CN113593727B - Supercritical carbon dioxide liquid lithium lead double-cold cladding - Google Patents
Supercritical carbon dioxide liquid lithium lead double-cold cladding Download PDFInfo
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- CN113593727B CN113593727B CN202110862732.1A CN202110862732A CN113593727B CN 113593727 B CN113593727 B CN 113593727B CN 202110862732 A CN202110862732 A CN 202110862732A CN 113593727 B CN113593727 B CN 113593727B
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- carbon dioxide
- supercritical carbon
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- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 title claims abstract description 96
- 238000005253 cladding Methods 0.000 title claims abstract description 84
- JWZCKIBZGMIRSW-UHFFFAOYSA-N lead lithium Chemical compound [Li].[Pb] JWZCKIBZGMIRSW-UHFFFAOYSA-N 0.000 title claims abstract description 83
- 229910002092 carbon dioxide Inorganic materials 0.000 title claims abstract description 48
- 239000001569 carbon dioxide Substances 0.000 title claims abstract description 48
- 239000007788 liquid Substances 0.000 title claims abstract description 28
- 238000001816 cooling Methods 0.000 claims abstract description 45
- 230000003014 reinforcing effect Effects 0.000 claims abstract description 27
- 230000035755 proliferation Effects 0.000 claims abstract description 26
- 239000002826 coolant Substances 0.000 claims abstract description 18
- 229910000831 Steel Inorganic materials 0.000 claims abstract description 15
- 239000010959 steel Substances 0.000 claims abstract description 15
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 claims abstract description 10
- 229910010271 silicon carbide Inorganic materials 0.000 claims abstract description 10
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 claims description 4
- 229910052721 tungsten Inorganic materials 0.000 claims description 4
- 239000010937 tungsten Substances 0.000 claims description 4
- 239000002131 composite material Substances 0.000 claims description 3
- 230000004927 fusion Effects 0.000 abstract description 12
- 230000000694 effects Effects 0.000 abstract description 11
- 230000007797 corrosion Effects 0.000 abstract description 8
- 238000005260 corrosion Methods 0.000 abstract description 8
- 238000010248 power generation Methods 0.000 abstract description 3
- 238000003466 welding Methods 0.000 abstract description 2
- 239000001307 helium Substances 0.000 description 11
- 229910052734 helium Inorganic materials 0.000 description 11
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 11
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 6
- 229910052722 tritium Inorganic materials 0.000 description 6
- 239000000463 material Substances 0.000 description 5
- 239000011248 coating agent Substances 0.000 description 4
- 238000000576 coating method Methods 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000000306 component Substances 0.000 description 2
- 230000007547 defect Effects 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 230000008642 heat stress Effects 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- 230000035882 stress Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000004913 activation Effects 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 239000000110 cooling liquid Substances 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000002294 plasma sputter deposition Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/13—First wall; Blanket; Divertor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/25—Maintenance, e.g. repair or remote inspection
-
- 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
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a supercritical carbon dioxide liquid lithium lead double-cold cladding, which adopts a sector cladding scheme, wherein each cladding sector comprises a plurality of proliferation units, the proliferation units are formed by welding a tungsten-attached U-shaped first wall processed by low-activation ferritic steel and a supercritical carbon dioxide inlet and outlet header, and the inside of each proliferation unit is divided into subchambers which are penetrated in the polar direction by a reinforcing plate and a cooling plate to form a lithium lead runner. Liquid lithium lead is shunted into the subchamber from the bottom of the cladding and flows out from the top of the cladding, so that nuclear heat in the proliferation area is taken away. The parallel flow channels in the U-shaped first wall are communicated with the supercritical carbon dioxide inlet and outlet header, supercritical carbon dioxide coolant is introduced, heat of the U-shaped first wall is discharged, and meanwhile the heat carrying capacity of the first wall is enhanced. And an electric and thermal insulating silicon carbide runner plug-in is arranged in the lithium lead runner, so that the MHD effect and corrosion problem are reduced, the cladding outlet temperature is increased, and an advanced cladding candidate scheme is provided for realizing efficient power generation of the fusion reactor.
Description
Technical Field
The invention belongs to the technical field of fusion reactor engineering, and mainly relates to a supercritical carbon dioxide liquid lithium lead double-cold cladding.
Background
The tritium proliferation cladding is a core component for realizing tritium self-holding, energy conversion and radiation shielding of the fusion reactor. The liquid cladding takes liquid lithium lead as tritium breeder and neutron multiplier, has simple structure, can realize online tritium extraction, is easy to expand to high temperature, and is generally regarded as a future advanced cladding scheme of the fusion reactor.
At present, three liquid lithium lead coating designs are mainly available at home and abroad. The self-cooling liquid lithium lead coating scheme is firstly proposed, liquid lithium lead is used as a tritium breeder, a neutron multiplier and a coolant, and meanwhile, low-activation steel is used as a structural material, but the flow rate of the liquid lithium lead is large, the Magnetohydrodynamic (MHD) effect of the lithium lead and a conductive steel wall in a strong magnetic field environment is strong, and the flow resistance of the lithium lead is large. The later improvement scheme adopts electrically insulating silicon carbide as a cladding structural material, so that the MHD effect can be effectively reduced, but the silicon carbide ceramic as the structural material needs to bear larger structural stress in a strong neutron irradiation environment, and the prior art is still immature. Then, in order to solve the MHD problem, another new solution of liquid lithium lead cooled independently is also proposed. Taking European Union as an example, a helium-cooled lithium lead cladding and a water-cooled lithium lead cladding are used as future fusion reactor candidate liquid cladding, liquid lithium lead is not used as a coolant, and only needs to flow slowly in the cladding to realize tritium extraction, the scheme can effectively reduce the MHD effect of a cladding proliferation area, but the lithium lead flow rate in a cladding header is still large, the MHD effect cannot be effectively relieved, in addition, the lower helium/water coolant outlet temperature is not high,limiting the thermal efficiency of the system. To improve the outlet temperature and the power generation efficiency, europe, the united states and china respectively propose a double-cooled lithium lead cladding concept. In this concept, lithium lead flows at a moderate flow rate in the proliferation zone, achieving self-cooling; at the same time, the high-pressure helium gas cools the cladding structures such as the first wall, the cooling plate and the like. Under the condition that an electric and heat-insulating silicon carbide insert is additionally arranged in the proliferation area, on one hand, the MHD effect is reduced, and on the other hand, the outlet temperature of lithium lead can reach more than 700 ℃, so that the heat efficiency is greatly improved. But the heat load of the first wall in the future fusion DEMO stack can reach MW/m 2 In order of magnitude, helium has difficulty adequately cooling the first wall due to the low heat loading.
The defects of the design schemes of the liquid lithium lead coating, which are related in the domestic and foreign researches, are summarized as follows: (1) The existing liquid lithium lead coating design is difficult to have the advantages of low MHD effect, low structural material corrosion, high thermal efficiency and the like due to multi-factor restriction. (2) The existing coolant scheme is difficult to meet the requirements of strong heat carrying capacity and high outlet temperature. The water cooling scheme has strong heat carrying capacity on the first wall, but the outlet temperature is not high, so that the heat efficiency is limited; helium cooling schemes, while achieving higher outlet temperatures, have limited cooling capacity for the first wall. In addition, the cladding nuclear heat is distributed in an exponential decay manner along the radial direction, so that the front region of the cladding is easy to be overtemperature due to insufficient cooling, and the steel structure of the front region and the rear region has large temperature difference, large stress and difficult design.
Disclosure of Invention
In order to solve the problems that the existing liquid lithium lead cladding is difficult to consider high-temperature high efficiency, strong heat carrying capacity and larger heat stress of a steel structure, the invention designs the supercritical carbon dioxide liquid lithium lead double-cold cladding, silicon carbide runner inserts with different heat conductivities and good high-temperature resistance, corrosion resistance and electric/thermal insulativity are arranged in different lithium lead runners, meanwhile, the supercritical carbon dioxide is adopted to cool the first wall and the structure of the cladding, so that the MHD effect, the corrosion of structural materials and the heat stress are reduced, the outlet temperature of the liquid lithium lead and the heat carrying capacity of the first wall are improved, and a candidate scheme is provided for the technical development of fusion reactor cladding.
The invention is realized by the following technical scheme: the supercritical carbon dioxide liquid lithium lead double-cold cladding adopts a sector cladding scheme, and is divided into an outer cladding sector and an inner cladding sector, wherein each sector comprises a plurality of proliferation units, each proliferation unit consists of a U-shaped first wall, a cooling plate, a reinforcing plate, a lithium lead runner plug-in unit and a supercritical carbon dioxide inlet/outlet header, the U-shaped first wall, the cooling plate, the reinforcing plate and the supercritical carbon dioxide outlet header are welded, and the cladding is divided into subchambers which are penetrated in the polar direction to form a lithium lead runner; the lithium lead runner insert is arranged in the lithium lead runner. The U-shaped first wall, the cooling plate, the reinforcing plate and the supercritical carbon dioxide inlet/outlet header are processed by low-activation ferritic steel. Tungsten armor is attached to the outer surface of the U-shaped first wall.
Further, cover plates are welded at the top and the bottom of the cladding sector respectively, an outer/inner cladding sector lithium lead inlet pipe is connected at the bottom, an outer/inner cladding sector lithium lead outlet pipe is connected at the top, liquid lithium lead is shunted from the bottom outer/inner cladding sector lithium lead inlet pipe into a parallel lithium lead runner, and finally flows out from the outer/inner cladding sector lithium lead outlet pipe in a collecting way to take away nuclear heat of a cladding proliferation area.
Further, a plurality of parallel coolant flow channels are arranged in the U-shaped first wall, the cooling plate and the reinforcing plate and are communicated with the supercritical carbon dioxide inlet/outlet header, and the supercritical carbon dioxide coolant is shunted from the inlet header to enter the coolant flow channels in the U-shaped first wall, the cooling plate and the reinforcing plate and then flows back to the outlet header to discharge heat; the cooling flow channels in the reinforcing plate are arranged in groups along polar regions, and each polar region is cooled by a group of cooling flow channels.
Further, each proliferation unit has the same or different geometry as each other and the same or different dimensions as each other.
Further, the lithium lead runner plug-in is processed by adopting an electrically and thermally insulating silicon carbide composite material.
Further, the sections, the intervals and the arrangement schemes of the cooling flow passages in the U-shaped first wall, the cooling plates and the reinforcing plates are optimized and determined according to the thermal-hydraulic requirements of the cladding.
The invention has the advantages that:
(1) Compared with high-pressure helium, the supercritical carbon dioxide coolant has the advantages that the density is improved by more than 10 times, the heat carrying capacity per unit volume is improved by about 150%, the defect of insufficient cooling capacity of the first wall is effectively overcome, and the safety of the fusion reactor cladding is improved.
(2) The silicon carbide runner plug-in provided by the invention has the advantages of high temperature resistance, corrosion resistance and good electric/thermal insulation, the MHD effect in the cladding layer can be effectively weakened, the corrosion problem of lithium lead to the runner can be avoided, meanwhile, the temperature of a lithium lead outlet is not limited by the corrosion temperature, the temperature can reach more than 700 ℃, and the thermoelectric conversion efficiency of the fusion reactor can be improved. The lithium lead runner plug-in components with different heat conductivities are selected to be used at different radial positions of the cladding, the heat conductivity of the lithium lead runner plug-in components close to the U-shaped first wall side is lower, and the temperature of the steel structure in the front region of the cladding is reduced to avoid overtemperature, so that the temperature difference of the steel structure in the front region and the rear region of the cladding is reduced, and the thermal stress of the steel structure is reduced.
(3) The cooling flow channels in the reinforcing plate (11) are distributed along the polar direction subareas in a grouping way, and each group of cooling flow channels only cools one polar direction subarea, so that the required coolant flow can be reduced, the flow channel length can be shortened, and the flow resistance can be reduced.
Drawings
FIG. 1 is a three-dimensional schematic of an inner and outer cladding segment and an exemplary proliferation cell of the present invention;
FIG. 2 is a schematic diagram showing the structural composition of a typical proliferation unit according to the present invention;
FIG. 3 is a cross-sectional view of an exemplary proliferation cell of the present invention, schematically illustrating a supercritical carbon dioxide flow scheme within a U-shaped first wall;
FIG. 4 is a schematic view of supercritical carbon dioxide flow scheme in a cooling plate and reinforcing plate according to the present invention;
FIG. 5 is a graph comparing supercritical carbon dioxide to high pressure helium loading capacities.
In the figure: 1. an outer cladding sector; 2. an inner cladding sector; 3. a cover plate; 4-1, an outer cladding sector lithium lead inlet pipe; 4-2, an inner cladding sector lithium lead inlet pipe; 5-1, an outer cladding sector lithium lead outlet pipe; 5-2, an inner cladding sector lithium lead outlet pipe; 6. a proliferation unit; 7.U type first wall; 8. tungsten armor; 9-1, supercritical carbon dioxide inlet header; 9-2, supercritical carbon dioxide outlet header; 10. a cooling plate; 11. a reinforcing plate; 12. a lithium lead runner insert; 13. and a lithium lead runner.
The dashed arrows in fig. 3 and 4 indicate the supercritical carbon dioxide flow direction.
Detailed Description
The technical solutions in the embodiments of the present invention are clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention. It will be apparent that the described embodiments are only some, but not all, embodiments of the invention. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
According to one embodiment of the invention, as shown in fig. 1, the fusion stack comprises sixteen outer cladding segments 1 and sixteen inner cladding segments 2. Each sector is designed by adopting a sector cladding scheme, and is divided into a plurality of proliferation units along the polar direction to be respectively processed, and then the sectors are formed by welding. As shown in fig. 3, each proliferation unit is composed of a U-shaped first wall 7, a cooling plate 10, a reinforcing plate 11, a lithium lead runner insert 12, and supercritical carbon dioxide inlet/outlet headers 9-1/9-2, independently of each other. Each proliferation unit 6 has the same or different geometry and the same or different dimensions as each other. For example, as shown in FIG. 2, a typical equatorial plane overcladding proliferation unit 6 is exemplified, which is comprised of a U-shaped first wall 7, cooling plates 10, reinforcing plates 11, lithium lead runner inserts 12, and supercritical carbon dioxide inlet/outlet headers 9-1/9-2.
Figure 3 shows a radial-circumferential cross-section of an embodiment, A-A of the exemplary proliferation cell 6 of figure 1. In cross section, two groups of cooling plates 10 and three groups of reinforcing plates 11 are respectively welded with the U-shaped first wall 7 and the supercritical carbon dioxide outlet header 9-2 to divide the cladding lithium lead proliferation area into twelve grids, and each grid forms a lithium lead runner 13. The top and bottom of each cladding sector are respectively welded with a cover plate 3, and the bottom is connected with an outer/inner cladding sector lithium lead inlet pipe 4-1/4-2, the top is connected with an outer/inner cladding sector lithium lead outlet pipe 5-1/5-2, liquid lithium lead is shunted from the bottom lithium lead inlet pipe 4-1/4-2 into a parallel lithium lead runner 13, and finally flows out from the lithium lead outlet pipe 5-1/5-2 in a collecting way, so that nuclear heat of a cladding proliferation area is taken away for power generation.
The U-shaped first wall 7, the cooling plate 10, the reinforcing plate 11 and the supercritical carbon dioxide inlet/outlet header 9-1/9-2 are processed by low-activation ferritic steel so as to reduce the activation level of radioactive substances of the fusion reactor cladding and shorten the radioactive waste treatment period. The outer surface of the U-shaped first wall 7 is provided with a high-temperature-resistant tungsten armor 8 for resisting plasma sputtering and high heat load and protecting the U-shaped first wall 7. The lithium lead runner insert 12 is made of an electrically and thermally insulating silicon carbide composite material, as shown in fig. 3, and is suspended in the lithium lead runner 13, and forms a certain liquid lithium lead gap with the steel structures of the cladding cooling plate 10 and the reinforcing plate 11. On one hand, the lithium lead runner plug-in 12 isolates the lithium lead and cladding steel structure which flow rapidly in the core area of the runner, reduces the MHD effect and slows down the corrosion of lithium lead to the cladding steel structure; on the other hand, the thermally insulated silicon carbide also plays a role in heat insulation, and can improve the lithium lead outlet temperature to 700 ℃ and the fusion pile thermoelectric conversion efficiency to more than 45% under the condition that the cladding steel structure does not exceed the allowable temperature (550-650 ℃).
The dashed arrow of fig. 3 illustrates the supercritical carbon dioxide cooling scheme within the U-shaped first wall 7. A plurality of parallel coolant flow passages are arranged in the U-shaped first wall 7, two ends of each flow passage are respectively communicated with the supercritical carbon dioxide inlet/outlet header 9-1/9-2, and supercritical carbon dioxide coolant is shunted from the inlet header 9-1 to enter the U-shaped first wall 7 and flows back to the outlet header 9-2 to discharge heat of the U-shaped first wall 7. The dashed arrows in fig. 4 illustrate the cooling scheme of the cooling plates 10 and reinforcing plates 11, with coolant from the supercritical carbon dioxide inlet header 9-1 being split along parallel flow paths into two sets of cooling plates 10 and three sets of reinforcing plates 11, flowing in polar distribution, and finally converging into the supercritical carbon dioxide outlet header 9-1 to effect cooling of the cooling plates 10 and reinforcing plates 11. The flow passage sections, spacing and lengths in the cooling plate 10 and reinforcing plate 11 can be optimally designed according to cooling requirements and flow resistance to achieve an optimal cooling solution design. In addition, as shown in fig. 4, the cooling flow passages in the reinforcing plate 11 are arranged in groups along the polar regions, and each group of cooling flow passages cools only one polar region, on the one hand, the required coolant flow rate is reduced, and on the other hand, the flow passage length is shortened, which is beneficial to reducing the flow resistance.
FIG. 5 shows a graph of supercritical carbon dioxide versus high pressure helium loading capacity at various pressure and temperature conditions. As can be seen, under typical coolant temperature (400 ℃) and pressure (8 MPa), 1m 3 The helium can take 29.3kJ heat away at 1 ℃ while the supercritical carbon dioxide can take 73.2kJ heat away, the heat carrying capacity is 2.5 times that of the helium. When the temperature is 300-500 ℃ and the pressure is 8-12MPa, the heat carrying capacity of the supercritical carbon dioxide and the heat carrying capacity of the supercritical carbon dioxide are changed, but the heat carrying capacity of the supercritical carbon dioxide and the heat carrying capacity of the supercritical carbon dioxide are 2.5 times of that of helium. This indicates that the supercritical carbon dioxide cladding has better heat carrying capacity than the conventional helium cold cladding, which is beneficial to improving the capability and safety margin of the cladding first wall against high heat load.
The invention, in part not set forth in detail, is well known in the art.
While the foregoing has described illustrative embodiments of the invention, it is convenient for those skilled in the art to understand the invention. It should be understood that the invention is not limited to the precise embodiments and that various changes may be made by one skilled in the art without departing from the scope and spirit of the invention as defined in the appended claims.
Claims (5)
1. The utility model provides a two cold claddings of supercritical carbon dioxide liquid lithium lead which characterized in that: adopting a sector cladding scheme, dividing the cladding into an outer cladding sector (1) and an inner cladding sector (2), wherein each sector comprises a plurality of proliferation units (6), the proliferation units (6) are composed of a U-shaped first wall (7), a cooling plate (10), a reinforcing plate (11), a lithium lead runner plug-in unit (12) and a supercritical carbon dioxide inlet/outlet header (9-1/9-2), the U-shaped first wall (7), the cooling plate (10), the reinforcing plate (11) and the supercritical carbon dioxide outlet header (9-2) are welded, and dividing the cladding into subchambers which are penetrated in a polar direction to form a lithium lead runner (13); the lithium lead runner insert (12) is arranged in the lithium lead runner (13), and a tungsten armor (8) is attached to the outer surface of the U-shaped first wall (7).
2. The supercritical carbon dioxide liquid lithium lead double-cooled cladding according to claim 1, wherein:
cover plates (3) are respectively welded at the top and the bottom of the cladding sector, an outer/inner cladding sector lithium lead inlet pipe (4-1/4-2) is connected at the bottom, an outer/inner cladding sector lithium lead outlet pipe (5-1/5-2) is connected at the top, liquid lithium lead is shunted from the bottom outer/inner cladding sector lithium lead inlet pipe (4-1/4-2) into a parallel lithium lead runner (13), and finally flows out from the outer/inner cladding sector lithium lead outlet pipe (5-1/5-2) in a converging manner to take away nuclear heat of a cladding proliferation area.
3. The supercritical carbon dioxide liquid lithium lead double-cooled cladding according to claim 1, wherein:
the U-shaped first wall (7), the cooling plate (10) and the reinforcing plate (11) are internally provided with a plurality of coolant flow channels which are connected in parallel and are communicated with the supercritical carbon dioxide inlet/outlet header (9-1/9-2), and the supercritical carbon dioxide coolant is shunted from the inlet header (9-1) to enter the coolant flow channels in the U-shaped first wall (7), the cooling plate (10) and the reinforcing plate (11) and then flows back to the outlet header (9-2) to discharge heat; the cooling flow channels in the reinforcing plate (11) are arranged in groups along polar regions, and each polar region is cooled by a group of cooling flow channels.
4. The supercritical carbon dioxide liquid lithium lead double-cooled cladding according to claim 1, wherein: the U-shaped first wall (7), the cooling plate (10), the reinforcing plate (11) and the supercritical carbon dioxide inlet/outlet header (9-1/9-2) are processed by adopting low-activation ferritic steel.
5. The supercritical carbon dioxide liquid lithium lead double-cooled cladding according to claim 1, wherein: the lithium lead runner insert (12) is processed by adopting an electrically and thermally insulating silicon carbide composite material.
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| CN115235134B (en) * | 2022-09-22 | 2022-12-20 | 中国科学院合肥物质科学研究院 | Supercritical carbon dioxide circulation system for fusion reactor |
| CN116665924B (en) * | 2023-06-14 | 2024-06-14 | 中国科学院合肥物质科学研究院 | A passive plate structure for inhibiting plasma vertical instability |
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