CN115019983A - Heat pipe stack system design and passive heat pipe stack waste heat discharge system and method - Google Patents
Heat pipe stack system design and passive heat pipe stack waste heat discharge system and method Download PDFInfo
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- CN115019983A CN115019983A CN202210569162.1A CN202210569162A CN115019983A CN 115019983 A CN115019983 A CN 115019983A CN 202210569162 A CN202210569162 A CN 202210569162A CN 115019983 A CN115019983 A CN 115019983A
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- 239000002918 waste heat Substances 0.000 title claims abstract description 22
- 238000000034 method Methods 0.000 title claims abstract description 12
- 239000000446 fuel Substances 0.000 claims abstract description 37
- 238000006243 chemical reaction Methods 0.000 claims abstract description 26
- 239000012530 fluid Substances 0.000 claims abstract description 24
- 238000009434 installation Methods 0.000 claims abstract description 4
- 230000000712 assembly Effects 0.000 claims description 20
- 238000000429 assembly Methods 0.000 claims description 20
- 239000007789 gas Substances 0.000 claims description 8
- 238000005086 pumping Methods 0.000 claims 1
- 230000008569 process Effects 0.000 abstract description 3
- 239000003758 nuclear fuel Substances 0.000 description 7
- 230000002457 bidirectional effect Effects 0.000 description 6
- 238000005516 engineering process Methods 0.000 description 6
- 230000005494 condensation Effects 0.000 description 3
- 238000009833 condensation Methods 0.000 description 3
- 230000008020 evaporation Effects 0.000 description 3
- 238000001704 evaporation Methods 0.000 description 3
- 230000003068 static effect Effects 0.000 description 3
- 230000008859 change Effects 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000009417 prefabrication Methods 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
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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
-
- 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
- G21C15/257—Promoting flow of the coolant using heat-pipes
-
- 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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
The invention belongs to the technical field of heat pipe reactors, and particularly relates to a heat pipe reactor system design and a passive heat pipe reactor waste heat discharge system and method, wherein the system comprises the following steps: the two sides of the reactor core are respectively inserted with a heat pipe; the fuel is designed to be hexagonal prism honeycomb hole shape, the inner part of the heat pipe installation jack is tightly contacted with the fuel for direct heat transfer; the first heat pipe heat exchanger exchanges heat with the heat pipe on one side of the reactor core; the second heat pipe heat exchanger exchanges heat with the heat pipe on the other side of the reactor core; the heat-driven conversion system is used for feeding cold fluid to the first heat pipe heat exchanger and the second heat pipe heat exchanger and absorbing heat to form hot fluid to return; the invention can reduce the heat transfer path in the heat transfer process of the reactor core, reduce the thermal resistance, simultaneously reduce the requirement on the length of the high-temperature heat pipe, and realize the infinite passive reactor core waste heat discharge.
Description
Technical Field
The invention belongs to the technical field of heat pipe reactors, and particularly relates to a heat pipe reactor system design and a passive heat pipe reactor waste heat discharge system and method.
Background
The micro reactor is a unique small reactor system, usually the electric power of the micro reactor system is less than 10MW, the micro reactor has the characteristics of factory prefabrication, device transportability, operation self-adjustment, rapid deployment and the like, the design is greatly simplified, the safety and the flexibility are obviously improved, and the micro reactor is highly suitable for special application scenes such as space, ocean, remote areas, mobile power supplies and the like. As one of the main technical routes of the micro-reactor, the heat pipe reactor has the advantages of full static state, passive state, small size and weight, self-adaption of heat transfer power and the like.
The heat pipe reactor is usually designed as a solid core, the heat transfer inside the core is usually mainly solid or air gap heat conduction, and the heat transfer process of the core has large thermal resistance, resulting in large temperature drop from the core to the secondary side. Therefore, in the design of fuel and core, the heat transfer path should be reduced as much as possible, the thermal resistance inside the core should be reduced, and the temperature on the secondary side should be increased, so as to output high-quality heat energy.
The heat pipes are the core heat transfer elements of the heat pipe stack, and the heat pipe stack usually needs to carry longer heat pipes to match larger core volume and power output. However, the mature degree of the existing long heat pipe manufacturing technology is low, and the length of the heat pipe which can be manufactured in an engineering mode is one of important factors which restrict the design size of the reactor core.
The efficient phase change heat transfer inside the heat pipes can passively conduct the heat of the reactor core to the outside of the reactor core and discharge the heat by using a thermodynamic conversion system as a conventional heat sink. When the normal heat trap (i.e. the thermal power conversion system) of the reactor fails due to accidents and the like, the reactor is stopped suddenly, the nuclear fuel does not perform fission reaction any more, but decays to release heat. The reactor is provided with a safety-level emergency heat trap system which is used as a means for discharging the residual heat of the reactor core decay in an accident.
However, the power level of the heat pipe stack is usually low, and if a set of standby heat trap system is additionally arranged on the heat pipe stack, on one hand, the system is complex and the reliability is reduced; on the other hand, additional system equipment is introduced, so that the unit power cost of the heat pipe stack is increased, and the economic competitiveness of the heat pipe stack technology is reduced.
Disclosure of Invention
The invention aims to provide a heat pipe reactor system design, which can reduce heat transfer paths in the heat transfer process of a reactor core, reduce thermal resistance and reduce the requirement on the length of a high-temperature heat pipe; in addition, the passive heat pipe stack waste heat discharge system and method can discharge waste heat in a passive and infinite time. The invention is realized by the following technical scheme:
in a first aspect, the present invention provides a heat pipe stack system design, comprising:
the reactor core internally comprises a plurality of heat pipe channels, and a heat pipe is respectively inserted from two sides of the reactor core in the same heat pipe channel; the fuel is designed to be hexagonal prism honeycomb hole shape, the inner part of the heat pipe installation jack is tightly contacted with the fuel for direct heat transfer;
the first heat pipe heat exchanger exchanges heat with the heat pipe on one side of the reactor core;
the second heat pipe heat exchanger exchanges heat with the heat pipe on the other side of the reactor core;
and the thermal power conversion system is used for feeding cold fluid to the first heat pipe heat exchanger and the second heat pipe heat exchanger and absorbing heat to form hot fluid to return.
As a further technical solution, the thermodynamic conversion system includes a gas turbine, a compressor, and a generator, which are coaxially arranged, and the compressor pumps cold fluid to the first heat pipe heat exchanger and the second heat pipe heat exchanger and absorbs heat to become hot fluid, which returns to the gas turbine to drive the compressor and the generator to rotate.
As a further aspect, the core includes a plurality of fuel assemblies, and each fuel assembly is provided with the fuel.
As a further technical solution, the core further comprises a plurality of control rod assemblies.
As a further technical scheme, the fuel assembly is arranged in a hexagonal prism shape, and the control rod assembly is arranged in the same hexagonal prism shape to be matched with the fuel assembly.
As a further technical scheme, a control rod advancing channel is arranged in the center of the control rod assembly.
As a further technical scheme, the periphery of a combined body formed by all the control rod assemblies and all the fuel assemblies is wrapped with a reflecting layer.
As a further technical scheme, the reflecting layer is provided with a control rotary drum.
In a second aspect, the invention provides a passive heat pipe stack waste heat discharge, and the heat pipe stack system design as the first aspect is adopted, wherein a waste discharge inlet differential pressure disc is arranged on the lower side of the second heat pipe heat exchanger, and a waste discharge outlet differential pressure disc is arranged on the upper side of the second heat pipe heat exchanger.
In a third aspect, the present invention provides a passive heat pipe stack waste heat removal method, which adopts the passive heat pipe stack waste heat removal system of the second aspect, and comprises the following steps:
during normal operation, cold fluid is fed into the first heat pipe heat exchanger and the second heat pipe heat exchanger through the thermal power conversion system, heat is absorbed to become hot fluid, and thermal power conversion is achieved;
when the reactor is stopped or an accident occurs, the residual discharge inlet pressure difference disc and the residual discharge outlet pressure difference disc are passively opened, so that the heat exchanger space of the second heat pipe heat exchanger is communicated with the ambient atmosphere, and the heat of the reactor core is led out through the heat pipes to heat air so as to realize passive infinite waste heat discharge.
The beneficial effects of the invention are as follows:
(1) the nuclear fuel is designed into a hexagonal prism honeycomb hole shape, and the heat pipe is inserted into the hole and is in close contact with the nuclear fuel to directly transfer heat, so that the heat transfer path is reduced, the thermal resistance is reduced, the output heat source temperature is improved, the efficiency of a heat pipe stack is improved, and the economy of the heat pipe stack technology is enhanced.
(2) The heat pipes are respectively inserted from two end faces of the reactor core, the reactor core parts of the first heat pipe and the second heat pipe are heat pipe evaporation sections, and the parts of two sides of the reactor core positioned in the heat pipe heat exchanger are heat pipe condensation sections, so that a bidirectional heat pipe belt heating mode is formed, the requirement on the length of a high-temperature heat pipe is greatly reduced, the design of the reactor core size is not limited by the maturity of the manufacturing technology of a long heat pipe, the reliability is broken through, and the flexibility is embodied.
(3) The invention designs a heat-carrying mode by utilizing the static heat transfer characteristic of the heat pipe and the principle that the air inlet and outlet height difference drives natural circulation, can realize infinite long-term passive reactor core waste heat discharge under the condition of not needing external energy drive, ensures the integrity of reactor core nuclear fuel, and obviously improves the safety performance of the heat pipe reactor.
(4) The invention has the advantages that the heat exchange of the bidirectional heat pipe is carried out under the normal operation condition, the surplus heat is arranged on one side under the accident condition, the surplus heat arrangement system of the heat pipe stack is designed by fully utilizing the space of the existing heat pipe and the heat exchanger, the system design of the safety facility of the heat pipe stack is greatly simplified, additional safety-level equipment is not required to be configured, the reliability of the safety system is improved, and the economic competitiveness of the heat pipe stack technology is enhanced.
Drawings
The accompanying drawings, which are incorporated in and constitute a part of this specification, are included to provide a further understanding of the invention, and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description, serve to explain the invention and not to limit the invention. It will be further appreciated that the figures are for simplicity and clarity and have not necessarily been drawn to scale. The invention will now be described and explained with additional specificity and detail through the use of the accompanying drawings in which:
FIG. 1 shows a schematic diagram of a heat pipe stack system design and a waste heat removal system in an embodiment of the invention;
FIG. 2 shows a cross-sectional view of a heat pipe reactor core structure in the embodiment of the invention, which is shown in the direction A-A in FIG. 1.
In the figure: 1. a core; 11. a fuel assembly; 12. a control rod assembly; 13. a reflective layer; 14. controlling the rotary drum; 15. an outer wall of the core system; 111. a fuel; 112. a heat pipe; 2. a first heat pipe heat exchanger; 3. a second heat pipe heat exchanger; 4. a first heat pipe; 5. a second heat pipe; 6. a residual row inlet differential pressure disc; 7. a residual discharge port differential pressure disc; 8. a gas turbine; 9. a compressor; 10. an electric generator.
Detailed Description
The technical solutions in the exemplary embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention.
Example 1
As shown in fig. 1 and fig. 2, the present embodiment provides a high-efficiency heat pipe stack system and a passive heat pipe stack waste heat removal system, including:
the reactor core 1 is internally provided with a plurality of heat pipe channels, and one heat pipe is respectively inserted from the two sides of the reactor core in the same heat pipe channel; the fuel is designed to be hexagonal prism honeycomb hole shape, the inner part of the heat pipe installation jack is tightly contacted with the fuel for direct heat transfer;
the first heat pipe heat exchanger 2 exchanges heat with the heat pipe on one side of the reactor core 1;
the second heat pipe heat exchanger 3 exchanges heat with the heat pipe on the other side of the reactor core 1, a surplus discharge inlet differential pressure disc 6 is arranged on the lower side of the second heat pipe heat exchanger, and a surplus discharge outlet differential pressure disc 7 is arranged on the upper side of the second heat pipe heat exchanger;
and the thermal power conversion system feeds cold fluid to the first heat pipe exchanger 2 and the second heat pipe exchanger 3, absorbs heat and returns the heat as hot fluid.
In the present embodiment, the first heat pipe 4 exchanges heat with the first heat pipe exchanger 2, the second heat pipe 5 exchanges heat with the second heat pipe exchanger 3, the heat pipes are respectively inserted from two end surfaces of the core 1, the core portions of the first heat pipe 4 and the second heat pipe 5 are heat pipe evaporation sections, and the portions on two sides in the heat pipe exchangers are heat pipe condensation sections, so as to form a bidirectional heat pipe heat-transfer mode (as shown in fig. 1). The design greatly reduces the requirement on the length of the high-temperature heat pipe, and obviously improves the technical maturity of the heat pipe in the system design.
In addition, due to the design of the bi-directional heat pipe with heat, the length of the heat pipe and the design of the heat pipe heat exchanger corresponding to the heat pipe heat exchanger can be flexibly adjusted according to the requirement of the core thermal design, namely two different forms of heat pipes can be installed in the core.
When the reactor normally operates, a bidirectional heat pipe belt heat mode is adopted, the first heat pipe 4 and the second heat pipe 5 remove heat from the reactor core 1 to the normal first heat pipe heat exchanger 2 and the normal second heat pipe heat exchanger 3 at two sides, and then the heat is sent into cold fluid through the heat-dynamic conversion system to absorb the heat in the first heat pipe heat exchanger 2 and the second heat pipe heat exchanger 3 and becomes hot fluid to realize energy conversion in the heat-dynamic conversion system.
When the normal heat trap (i.e. the thermal power conversion system) of the reactor fails due to an accident or the like, the reactor is scrammed, the nuclear fuel does not perform fission reaction any more, and decay heat is generated. At the moment, the residual discharge inlet pressure difference disc 6 and the residual discharge outlet pressure difference disc 7 are opened in a passive mode, so that the space of the second heat pipe heat exchanger 3 (which is converted into a passive residual discharge heat exchanger when the reactor is stopped) is communicated with the ambient atmosphere, and the reactor is switched from a bidirectional heat pipe hot-belt mode to a single-side residual discharge operation mode. Due to the passive high-efficiency phase change heat transfer mechanism of the heat pipes, the second heat pipe 5 continuously guides the heat of the reactor core 1 out of the second heat pipe exchanger 3 to heat air. And because the second heat pipe exchanger 3 has certain height difference with two communicating ports of the ambient atmosphere, hot air is discharged from the residual discharge port pressure difference disc 7 at the upper part, and cold air in the external environment is sucked from the residual discharge port pressure difference disc 6 at the lower part, so that efficient passive infinite natural circulation belt heat is formed.
The hot mode designed by utilizing the static heat transfer characteristic of the heat pipe and the principle that the air inlet and outlet height difference drives natural circulation does not need any external energy source for driving, does not have time limitation, can realize infinite long-term passive reactor core waste heat discharge, ensures the integrity of reactor core nuclear fuel, and obviously improves the safety performance of the heat pipe reactor.
In addition, bidirectional heat pipe heat exchange is performed under the normal operation condition, and the surplus heat is performed on one side under the accident condition, so that the surplus heat system of the heat pipe stack is designed by fully utilizing the space of the existing heat pipe and heat exchanger, the system design of safety facilities of the heat pipe stack is greatly simplified, additional safety-level equipment is not required to be configured, the reliability of a safety system is improved, and the economic competitiveness of the heat pipe stack technology is enhanced.
As shown in fig. 1, the thermodynamic conversion system includes a gas turbine 8, a compressor 9 and a generator 10 which are coaxially arranged, and the compressor 9 pumps cold fluid to the first heat pipe exchanger 2 and the second heat pipe exchanger 3 and absorbs heat to become hot fluid which is returned to the gas turbine 8 so as to drive the compressor 9 and the generator 10 to rotate. The turbine 8 is provided with a thermal power conversion system air outlet, and the compressor 9 is provided with a thermal power conversion system air inlet.
As shown in fig. 2, the core 1 includes a plurality of fuel assemblies 11, the fuel assemblies 11 are arranged in a hexagonal prism shape, each fuel assembly 11 is provided with fuel 111, and a plurality of heat pipes 112 are inserted into the fuel 111, and the heat pipe 112 is one of the first heat pipe 4 and the second heat pipe 5. The fuel is directly contacted with the heat pipe for heat conduction, so that a heat transfer path is reduced, the thermal resistance from the fuel to the heat pipe is reduced, and the operating efficiency of the system is improved. It is understood that fuel 111 refers to nuclear fuel.
The heat transfer path inside the core is as shown in fig. 2, and the heat in the fuel 111 is transferred to the inside (evaporation stage) of the core 1 of the first heat pipe 4 and the second heat pipe 5 in a direct contact heat conduction manner. The heat transfer path outside the core 1 is shown in fig. 1. After absorbing heat inside the reactor core 1, the first heat pipe 4 and the second heat pipe 5 transfer heat to two ends (condensation sections) of the heat pipes in the first heat pipe heat exchanger 2 and the second heat pipe heat exchanger 3 through gas flow; the compressor 9 in the thermal power conversion system sends cold fluid into the first heat pipe exchanger 2 and the second heat pipe exchanger 3 to cool the first heat pipe 4 and the second heat pipe 5, and absorbs heat to become hot fluid which returns to the thermal power conversion system impulse turbine 8, so that the coaxial compressor 9 and the generator 10 are driven to rotate, and thermal power conversion is realized.
As shown in fig. 2, the fuel 111 is in the shape of honeycomb holes, and a heat pipe 112 is inserted into each honeycomb hole, so that the arrangement is more uniform, and the heat released by the fuel is uniformly and sufficiently absorbed.
The reactor core 1 further comprises a plurality of control rod assemblies 12, wherein the control rod assemblies 12 are arranged in the same hexagonal prism shape, mature rod-shaped absorbers are adopted, the arrangement is uniform, and the matching is tight. The size, number, location of the fuel assemblies 11 and control rod assemblies 12 and the number of heat pipes 112 in the fuel assemblies may be varied according to core design requirements and are not limited to the form shown in FIG. 2.
The control rod assembly 12 is provided with a control rod advancing channel in the center, and the start and stop of the reactor and the output power regulation can be realized by regulating the advancing distance of the control rods in the advancing channel.
The reflecting layer 13 is wrapped on the periphery of the combination formed by all the control rod assemblies 12 and all the fuel assemblies 11, so that the neutron utilization rate can be improved. The control drum 14 is disposed on the reflective layer 13, and reactivity adjustment of the core is performed by turning to the absorption surface or the reflective surface, thereby satisfying different requirements such as expansion of reactivity control range and backup emergency shutdown system.
Example 2
The embodiment provides a passive heat pipe stack waste heat removal method, which adopts the passive heat pipe stack waste heat removal system in embodiment 1, and comprises the following steps:
when the heat exchanger runs normally, cold fluid is fed into the first heat pipe heat exchanger 2 and the second heat pipe heat exchanger 3 through the heat-power conversion system, and heat is absorbed to be hot fluid to return, so that heat-power conversion is realized;
when the reactor is stopped or an accident occurs, the residual discharge inlet pressure difference disc 6 and the residual discharge outlet pressure difference disc 7 are passively opened, so that the heat exchanger space of the second heat pipe heat exchanger 3 is communicated with the ambient atmosphere, and the heat of the reactor core 1 is led out through the heat pipes 112 to heat air so as to realize passive residual heat discharge.
Although the present invention has been described with reference to the preferred embodiments, it is not intended to limit the present invention, and those skilled in the art can make variations and modifications of the present invention without departing from the spirit and scope of the present invention by using the methods and technical contents disclosed above.
Claims (10)
1. A heat pipe stack system design, comprising:
the reactor core internally comprises a plurality of heat pipe channels, and a heat pipe is respectively inserted from two sides of the reactor core in the same heat pipe channel; the fuel is designed to be hexagonal prism honeycomb hole shape, the inner part of the heat pipe installation jack is tightly contacted with the fuel for direct heat transfer;
the first heat pipe heat exchanger exchanges heat with the heat pipe on one side of the reactor core;
the second heat pipe heat exchanger exchanges heat with the heat pipe on the other side of the reactor core;
and the thermal conversion system feeds cold fluid to the first heat pipe heat exchanger and the second heat pipe heat exchanger, absorbs heat and returns hot fluid.
2. A heat pipe stack system design as claimed in claim 1 wherein said thermodynamic conversion system comprises a co-axial gas turbine, a compressor and a generator, said compressor pumping cold fluid to said first heat pipe exchanger and said second heat pipe exchanger and absorbing heat as hot fluid back to said gas turbine to rotate said compressor and said generator.
3. A heat pipe stack system design as claimed in claim 1 wherein said core comprises a plurality of fuel assemblies, each said fuel assembly being provided with said fuel.
4. A heat pipe stack system design as claimed in claim 3 wherein said core further comprises a plurality of control rod assemblies.
5. The design of a heat pipe stack system of claim 4, wherein the fuel assemblies are arranged in a hexagonal prism and the control rod assemblies are arranged in the same hexagonal prism to fit the fuel assemblies.
6. The design for a heat pipe stack system of claim 5 wherein the control rod assembly center is provided with a control rod travel channel.
7. A heat pipe stack system design as claimed in claim 4 wherein the combination of all of said control rod assemblies and all of said fuel assemblies is surrounded by a reflective layer.
8. A heat pipe stack system design as claimed in claim 7 wherein the reflective layer is configured with control drums.
9. A passive heat pipe stack waste heat removal system is designed by adopting the heat pipe stack system according to any one of claims 1 to 8, and is characterized in that a waste heat removal inlet differential pressure disc is arranged on the lower side of the second heat pipe heat exchanger, and a waste heat removal outlet differential pressure disc is arranged on the upper side of the second heat pipe heat exchanger.
10. A passive heat pipe stack waste heat removal method using the passive heat pipe stack waste heat removal system according to claim 9, characterized by comprising the steps of:
when the heat exchanger works normally, cold fluid is sent into the first heat pipe heat exchanger and the second heat pipe heat exchanger through the heat-power conversion system, and heat is absorbed to be changed into hot fluid to return, so that heat-power conversion is realized;
when the reactor is shut down or an accident occurs, the residual discharge inlet pressure difference disc and the residual discharge outlet pressure difference disc are passively opened, so that the heat exchanger space of the second heat pipe heat exchanger is communicated with the ambient atmosphere, and the heat of the reactor core is led out through the heat pipes to heat air so as to realize passive infinite-time residual heat discharge.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210569162.1A CN115019983A (en) | 2022-05-24 | 2022-05-24 | Heat pipe stack system design and passive heat pipe stack waste heat discharge system and method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210569162.1A CN115019983A (en) | 2022-05-24 | 2022-05-24 | Heat pipe stack system design and passive heat pipe stack waste heat discharge system and method |
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| Publication Number | Publication Date |
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| CN115019983A true CN115019983A (en) | 2022-09-06 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210569162.1A Withdrawn CN115019983A (en) | 2022-05-24 | 2022-05-24 | Heat pipe stack system design and passive heat pipe stack waste heat discharge system and method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN115019983A (en) |
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2022
- 2022-05-24 CN CN202210569162.1A patent/CN115019983A/en not_active Withdrawn
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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Application publication date: 20220906 |
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