a magnetic shielding cover of the magnetic heat exchanger 5 slides down, and the lead-bismuth alloy coolant enters a hollow cavity of the magnetic heat exchanger 5 through a liquid inlet 507,
2019101235 09 Oct 2019 to maintain part of a waste heat removal capacity of the reactor core 2 under the action of natural circulation; at the same time, an outlet pipe 13 of a passive waste heat removal system and a valve on a steam pipe are opened, and water in a cooling water tank 11 flows from the outlet pipe 13 into the reactor core 2 under the action of gravity; the water boils after directly coming into contact with the lead-bismuth alloy coolant, and steam generated from heated water is returned to the cooling water tank 11 through the steam pipe; the lead-bismuth alloy coolant is heated to rise to exchange heat with a heating pipe of a waste heat-driven passive reactor core 2 cooling system, so that the water in the heat pipe is heated to evaporate into a steam turbine 15; when a steam pressure in a primary loop is detected to be too low, the steam turbine 15 stops working.
Embodiment 2
The present embodiment provides lead-cooled fast reactor waste heat removal system, where based on Embodiment 1, the waste heat-driven passive reactor core cooling system further includes a secondary loop, which is disposed in parallel with the primary loop, and is composed of a water supply tank 6, a pneumatic pump 7, the steam generator 4 and the heating pipe which are interconnected; a water inlet end of the steam generator 4 is connected in parallel with the primary feedwater pump 9 and the pneumatic pump 7.
When the reactor core 2 has a power failure condition, in the step S4, the pneumatic pump 7 is opened to remove waste heat of the reactor core 2 while the magnetic heat exchanger 5 and the passive waste heat removal system remove waste heat of the reactor core 2, and the specific step is as follows:
the heated rising lead-bismuth coolant exchanges heat with a heating pipe of a waste heatdriven passive reactor core 2 cooling system, so that water in the heat pipe is heated to evaporate into the steam turbine 15; when a steam pressure in a primary loop is detected to be too low, a valve of the pneumatic pump 7 is completely opened till a pipeline of the steam turbine 15 is closed, and remaining steam drives the pneumatic pump 7 to pump water from a water supply tank 6 into a heating pipe of a secondary loop, and the water in the water supply tank exchanges heat with the lead-bismuth alloy coolant in the reactor pressure vessel 1, thereby further accelerating the continued cooling circulation of the lead-bismuth alloy coolant.
Embodiment 3
The present embodiment provides a lead-cooled fast reactor waste heat removal system, where based on Embodiment 2, two sides of the passive waste heat removal system are symmetrically provided with two magnetic heat exchanger active waste heat removal systems; by disposing the two magnetic heat exchanger active waste heat removal systems to run simultaneously, the waste heat removal of the reactor core 2 can be further accelerated when the reactor core 2 is under normal shutdown and power failure conditions.
2019101235 09 Oct 2019
Embodiment 4
The present embodiment provides a lead-cooled fast reactor waste heat removal system, where based on Embodiment 3, two sides of the passive waste heat removal system are symmetrically provided with two waste heat-driven passive reactor core cooling systems; by disposing the two waste heat-driven passive reactor core cooling systems, the waste heat removal capacity of the reactor core 2 can improved under any conditions.
The above are merely illustrative embodiments of the present invention, and are not intended to limit the present invention in terms of form and substance. It should be noted that, improvements and additions made by those of ordinary skill in the art without departing from the method of the present invention shall be considered as falling within the protection scope of the present invention, modifications and equivalent variations made to the technical contents disclosed above by those skilled in the art without departing from the spirit and scope of the present invention shall be equivalent embodiments of the present invention, and modifications and equivalent variations made to the above embodiments in accordance with the technical essence of the present invention shall belong to the protection scope of the present invention.
Claims (2)
- (1) sliding the magnetic shielding cover of the magnetic heat exchanger down, so that the coolant enters the heat exchanger through a channel to maintain part of a waste heat removal capacity under the action of natural circulation;1. A lead-cooled fast reactor waste heat removal system, comprising a reactor pressure vessel (I) that comprises a reactor core (2), and a containment vessel (14), a passive waste heat removal system being disposed above the containment vessel (14), wherein a magnetic heat exchanger active waste heat removal system and a waste heat-driven passive reactor core cooling system, which work independently, are further disposed above the containment vessel (14);the magnetic heat exchanger active waste heat removal system comprises a circulation loop composed of a water tank (16), a waste heat removal pump (8) and a magnetic heat exchanger (5), the magnetic heat exchanger (5) being located inside the reactor pressure vessel (1);the waste heat-driven passive reactor core cooling system comprises a primary loop composed of a primary feedwater pump (9), a steam generator, a heating pipe and a steam turbine (15) which are interconnected by a pipeline, the heating pipe being located inside the reactor pressure vessel (1).2. The lead-cooled fast reactor waste heat removal system according to claim 1, wherein the passive waste heat removal system comprises a cooling water tank (11), an outlet pipe (13) and a steam pipe; one end of the outlet pipe (13) is connected to the bottom of the cooling water tank (II) , and the other end is extended into the reactor pressure vessel (1); a steam collecting port (12) of the steam pipe is located inside the reactor pressure vessel (1), and a tail end of the steam pipe is provided with a check valve (10), which is located below a liquid level of the cooling water tank (11).3. The lead-cooled fast reactor waste heat removal system according to claim 1, wherein the waste heat-driven passive reactor core cooling system further comprises a secondary loop, which is disposed in parallel with the primary loop, and is composed of a water supply tank (6), a pneumatic pump (7), the steam generator (4) and the heating pipe which are interconnected.4. The lead-cooled fast reactor waste heat removal system according to claim 3, wherein a water inlet end of the steam generator (4) is connected in parallel with the primary feedwater pump (9) and the pneumatic pump.5. The lead-cooled fast reactor waste heat removal system according to claim 1, wherein two sides of the passive waste heat removal system are symmetrically provided with two magnetic heat exchanger (5) active waste heat removal systems.6. The lead-cooled fast reactor waste heat removal system according to claim 1, wherein the magnetic heat exchanger (5) comprises a heat exchanger container (501), an upper end cover (502) , a lower end cover (503), a magnetic shielding cover (504), and a spiral heat exchange pipe (505); the heat exchanger container (501), the upper end cover (502) and the lower end cover (503) form a hollow cavity by an interference fit; a water inlet (509) and a water outlet (510) of2019101235 09 Oct 2019 the spiral heat exchange pipe (505) respectively pass through central circular holes (508) of the lower end cover (503) and the upper end cover (502) to communicate with the waste heat removal pump (8) and the water tank (16) respectively; upper and lower ends of the heat exchanger container (501) are connected to the magnetic shielding cover (504) by magnetic attraction; upper and lower end side walls of the heat exchanger container (501) are respectively provided with a plurality of liquid inlets (507); a lower part of the liquid inlets (507) is provided with a ring (504) for limiting the magnetic shielding cover (506).7. The lead-cooled fast reactor waste heat removal system according to claim 6, wherein the liquid inlets (507) have a square shape, and the plurality of liquid inlets (507) are uniformly distributed along the same circumference of a side wall of the heat exchanger container (501).8. A waste heat removal method for the lead-cooled fast reactor waste heat removal system according to any one of claims 1 to 7, comprising the following steps:51, when a reactor is working normally, transferring heat energy generated in a reactor core to a coolant in a reactor pressure vessel, so that the coolant absorbs heat to rise to exchange heat with water in a heating pipe, and the water in the heating pipe is heated to enter a steam generator for vaporization, and then enters a steam turbine;52, returning the coolant after the heat exchange in the step SI to a lower part of the reactor core under a driving action of a primary pump; determining whether the reactor core has a normal shutdown condition, and if yes, performing step S3 during heat exchange between the coolant and the steam turbine, otherwise continuing the steps SI and S2;53, turning a waste heat removal pump on, and involving a magnetic heat exchanger in a heat exchange process to realize waste heat removal; determining whether the reactor core has a power failure condition, and if yes, proceeding to step S4, otherwise continuing the step S3; and54, sliding a magnetic shielding cover of the magnetic heat exchanger down, and turning on a passive waste heat removal system and a pneumatic pump valve to remove waste heat simultaneously.9. The waste heat removal method of the lead-cooled fast reactor waste heat removal system according to claim 8, wherein the coolant is a lead-bismuth alloy coolant.10. The waste heat removal method of the lead-cooled fast reactor waste heat removal system according to claim 8, wherein the step S4 is specifically:
- (2) opening an outlet pipe of the passive waste heat removal system and a valve on the steam pipe, so that water in a cooling water tank flows from the outlet pipe into the reactor core under2019101235 09 Oct 2019 the action of gravity, and boils after directly coming into contact with the coolant, and returning steam generated from heated water to the cooling water tank through the steam pipe; and (3) enabling the heated rising coolant to exchange heat with a heating pipe of a waste heatdriven passive reactor core cooling system, so that water in the heat pipe is heated to evaporate into the steam turbine, and when a steam pressure in a primary loop is detected to be too low, stopping the steam turbine, and turning the pneumatic pump on to activate a secondary loop, so that water in a water supply tank is carried to the heating pipe for heat exchange.
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| CN201910276050.5 | 2019-04-08 | ||
| CN201910276050.5A CN110010255B (en) | 2019-04-08 | 2019-04-08 | Lead-cooled fast reactor waste heat discharging system and discharging method |
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| CN111128414A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111430050B (en) * | 2020-04-24 | 2024-06-18 | 上海核工程研究设计院股份有限公司 | Passive residual heat removal system for secondary side of reactor and use method |
| CN113744899B (en) * | 2021-06-02 | 2024-06-18 | 上海核工程研究设计院股份有限公司 | Nuclear reactor start-up heating system |
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| DE2316066C2 (en) * | 1973-03-30 | 1982-05-27 | Siemens AG, 1000 Berlin und 8000 München | Nuclear reactor, especially pressurized water reactor |
| EP0418701B1 (en) * | 1989-09-19 | 1994-06-01 | Mitsubishi Jukogyo Kabushiki Kaisha | Reactor core decay heat removing system in a pressurized water reactor |
| UA81419C2 (en) * | 2005-01-17 | 2008-01-10 | Севастопольский Национальный Технический Университет | Passive system for rejection of residual heat generation |
| CN103295656B (en) * | 2012-02-29 | 2017-12-26 | 上海核工程研究设计院 | Diversified engineered safety system for nuclear reactor |
| CN103632737A (en) * | 2012-08-20 | 2014-03-12 | 中国核动力研究设计院 | Passive waste heat discharge system of nuclear power station steam generator secondary side |
| KR101617161B1 (en) * | 2014-10-15 | 2016-05-03 | 한국원자력연구원 | Reactor with safety system using steam pressure and operating method for the reactor |
| KR20170000601A (en) * | 2015-06-24 | 2017-01-03 | 김영선 | Passive Safety System of Nuclear Power generation system |
| CN106409353B (en) * | 2016-09-26 | 2018-09-07 | 南华大学 | It is a kind of based on gaslift liquid metal cooling the multi-functional heap of pool reactor in hot separating system |
| CN107507654B (en) * | 2017-08-03 | 2019-07-26 | 中国核工业第五建设有限公司 | The installation method of air guide device |
| CN209859630U (en) * | 2019-04-08 | 2019-12-27 | 南华大学 | Lead-cooled fast reactor waste heat discharge system |
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| CN111128414A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
| CN111128414B (en) * | 2019-12-31 | 2022-07-26 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
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| CN110010255A (en) | 2019-07-12 |
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