CN112259317A - Heat shield component of superconducting coil of thermonuclear fusion reactor and preparation method thereof - Google Patents
Heat shield component of superconducting coil of thermonuclear fusion reactor and preparation method thereof Download PDFInfo
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- CN112259317A CN112259317A CN202011047780.7A CN202011047780A CN112259317A CN 112259317 A CN112259317 A CN 112259317A CN 202011047780 A CN202011047780 A CN 202011047780A CN 112259317 A CN112259317 A CN 112259317A
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- 230000004927 fusion Effects 0.000 title claims abstract description 26
- 238000002360 preparation method Methods 0.000 title abstract description 5
- 229910000831 Steel Inorganic materials 0.000 claims abstract description 97
- 239000010959 steel Substances 0.000 claims abstract description 97
- 238000005219 brazing Methods 0.000 claims abstract description 92
- QZLJNVMRJXHARQ-UHFFFAOYSA-N [Zr].[Cr].[Cu] Chemical compound [Zr].[Cr].[Cu] QZLJNVMRJXHARQ-UHFFFAOYSA-N 0.000 claims abstract description 87
- 229910052802 copper Inorganic materials 0.000 claims abstract description 73
- 239000010949 copper Substances 0.000 claims abstract description 73
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims abstract description 69
- 238000003466 welding Methods 0.000 claims description 67
- 229910000881 Cu alloy Inorganic materials 0.000 claims description 28
- 239000000945 filler Substances 0.000 claims description 22
- 238000003756 stirring Methods 0.000 claims description 22
- 238000000034 method Methods 0.000 claims description 17
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims description 14
- 238000001514 detection method Methods 0.000 claims description 12
- 229910052751 metal Inorganic materials 0.000 claims description 12
- 239000002184 metal Substances 0.000 claims description 12
- 239000001307 helium Substances 0.000 claims description 10
- 229910052734 helium Inorganic materials 0.000 claims description 10
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 10
- 238000012360 testing method Methods 0.000 claims description 10
- 229910001093 Zr alloy Inorganic materials 0.000 claims description 9
- 230000007547 defect Effects 0.000 claims description 9
- 229910052757 nitrogen Inorganic materials 0.000 claims description 7
- 238000001816 cooling Methods 0.000 claims description 6
- 238000007689 inspection Methods 0.000 claims description 6
- 239000000463 material Substances 0.000 claims description 5
- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 claims description 3
- 238000000861 blow drying Methods 0.000 claims description 3
- 238000004140 cleaning Methods 0.000 claims description 3
- 239000007789 gas Substances 0.000 claims description 3
- 238000003754 machining Methods 0.000 claims description 3
- 238000009659 non-destructive testing Methods 0.000 claims description 3
- 238000005086 pumping Methods 0.000 claims description 3
- 239000010935 stainless steel Substances 0.000 claims description 3
- 229910001220 stainless steel Inorganic materials 0.000 claims description 3
- 230000005570 vertical transmission Effects 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 3
- 238000012545 processing Methods 0.000 claims description 2
- 230000002706 hydrostatic effect Effects 0.000 claims 2
- 238000004381 surface treatment Methods 0.000 claims 1
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 4
- 238000007789 sealing Methods 0.000 description 3
- 238000012937 correction Methods 0.000 description 2
- 229910052759 nickel Inorganic materials 0.000 description 2
- 238000007747 plating Methods 0.000 description 2
- 229910052726 zirconium Inorganic materials 0.000 description 2
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 1
- 229910017526 Cu-Cr-Zr Inorganic materials 0.000 description 1
- 229910017810 Cu—Cr—Zr Inorganic materials 0.000 description 1
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical compound [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000003908 quality control method Methods 0.000 description 1
- 239000003507 refrigerant Substances 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 229910052709 silver Inorganic materials 0.000 description 1
- 239000004332 silver Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
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- H—ELECTRICITY
- H01—ELECTRIC ELEMENTS
- H01F—MAGNETS; INDUCTANCES; TRANSFORMERS; SELECTION OF MATERIALS FOR THEIR MAGNETIC PROPERTIES
- H01F6/00—Superconducting magnets; Superconducting coils
- H01F6/04—Cooling
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/05—Thermonuclear fusion reactors with magnetic or electric plasma confinement
- G21B1/057—Tokamaks
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
-
- H—ELECTRICITY
- H01—ELECTRIC ELEMENTS
- H01F—MAGNETS; INDUCTANCES; TRANSFORMERS; SELECTION OF MATERIALS FOR THEIR MAGNETIC PROPERTIES
- H01F41/00—Apparatus or processes specially adapted for manufacturing or assembling magnets, inductances or transformers; Apparatus or processes specially adapted for manufacturing materials characterised by their magnetic properties
- H01F41/02—Apparatus or processes specially adapted for manufacturing or assembling magnets, inductances or transformers; Apparatus or processes specially adapted for manufacturing materials characterised by their magnetic properties for manufacturing cores, coils, or magnets
- H01F41/04—Apparatus or processes specially adapted for manufacturing or assembling magnets, inductances or transformers; Apparatus or processes specially adapted for manufacturing materials characterised by their magnetic properties for manufacturing cores, coils, or magnets for manufacturing coils
- H01F41/048—Superconductive coils
-
- 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
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- Engineering & Computer Science (AREA)
- Power Engineering (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Pressure Welding/Diffusion-Bonding (AREA)
Abstract
The invention belongs to the technical field of thermonuclear fusion reactors, and particularly relates to a thermonuclear fusion reactor superconducting coil heat shield component and a preparation method thereof, wherein the thermonuclear fusion reactor superconducting coil heat shield component comprises the following steps: an F-shaped pipe A, F type pipe B, a copper plate A, a copper plate B, a copper plate C and a copper-chromium-zirconium steel pipe brazing assembly; the copper plate A3 is connected with the copper plate B4 through a copper-chromium-zirconium steel tube brazing assembly, and the copper plate B is provided with the copper-chromium-zirconium steel tube brazing assembly; and F-shaped pipes A and F-shaped pipes B are respectively arranged at two ends of the copper-chromium-zirconium steel pipe brazing assembly.
Description
Technical Field
The invention belongs to the technical field of thermonuclear fusion reactors, and particularly relates to a thermonuclear fusion reactor superconducting coil heat shield component and a preparation method thereof.
Background
ITER is the largest superconducting Tokamak device in the world at present. In the ITER apparatus, the magnetic confinement of the plasma is achieved by different superconducting coils. In a fusion reactor magnet system comprising 18 correction coils, these superconducting coils must be kept below a very low temperature to maintain superconductivity and thus stable operation of the ITER apparatus. However, each poloidal field coil box in contact with the calibration field coil generates approximately 16.596kW of heat under the magnetic field in order to ensure proper operation of the calibration field superconducting magnet during fusion reactor operation. A heat shield member formed by connecting a copper alloy plate contacting the poloidal field coil support and a 316L tube system with a helium refrigerant of 10k and 5bar inside is located between the poloidal field coil support and the correction coil clamp to remove heat generated by the poloidal field coil support.
Several problems exist with current heat shield components:
1) the high-quality connection of the stainless steel pipe and the copper plate vacuum brazing joint can not be realized on the length of more than 1000 mm;
2) the grain of the copper alloy plate is seriously grown when the copper alloy plate is in vacuum brazing with a steel pipe, so that the mechanical property is degraded, and the yield strength of copper after the copper alloy plate undergoes brazing thermal cycle is even lower than 60 MPa;
3) TS belongs to parts in a vacuum chamber, the number of welding seams is very large, good sealing performance is required, and the leakage requirement is 1x10-9Pa.m 3/s;
therefore, a superconducting coil heat shielding component needs to be designed to solve the technical problems of low quality of dissimilar material connection, degraded mechanical properties and low vacuum sealing performance of the superconducting coil heat shielding component in the prior art.
Disclosure of Invention
The invention aims to design a superconducting coil heat shield component of a thermonuclear fusion reactor and a preparation method thereof, which are used for solving the technical problems of low connection quality of dissimilar materials, degraded mechanical property and low vacuum sealing property of the superconducting coil heat shield component in the prior art
The technical scheme of the invention is as follows:
a superconducting coil heat shield component of a thermonuclear fusion reactor, comprising: an F-shaped pipe A1, an F-shaped pipe B2, a copper plate A3, a copper plate B4, a copper plate C5 and a copper-chromium-zirconium steel pipe brazing assembly 6; the copper plate A3 is connected with the copper plate B4 through a copper-chromium-zirconium steel tube brazing assembly 6, and the copper-chromium-zirconium steel tube brazing assembly 6 is arranged between the copper plate B4 and the copper plate C5; and F-shaped pipes A1 and B2 are respectively arranged at two ends of the copper-chromium-zirconium steel pipe brazing assembly 6.
The copper chromium zirconium steel pipe brazing assembly 6 comprises: copper chromium zirconium block 10, brazing filler metal 7, filler groove 8 and steel pipe 9;
the copper chromium zirconium block 10 is integrally of a strip-shaped convex structure, a copper alloy through hole is formed in the center of the copper chromium zirconium block 10, a steel pipe 9 is inserted into the copper alloy through hole, the steel pipe 9 is not in contact with the copper alloy through hole, a gap is reserved between the steel pipe 9 and the copper alloy through hole, and a filling groove 8 is formed in one side of the copper alloy through hole; the brazing filler metal 7 is placed in a filler channel 8.
The straightness of the steel pipe 9 is 0.02mm/100mm, the roundness of the steel pipe 9 is within 0.02mm, and the steel pipe 9 is made of a steel material; the brazing filler metal 7 is AgCu 28.
A superconducting coil heat shield assembly for a thermonuclear fusion reactor as described in any one of the above, comprising the steps of:
the method comprises the following steps: machining the surfaces of the steel pipe 9 and the copper-chromium-zirconium block 10 before brazing;
step two: assembling and vacuum brazing the steel pipe 9 and the copper-chromium-zirconium block 10 before brazing;
step three: brazing in a vacuum brazing furnace;
step four: after processing the copper-chromium-zirconium steel pipe brazing assembly 6, the copper plate A3, the copper plate B4 and the copper plate C5 are butted by using friction stir welding
Step five: connecting an F-shaped pipe A1 and an F-shaped pipe B2 with a steel pipe 9 in the copper-chromium-zirconium steel pipe brazing assembly 6 by adopting a TIG welding mode;
step six: performing nondestructive testing on the stirring friction welding seams of the copper-chromium-zirconium steel pipe brazing assembly 6 and the copper plates 3, 4 and 5;
step seven: and (4) performing water pressure detection on the copper-chromium-zirconium alloy block 10 welded in the step five, and performing vacuum positive pressure helium leakage detection on the heat shield part connected by TIG welding in the step five.
The first step further comprises: the deviation of the copper alloy through holes and the straightness on the copper chromium zirconium block 11 is within 0.02mm/100 mm; the inner and outer surfaces of the steel pipe 9 and the copper-chromium-zirconium block 10 are cleaned by absolute ethyl alcohol ultrasonic wave, the nickel plating layer is ensured not to be damaged in the cleaning process, and then hot nitrogen is used for blow-drying for standby.
The second step further comprises:
inserting the nickel-plated steel pipe 9 into the copper alloy through hole of the copper chromium zirconium alloy block 10; controlling the brazing gap between the steel pipe 10 and the copper alloy through hole to be 0.03 mm; then, inserting the brazing wire 7 into a filler groove 8 on a copper chromium zirconium alloy block 10 to form a copper chromium zirconium steel pipe brazing assembly 6;
the third step further comprises: placing the copper-chromium-zirconium steel pipe brazing assembly 6 in the second step into a vacuum furnace, setting the brazing temperature of the vacuum furnace to be 8 x10 < -3 > pa, brazing for 30min at 800 ℃, and then cooling to 500 ℃ in the vacuum furnace; when the workpiece temperature was reduced to 500 ℃, cooling was accelerated to 150 ℃ at a rate of 5 ℃/min by introducing nitrogen.
The fourth step further comprises: welding and connecting the longest edge of the copper plate A3 and the longest edge of the copper plate B4 through the copper-chromium-zirconium steel tube brazing assembly 6 in a friction stir welding mode, and similarly welding and connecting the other longest edge of the copper plate B4 and the longest edge of the copper plate C5 through the copper-chromium-zirconium steel tube brazing assembly 6 in a friction stir welding mode; welding parameter range: the welding speed v was 100mm/min, the rotational speed U was 500rpm, and the stirring head pressure was 1000N.
The fifth step further comprises: the TIG welding process parameters are 88A of current, 10V of voltage and 10 degrees/s of welding speed.
The sixth step further comprises: using 120-degree projection for three times, and inspecting the welding seam quality of the soldered joint in a double-wall double-shadow radiographic inspection mode, wherein the surface defect of the welding seam exceeding 1mm cannot exist; using 120-degree projection and double-wall double-shadow radiographic inspection for three times to inspect the quality of the welding seam of the steel pipe 10 joint, wherein the welding seam has no defect exceeding 0.4 mm; the quality of the welding seam of the stirring friction welding seam of the copper-chromium-zirconium steel pipe brazing assembly 6 and the copper plates 3, 4 and 5 is checked in a vertical transmission flaw detection mode, and the defect of more than 0.4mm cannot be caused.
The step seven of performing the hydraulic test on the copper-chromium-zirconium block 10 welded in the step five comprises the following steps: setting the hydraulic test pressure to be 5 +/-0.2 MPa, testing the hydraulic time to be 30min, and detecting the leakage and visible permanent deformation conditions of the copper-chromium-zirconium block 10 with the pressure value change smaller than 0.2 MPa;
the step seven of performing vacuum positive pressure helium leakage detection on the heat shielding component welded in the step five comprises the following steps: placing the heat shielding component welded in the fifth step into a vacuum chamber, and pumping the vacuum chamber to 1 × 10-4Pa, filling helium gas of 3MPa into the heat shielding component, and maintaining the pressure for 30min, wherein the leakage rate of the copper-chromium-zirconium block 10 is required to be lower than 1x10 < -9 > Pa.m3/s。
The invention has the beneficial effects that:
1) according to the invention, the copper pipe is processed by using the high-precision deep hole drill, so that the brazing gap between the copper block and the steel pipe lap joint is effectively ensured, and the brazing rate can reach more than 95%;
2) according to the invention, the steel pipe is cooled to the liquid nitrogen temperature and then penetrates into the copper block, compared with the traditional method, the brazing gap can be further controlled, so that the shearing strength of the steel-copper brazing joint can reach more than 210 MPa;
3) the invention realizes 360-degree connection with the copper inner hole in the circumferential direction of the steel pipe, and the heat conduction efficiency of the part can be greatly improved by matching with the high-heat-conductivity silver-based brazing filler metal;
4) according to the invention, a small amount of copper-chromium-zirconium blocks are used for braze welding connection with the pipe to form a steel pipe and copper block braze welding assembly, and then the copper-chromium-zirconium and a large-area copper plate on the braze welding assembly are connected by friction stir welding at normal temperature, so that coarsening of grain size and degradation such as reduction of mechanical properties of the copper plate during braze welding can be avoided;
5) according to the invention, a small amount of copper-chromium-zirconium blocks are used for being in braze welding connection with the high-temperature resistant stainless steel pipe to form a steel pipe and copper block braze welding assembly, and then the copper-chromium-zirconium blocks and a large area of copper plate on the braze welding assembly are connected by friction stir welding at normal temperature, so that the quality control is facilitated and the production efficiency is improved;
6) the invention uses the friction stir welding to connect the copper, the chromium and the zirconium on the brazing assembly and the large-area copper plate, and can effectively weld deformation of the components due to the inherent property of the low heat input semi-solid connection of the friction stir welding.
Drawings
FIG. 1 is a schematic view of a superconducting coil heat shield assembly of a thermonuclear fusion reactor according to the present invention;
FIG. 2 is a schematic cross-sectional view of a Cu-Cr-Zr block according to the present invention
Wherein, 1-F type pipe A; 2-F type pipe B, 3-copper plate A; 4-copper plate B, 5-copper plate C and 6-copper chromium zirconium steel tube brazing components; 7-brazing filler metal, 8-filler grooves, 9-steel pipes and 10-copper-chromium-zirconium blocks;
Detailed Description
The invention will be further described with reference to the following figures and examples:
a superconducting coil heat shield component of a thermonuclear fusion reactor, comprising: an F-shaped pipe A1, an F-shaped pipe B2, a copper plate A3, a copper plate B4, a copper plate C5 and a copper-chromium-zirconium steel pipe brazing assembly 6; the copper plate A3 is connected with the copper plate B4 through a copper-chromium-zirconium steel tube brazing assembly 6, and the copper-chromium-zirconium steel tube brazing assembly 6 is arranged between the copper plate B4 and the copper plate C5; and F-shaped pipes A1 and F-shaped pipes B2 are respectively arranged at two ends of the copper-chromium-zirconium steel pipe brazing assembly A6.
The copper chromium zirconium steel pipe brazing assembly 6 comprises: copper chromium zirconium block 10, brazing filler metal 7, filler groove 8 and steel pipe 9;
the copper chromium zirconium block 10 is integrally of a strip-shaped convex structure, a copper alloy through hole is formed in the center of the copper chromium zirconium block 10, a steel pipe 9 is inserted into the copper alloy through hole, the steel pipe 9 is not in contact with the copper alloy through hole, a gap is reserved between the steel pipe 9 and the copper alloy through hole, and a filling groove 8 is formed in one side of the copper alloy through hole; the brazing filler metal 7 is placed in a filler channel 8.
The straightness of the steel pipe 9 is 0.02mm/100mm, the roundness of the steel pipe 9 is within 0.02mm, and the steel pipe 9 is made of a steel material; the brazing filler metal 7 is AgCu 28.
A superconducting coil heat shield assembly for a thermonuclear fusion reactor as described in any one of the above, comprising the steps of:
the method comprises the following steps: machining the surfaces of the steel pipe 9 and the copper-chromium-zirconium block 10 before brazing;
step two: assembling and vacuum brazing the steel pipe 9 and the copper-chromium-zirconium block 10 before brazing;
step three: brazing in a vacuum brazing furnace;
step four: heating the copper-chromium-zirconium steel pipe brazing assembly 6, and then butting the heated copper-chromium-zirconium steel pipe brazing assembly with a copper plate A3, a copper plate B4 and a copper plate C5 by using friction stir welding
Step five: connecting an F-shaped pipe A1 and an F-shaped pipe B2 with a steel pipe 9 in the copper-chromium-zirconium steel pipe brazing assembly 6 by adopting a TIG welding mode;
step six: carrying out nondestructive testing on the stirring friction welding seams of the copper-chromium-zirconium steel pipe brazing assembly 6 and the copper plates 3, 4 and 5;
step seven: and (4) performing water pressure detection on the copper-chromium-zirconium alloy block 10 welded in the step five, and performing vacuum positive pressure helium leakage detection on the heat shield part connected by TIG welding in the step five.
The first step further comprises: the deviation of the copper alloy through holes and the straightness on the copper chromium zirconium block 11 is within 0.02mm/100 mm; the inner and outer surfaces of the steel pipe 9 and the copper-chromium-zirconium block 10 are cleaned by absolute ethyl alcohol ultrasonic wave, the nickel plating layer is ensured not to be damaged in the cleaning process, and then hot nitrogen is used for blow-drying for standby.
The second step further comprises:
inserting the nickel-plated steel pipe 9 into the copper alloy through hole of the copper chromium zirconium alloy block 10; controlling the brazing gap between the steel pipe 10 and the copper alloy through hole to be 0.03 mm; then, inserting the brazing wire 7 into a filler groove 8 on a copper chromium zirconium alloy block 10 to form a copper chromium zirconium steel pipe brazing assembly 6;
the third step further comprises: placing the copper-chromium-zirconium steel pipe brazing assembly 6 in the second step into a vacuum furnace, setting the brazing temperature of the vacuum furnace to be 8 x10 < -3 > pa, brazing for 30min at 800 ℃, and then cooling to 500 ℃ in the vacuum furnace; when the workpiece temperature was reduced to 500 ℃, cooling was accelerated to 150 ℃ at a rate of 5 ℃/min by introducing nitrogen.
The fourth step further comprises: welding and connecting the longest edge of the copper plate A3 and the longest edge of the copper plate B4 through the copper-chromium-zirconium steel tube brazing assembly 6 in a friction stir welding mode, and similarly welding and connecting the other longest edge of the copper plate B4 and the longest edge of the copper plate C5 through the copper-chromium-zirconium steel tube brazing assembly 6 in a friction stir welding mode; welding parameter range: the welding speed v was 100mm/min, the rotational speed U was 500rpm, and the stirring head pressure was 1000N.
The fifth step further comprises: the TIG welding process parameters are 88A of current, 10V of voltage and 10 degrees/s of welding speed.
The sixth step further comprises: using 120-degree projection for three times, and inspecting the welding seam quality of the soldered joint in a double-wall double-shadow radiographic inspection mode, wherein the surface defect of the welding seam exceeding 1mm cannot exist; using 120-degree projection and double-wall double-shadow radiographic inspection for three times to inspect the quality of the welding seam of the steel pipe 10 joint, wherein the welding seam has no defect exceeding 0.4 mm; the quality of the welding seam of the stirring friction welding seam of the copper-chromium-zirconium steel pipe brazing assembly 6 and the copper plates 3, 4 and 5 is checked in a vertical transmission flaw detection mode, and the defect of more than 0.4mm cannot be caused.
The step seven of performing the hydraulic test on the copper-chromium-zirconium block 10 welded in the step five comprises the following steps: setting the hydraulic test pressure to be 5 +/-0.2 MPa, testing the hydraulic time to be 30min, and detecting the leakage and visible permanent deformation conditions of the copper-chromium-zirconium block 10 with the pressure value change smaller than 0.2 MPa;
the step seven of performing vacuum positive pressure helium leakage detection on the heat shielding component welded in the step five comprises the following steps: placing the heat shielding component welded in the fifth step into a vacuum chamber, and pumping the vacuum chamber to 1 × 10-4Pa, filling helium gas of 3MPa into the heat shielding component, and maintaining the pressure for 30min, wherein the leakage rate of the copper-chromium-zirconium block 10 is required to be lower than 1x10 < -9 > Pa.m3/s。
The present invention has been described in detail with reference to the drawings and examples, but the present invention is not limited to the examples, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present invention. The prior art can be adopted in the content which is not described in detail in the invention.
Claims (11)
1. A superconducting coil heat shield component for a thermonuclear fusion reactor, comprising: an F-shaped pipe A (1), an F-shaped pipe B (2), a copper plate A (3), a copper plate B (4), a copper plate C (5) and a copper-chromium-zirconium steel pipe brazing assembly (6); the copper plate A (3) and the copper plate B (4) are connected through a copper-chromium-zirconium steel tube brazing assembly (6), and the copper-chromium-zirconium steel tube brazing assembly (6) is arranged between the copper plate B (4) and the copper plate C (5); and F-shaped pipes A (1) and B (2) are respectively arranged at two ends of the copper-chromium-zirconium steel pipe brazing assembly (6).
2. The superconducting coil heat shield assembly of thermonuclear fusion reactor as claimed in claim 1 wherein said copper chromium zirconium steel tube brazed assembly (6) comprises: the brazing filler metal comprises a copper-chromium-zirconium block (10), brazing filler metal (7), a filler groove (8) and a steel pipe (9);
the copper chromium zirconium block (10) is integrally of a strip-shaped convex structure, a copper alloy through hole is formed in the center of the copper chromium zirconium block (10), a steel pipe (9) is inserted into the copper alloy through hole, the steel pipe (9) is not in contact with the copper alloy through hole, a gap is reserved between the steel pipe (9) and the copper alloy through hole, and a filling groove (8) is formed in one side of the copper alloy through hole; the brazing filler metal (7) is placed in the filler groove (8).
3. A superconducting coil heat shield assembly for a thermonuclear fusion reactor as claimed in claim 2 wherein: the straightness of the steel pipe (9) is 0.02mm/100mm, the roundness of the steel pipe (9) is within 0.02mm, and the steel pipe (9) is made of a stainless steel material; the brazing filler metal (7) is AgCu 28.
4. A superconducting coil heat shield assembly for a thermonuclear fusion reactor as claimed in any of claims 1 to 3 comprising the steps of:
the method comprises the following steps: machining the surface treatment of the steel pipe (9) and the copper-chromium-zirconium block (10) before brazing;
step two: assembling and vacuum brazing the steel pipe (9) and the copper-chromium-zirconium block (10) before brazing;
step three: brazing in a vacuum brazing furnace;
step four: processing a copper-chromium-zirconium steel pipe brazing assembly (6), and then butting the processed copper-chromium-zirconium steel pipe brazing assembly with a copper plate A (3), a copper plate B (4) and a copper plate C (5) by using friction stir welding
Step five: connecting the F-shaped pipe A (1) and the F-shaped pipe B (2) with a steel pipe (9) in the copper-chromium-zirconium steel pipe brazing assembly (6) in a TIG welding mode;
step six: performing nondestructive testing on the stirring friction welding seams of the four-copper-chromium-zirconium steel pipe brazing assembly (6) and the copper plate A (3), the copper plate B (4) and the copper plate C (5);
step seven: carrying out water pressure detection on the copper-chromium-zirconium alloy block (10) welded in the step five; and (4) carrying out vacuum positive pressure helium leakage detection on the heat shield component after the fifth step of TIG welding connection.
5. The method for preparing a superconducting coil heat shield component of a thermonuclear fusion reactor as claimed in claim 4, wherein said step one further comprises: the deviation of the copper alloy through holes and the straightness on the copper chromium zirconium block (11) is within 0.02mm/100 mm; the inner and outer surfaces of the steel pipe (9) and the copper-chromium-zirconium block (10) are cleaned by absolute ethyl alcohol ultrasonic wave, the nickel-plated layer is ensured not to be damaged in the cleaning process, and then hot nitrogen is used for blow-drying for standby.
6. The method for preparing a superconducting coil heat shield component of a thermonuclear fusion reactor as claimed in claim 5, wherein: the second step further comprises:
inserting the nickel-plated steel pipe (9) into a copper alloy through hole of a copper chromium zirconium alloy block (10); controlling the brazing gap between the steel pipe (10) and the copper alloy through hole to be 0.03 mm; and then, inserting the brazing wire (7) into a filler groove (8) on a copper-chromium-zirconium alloy block (10) to form a copper-chromium-zirconium steel pipe brazing assembly (6).
7. The method for preparing a superconducting coil heat shield component of a thermonuclear fusion reactor as claimed in claim 6, wherein: the third step further comprises: placing the copper-chromium-zirconium steel pipe brazing assembly (6) in the second step into a vacuum furnace, setting the brazing temperature of the vacuum furnace to be 8 x10 < -3 > pa, brazing for 30min at 800 ℃, and then cooling to 500 ℃ in the vacuum furnace; when the workpiece temperature was reduced to 500 ℃, cooling was accelerated to 150 ℃ at a rate of 5 ℃/min by introducing nitrogen.
8. The method for preparing a superconducting coil heat shield component of a thermonuclear fusion reactor as claimed in claim 7, wherein: the fourth step further comprises: welding and connecting the longest edge of the copper plate A (3) and the longest edge of the copper plate B (4) through the copper-chromium-zirconium steel tube brazing assembly (6) in a friction stir welding mode, and similarly welding and connecting the other longest edge of the copper plate B (4) and the longest edge of the copper plate C (5) through the copper-chromium-zirconium steel tube brazing assembly (6) in a friction stir welding mode; welding parameter range: the welding speed v was 100mm/min, the rotational speed U was 500rpm, and the stirring head pressure was 1000N.
9. The method for preparing a superconducting coil heat shield component of a thermonuclear fusion reactor as claimed in claim 8, wherein: the fifth step further comprises: the TIG welding process parameters are 88A of current, 10V of voltage and 10 degrees/s of welding speed.
10. The method for preparing a superconducting coil heat shield component of a thermonuclear fusion reactor as claimed in claim 9, wherein: the sixth step further comprises: using 120-degree projection for three times, and inspecting the welding seam quality of the soldered joint in a double-wall double-shadow radiographic inspection mode, wherein the surface defect of the welding seam exceeding 1mm cannot exist; the welding seam quality of the joint of the steel pipe (10) is inspected by using 120-degree projection and double-wall double-shadow radiographic inspection for three times, and the welding seam has no defect exceeding 0.4 mm; the quality of the welding seam of the stirring friction welding seam of the copper-chromium-zirconium steel pipe brazing assembly (6) and the copper plates A (3), B (4) and C (5) is checked by using a vertical transmission flaw detection mode, and the defect of more than 0.4mm cannot be caused.
11. The method for preparing a superconducting coil heat shield component of a thermonuclear fusion reactor as claimed in claim 10, wherein: the step seven of carrying out the hydraulic test on the copper-chromium-zirconium block (10) welded in the step five comprises the following steps: setting the hydrostatic test pressure to be 5 +/-0.2 MPa, testing the hydrostatic test time to be 30min, and detecting the leakage and visible permanent deformation conditions of the copper-chromium-zirconium block (10) when the pressure value change is less than 0.2 MPa;
the step seven of performing vacuum positive pressure helium leakage detection on the heat shield component subjected to TIG welding in the step five comprises the following steps: placing the heat shielding component welded in the fifth step into a vacuum chamber, and pumping the vacuum chamber to 1 × 10-4Pa, filling helium gas with 3MPa into the heat shielding component, and maintaining the pressure for 30min, wherein the leakage rate of the copper-chromium-zirconium block (10) is required to be lower than 1x10 < -9 > Pa3/s。
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