CN113185127A - Ca-Ti-Y-Al-Si-O microcrystalline glass solder and glass packaging method for end port of nuclear cladding tube - Google Patents
Ca-Ti-Y-Al-Si-O microcrystalline glass solder and glass packaging method for end port of nuclear cladding tube Download PDFInfo
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- CN113185127A CN113185127A CN202110425977.8A CN202110425977A CN113185127A CN 113185127 A CN113185127 A CN 113185127A CN 202110425977 A CN202110425977 A CN 202110425977A CN 113185127 A CN113185127 A CN 113185127A
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- 238000005253 cladding Methods 0.000 title claims abstract description 103
- 239000011521 glass Substances 0.000 title claims abstract description 76
- 229910018557 Si O Inorganic materials 0.000 title claims abstract description 28
- LIVNPJMFVYWSIS-UHFFFAOYSA-N silicon monoxide Inorganic materials [Si-]#[O+] LIVNPJMFVYWSIS-UHFFFAOYSA-N 0.000 title claims abstract description 28
- 229910000679 solder Inorganic materials 0.000 title claims abstract description 24
- 238000000034 method Methods 0.000 title claims abstract description 14
- 238000004806 packaging method and process Methods 0.000 title abstract description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 16
- 238000001816 cooling Methods 0.000 claims abstract description 13
- 239000002994 raw material Substances 0.000 claims abstract description 4
- 238000010438 heat treatment Methods 0.000 claims description 38
- 239000000843 powder Substances 0.000 claims description 26
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 claims description 23
- 238000000498 ball milling Methods 0.000 claims description 21
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 20
- 229910052681 coesite Inorganic materials 0.000 claims description 18
- 229910052906 cristobalite Inorganic materials 0.000 claims description 18
- 239000011812 mixed powder Substances 0.000 claims description 18
- 239000000377 silicon dioxide Substances 0.000 claims description 18
- 229910052682 stishovite Inorganic materials 0.000 claims description 18
- 229910052905 tridymite Inorganic materials 0.000 claims description 18
- 238000003825 pressing Methods 0.000 claims description 15
- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 claims description 14
- 229910052593 corundum Inorganic materials 0.000 claims description 14
- 229910001845 yogo sapphire Inorganic materials 0.000 claims description 14
- 238000004321 preservation Methods 0.000 claims description 13
- 239000012298 atmosphere Substances 0.000 claims description 11
- 239000011248 coating agent Substances 0.000 claims description 9
- 238000000576 coating method Methods 0.000 claims description 9
- 238000002156 mixing Methods 0.000 claims description 9
- GWEVSGVZZGPLCZ-UHFFFAOYSA-N titanium dioxide Inorganic materials O=[Ti]=O GWEVSGVZZGPLCZ-UHFFFAOYSA-N 0.000 claims description 8
- 239000002245 particle Substances 0.000 claims description 7
- 239000000565 sealant Substances 0.000 claims description 7
- 238000007873 sieving Methods 0.000 claims description 7
- 239000000203 mixture Substances 0.000 claims description 4
- 238000002360 preparation method Methods 0.000 claims description 3
- 239000012300 argon atmosphere Substances 0.000 claims description 2
- 238000004140 cleaning Methods 0.000 claims description 2
- 238000001035 drying Methods 0.000 claims description 2
- 239000003761 preservation solution Substances 0.000 claims description 2
- 238000004506 ultrasonic cleaning Methods 0.000 claims description 2
- 239000013078 crystal Substances 0.000 abstract description 11
- 238000007789 sealing Methods 0.000 abstract description 10
- 230000000694 effects Effects 0.000 abstract description 7
- 230000005855 radiation Effects 0.000 abstract description 7
- 239000000835 fiber Substances 0.000 abstract description 6
- 238000006243 chemical reaction Methods 0.000 abstract description 4
- 230000001737 promoting effect Effects 0.000 abstract description 4
- 231100000957 no side effect Toxicity 0.000 abstract description 3
- 230000009286 beneficial effect Effects 0.000 abstract description 2
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 description 66
- 229910010271 silicon carbide Inorganic materials 0.000 description 57
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical group [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 10
- 235000019441 ethanol Nutrition 0.000 description 10
- 239000000463 material Substances 0.000 description 8
- OGIDPMRJRNCKJF-UHFFFAOYSA-N titanium oxide Inorganic materials [Ti]=O OGIDPMRJRNCKJF-UHFFFAOYSA-N 0.000 description 7
- 229910052786 argon Inorganic materials 0.000 description 5
- 239000003795 chemical substances by application Substances 0.000 description 5
- 239000008393 encapsulating agent Substances 0.000 description 5
- 238000005538 encapsulation Methods 0.000 description 5
- 238000010791 quenching Methods 0.000 description 5
- 230000000171 quenching effect Effects 0.000 description 5
- 230000009977 dual effect Effects 0.000 description 4
- 230000002349 favourable effect Effects 0.000 description 4
- 238000012536 packaging technology Methods 0.000 description 4
- 229910001093 Zr alloy Inorganic materials 0.000 description 3
- 239000002131 composite material Substances 0.000 description 3
- 238000001764 infiltration Methods 0.000 description 3
- 230000008595 infiltration Effects 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- BPQQTUXANYXVAA-UHFFFAOYSA-N Orthosilicate Chemical compound [O-][Si]([O-])([O-])[O-] BPQQTUXANYXVAA-UHFFFAOYSA-N 0.000 description 2
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 description 2
- KZHJGOXRZJKJNY-UHFFFAOYSA-N dioxosilane;oxo(oxoalumanyloxy)alumane Chemical compound O=[Si]=O.O=[Si]=O.O=[Al]O[Al]=O.O=[Al]O[Al]=O.O=[Al]O[Al]=O KZHJGOXRZJKJNY-UHFFFAOYSA-N 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000011049 filling Methods 0.000 description 2
- 239000001257 hydrogen Substances 0.000 description 2
- 229910052739 hydrogen Inorganic materials 0.000 description 2
- 229910003465 moissanite Inorganic materials 0.000 description 2
- 229910052863 mullite Inorganic materials 0.000 description 2
- 238000001228 spectrum Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 229910052727 yttrium Inorganic materials 0.000 description 2
- VWQVUPCCIRVNHF-UHFFFAOYSA-N yttrium atom Chemical compound [Y] VWQVUPCCIRVNHF-UHFFFAOYSA-N 0.000 description 2
- 238000009825 accumulation Methods 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000005219 brazing Methods 0.000 description 1
- 235000008429 bread Nutrition 0.000 description 1
- 238000001723 curing Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 239000000945 filler Substances 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical compound [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 238000005245 sintering Methods 0.000 description 1
- 230000001629 suppression Effects 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
- 238000009736 wetting Methods 0.000 description 1
- 229910001928 zirconium oxide Inorganic materials 0.000 description 1
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- C—CHEMISTRY; METALLURGY
- C03—GLASS; MINERAL OR SLAG WOOL
- C03C—CHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
- C03C8/00—Enamels; Glazes; Fusion seal compositions being frit compositions having non-frit additions
- C03C8/24—Fusion seal compositions being frit compositions having non-frit additions, i.e. for use as seals between dissimilar materials, e.g. glass and metal; Glass solders
-
- C—CHEMISTRY; METALLURGY
- C03—GLASS; MINERAL OR SLAG WOOL
- C03C—CHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
- C03C10/00—Devitrified glass ceramics, i.e. glass ceramics having a crystalline phase dispersed in a glassy phase and constituting at least 50% by weight of the total composition
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B37/00—Joining burned ceramic articles with other burned ceramic articles or other articles by heating
- C04B37/003—Joining burned ceramic articles with other burned ceramic articles or other articles by heating by means of an interlayer consisting of a combination of materials selected from glass, or ceramic material with metals, metal oxides or metal salts
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2237/00—Aspects relating to ceramic laminates or to joining of ceramic articles with other articles by heating
- C04B2237/02—Aspects relating to interlayers, e.g. used to join ceramic articles with other articles by heating
- C04B2237/10—Glass interlayers, e.g. frit or flux
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2237/00—Aspects relating to ceramic laminates or to joining of ceramic articles with other articles by heating
- C04B2237/30—Composition of layers of ceramic laminates or of ceramic or metallic articles to be joined by heating, e.g. Si substrates
- C04B2237/32—Ceramic
- C04B2237/36—Non-oxidic
- C04B2237/365—Silicon carbide
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2237/00—Aspects relating to ceramic laminates or to joining of ceramic articles with other articles by heating
- C04B2237/30—Composition of layers of ceramic laminates or of ceramic or metallic articles to be joined by heating, e.g. Si substrates
- C04B2237/32—Ceramic
- C04B2237/38—Fiber or whisker reinforced
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2237/00—Aspects relating to ceramic laminates or to joining of ceramic articles with other articles by heating
- C04B2237/50—Processing aspects relating to ceramic laminates or to the joining of ceramic articles with other articles by heating
- C04B2237/84—Joining of a first substrate with a second substrate at least partially inside the first substrate, where the bonding area is at the inside of the first substrate, e.g. one tube inside another tube
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to a Ca-Ti-Y-Al-Si-O microcrystalline glass solder and SiCfA glass packaging method for SiC nuclear cladding tube port selects raw materials with excellent radiation resistance and no side effect on nuclear reaction process, adopts a melting-water cooling method to prepare microcrystalline glass solder with excellent mechanical property and good air tightness, depends on small high-temperature viscosity, thermal expansion coefficient and SiCfThe SiC matching and good wettability can be realized at the applicable temperature (less than or equal to 1450 ℃) and under the non-pressure condition of the domestic third-generation SiC fiberfThe port of the SiC nuclear cladding tube is packaged and connected, the prepared connecting joint has both a glass phase and a crystal phase, the glass phase ensures excellent sealing effect at high temperature,the crystal phase is beneficial to improving the high-temperature strength and promoting the SiCfThe application of SiC in the nuclear reactor reduces the risk of accidents such as nuclear radiation, nuclear leakage and the like, and improves the safety of the operation of the nuclear reactor.
Description
Technical Field
The invention belongs to the packaging technology of nuclear fuel cladding tubes, and relates to a Ca-Ti-Y-Al-Si-O microcrystalline glass solder and SiCfA glass packaging method for a/SiC nuclear cladding tube port, in particular to SiCfThe preparation and the packaging technology of the Ca-Ti-Y-Al-Si-O glass sealant and the glass pressing sheet at the port of the SiC nuclear cladding tube are mainly used for port packaging and connection of the nuclear cladding tube.
Background
On 11 th 3 th 2011, 9.0 th-level earthquake occurs near coastal areas of the fairy platform in japan, and the earthquake and the strong tsunami caused by the earthquake seriously create the first nuclear power station in the fukushima under the control of the power company in tokyo in japan, so that nuclear accidents caused by nuclear leakage are caused. The direct reason for occurrence of the Fudao nuclear accident is that tsunami causes power failure of a unit power supply system, water circulation of a loop system is stopped, a cooling system fails, steam in a pressure container cannot be normally sent out for power generation, a zirconium alloy cladding for wrapping a fuel assembly is exposed in the steam and reacts with water molecules in the zirconium alloy cladding at high temperature to generate zirconium oxide; meanwhile, when excessive hydrogen is continuously released by the zirconia and is discharged to an outside plant together with radioactive substances through a valve on the suppression pool along with steam, the concentration is overhigh due to accumulation in a region between the containment and the plant, and explosion is caused under the action of oxygen at high temperature, so that serious nuclear accidents are caused.
After the fukushima nuclear accident, the development of a new generation of pressurized water reactor nuclear fuel cladding material capable of replacing zirconium alloy cladding becomes a key problem to be solved urgently, the new generation of cladding tube material is resistant to irradiation and high temperature, has good chemical stability and good environmental performance (does not produce violent reaction with water and generates less hydrogen), can still keep the integrity of a reactor core when the nuclear accident occurs, ensures that nuclear fuel fission products and radioactive gas are not leaked, and can reduce the probability of nuclear leakage accidents to the maximum extent.
SiCfthe/SiC not only has good high-temperature mechanical property and chemical stability, high specific strength and high specific modulus, but also has excellent irradiation resistance, low residual heat of irradiation and low induced radioactivity, so that the SiC is an ideal candidate material for a new-generation nuclear cladding tube. The port encapsulation being SiCfThe port encapsulation technology becomes the key technology of the safe service of the SiC nuclear cladding tube. Due to the current SiCfThe SiC nuclear cladding tube adopts domestic third-generation silicon carbide fiber, the maximum service temperature is 1450 ℃, so the encapsulation temperature is lower than 1450 ℃; the cladding tube is a thin-wall slender tube, so that excessive stress cannot be applied in the processing process, and the cladding tube is prevented from being damaged; the packaging solder needs to have good radiation resistance; the packaging plug head needs to keep good mechanical property and air tightness under accident working conditions (1200 ℃, 25 MPa). These service requirements greatly limit the application of various packaging techniques to the packaging of nuclear cladding tubes. At present, the common packaging technology is difficult to meet the requirements at the same time.
CaO-Y is adopted in the invention patent of the packaging method of the SiCf/SiC nuclear cladding tube port CaO-Y2O3-Al2O3-SiO2 glass (application number CN201911162409.2)2O3-Al2O3-SiO2The glass finishes the pair SiCfAnd encapsulating the port of the/SiC nuclear cladding tube. The CYAS glass has low high-temperature viscosity and thermal expansion coefficient (3.9 multiplied by 10)-6) With SiCfThermal expansion coefficient of/SiC (4.0X 10)-6) Matching with SiCfthe/SiC composite material has good wetting effect, and the connecting joint has a compact and stable tissue structure, so that the dual requirements of the nuclear cladding tube port on mechanical property and air tightness can be ensured. However, the CYAS glass is packaged in pure glass phase, and has no crystal phase inside, so that improvement on the existing packaging technology is needed to further improve the high-temperature mechanical property of the CYAS glass.
Disclosure of Invention
Technical problem to be solved
To avoidThe invention provides a Ca-Ti-Y-Al-Si-O microcrystalline glass solder and SiC without the defects of the prior artfA glass packaging method of a port of a SiC nuclear cladding tube.
Technical scheme
SiCfThe Ca-Ti-Y-Al-Si-O microcrystalline glass solder at the end port of the SiC nuclear cladding tube is characterized by comprising the following components in percentage by mass: 3-10 wt.% of CaO and 1-5 wt.% of TiO 210 to 35 wt.% of Y2O320 to 40 wt.% of Al2O3And 30 to 50 wt.% of SiO2(ii) a The mass percentage of each component in the raw material composition is 100%.
The SiCfThe preparation method of the Ca-Ti-Y-Al-Si-O microcrystalline glass solder at the end port of the SiC nuclear cladding tube is characterized by comprising the following steps of: the mass fraction ratio is as follows: 3-10 wt.% of CaO and 1-5 wt.% of TiO 210 to 35 wt.% of Y2O320 to 40 wt.% of Al2O3And 30 to 50 wt.% of SiO2Placing the mixture into a ball mill, performing ball milling and uniformly mixing to obtain mixed powder, placing the mixed powder into an alumina crucible, placing the alumina crucible into a heat treatment furnace, performing heat preservation for 3-5 hours under the conditions of air atmosphere and heat treatment temperature of 1580-1680 ℃, taking out the mixed powder and pouring the heat preservation solution into cold water to obtain a transparent colorless glass block; and crushing and ball-milling the obtained glass blocks, and sieving to obtain the microcrystalline glass solder.
The ball milling time is not less than 7h, and the rotating speed of the ball mill is 200-300 r/min.
The particle size of the mixed powder is 0.5-1.5 μm.
By using the SiCfCa-Ti-Y-Al-Si-O microcrystalline glass solder pair SiC at end port of SiC nuclear cladding tubefThe method for encapsulating the port of the/SiC nuclear cladding tube is characterized by comprising the following steps:
step 1: uniformly mixing 70-90 wt.% of absolute ethyl alcohol with the glass solder to obtain a glass powder sealant;
step 2: putting the glass powder sealant into a circular tabletting mold, and pressing under the pressure of 6-12 MPa to obtain a glass tablet; the diameter of the circular tabletting mould is matched with the diameter of the bulge of the plug head of the cladding tube; the thickness of the circular pressing sheet is not less than 3 mm;
and step 3: uniformly coating the glass powder sealant on SiCfCoating the inner wall of the SiC nuclear cladding tube and the protruding part of the plug head of the cladding tube to a depth greater than the protruding height of the plug head of the cladding tube; placing the glass pressing sheet on the convex part of the plug head of the cladding tube, and assembling the glass pressing sheet on the SiCfthe/SiC nuclear cladding tube is arranged inside the shell;
and 4, step 4: SiC to be assembled with plugfPlacing the/SiC nuclear cladding tube in a heat treatment furnace, heating at 2-10 ℃/min under the argon atmosphere, preserving heat at 1350-1430 ℃ for 30-60 min, and cooling to room temperature at 2-10 ℃/min after heat preservation is finished to finish SiCfAnd encapsulating the SiC core cladding tube.
The SiCfPutting the SiC nuclear cladding tube and the cladding tube plug head into absolute ethyl alcohol for ultrasonic cleaning, and cleaning the cleaned SiCfPutting the SiC nuclear cladding tube and the cladding tube plug head into an oven for drying and then assembling;
advantageous effects
The invention provides a Ca-Ti-Y-Al-Si-O microcrystalline glass solder and SiCfA glass packaging method for SiC nuclear cladding tube port selects raw materials with excellent radiation resistance and no side effect on nuclear reaction process, adopts a melting-water cooling method to prepare microcrystalline glass solder with excellent mechanical property and good air tightness, depends on small high-temperature viscosity, thermal expansion coefficient and SiCfThe SiC matching and good wettability can be realized at the applicable temperature (less than or equal to 1450 ℃) and under the non-pressure condition of the domestic third-generation SiC fiberfThe port of the SiC nuclear cladding tube is packaged and connected, the prepared connecting joint has both a glass phase and a crystal phase, the glass phase ensures excellent sealing effect at high temperature, and the crystal phase is favorable for improving high-temperature strength and promoting SiCfThe application of SiC in the nuclear reactor reduces the risk of accidents such as nuclear radiation, nuclear leakage and the like, and improves the safety of the operation of the nuclear reactor.
The Ca-Ti-Y-Al-Si-O microcrystalline glass solder is prepared by a melting-water cooling method, and can be used for finishing SiC under the conditions of domestic third-generation SiC applicable temperature (less than or equal to 1450 ℃) and no pressurefThe encapsulation/connection of the SiC core cladding tube is favorable for further advancingSiCfApplication of SiC in nuclear reactor.
The Ca-Ti-Y-Al-Si-O glass solder is prepared by selecting low-activity elements with small nuclear irradiation decay rate, no side effect on the nuclear reaction process and excellent irradiation resistance through a melting-water cooling method, and the prepared glass solder has small high-temperature viscosity and thermal expansion coefficient and SiCfThe SiC has the characteristics of good matching and wettability, and can realize SiC under the applicable temperature (less than or equal to 1450 ℃) and no pressure conditions of the domestic third-generation SiC fiberfAnd packaging and connecting the port of the/SiC nuclear cladding tube.
The invention is the original CaO-Y2O3-Al2O3-SiO2Adding a certain amount of TiO on the basis of glass2The prepared connecting joint has a compact and stable internal structure, and excellent mechanical properties and air tightness. The connection joint has both glass phase and crystal phase, the XRD spectrum of the connection joint has a special steamed bun peak in an amorphous state and yttrium silicate and mullite crystal peaks, the glass phase can provide high-temperature sealing capability, and has obvious infiltration filling effect, thereby ensuring SiCfThe air tightness of the port of the SiC nuclear cladding tube; the crystal phase improves the high-temperature mechanical property, can further meet the dual requirements of the nuclear cladding tube port on the mechanical property and the air tightness, and is favorable for promoting the promotion of SiCfThe application of the SiC nuclear cladding tube reduces the risk of accidents such as nuclear radiation, nuclear leakage and the like and improves the safety of nuclear reactor operation.
Drawings
FIG. 1 is a work flow diagram of the present invention
FIG. 2 is SiCfDrawing of SiC nuclear cladding tube
FIG. 3 is SiCfDrawing of port plug head of SiC nuclear cladding tube
FIG. 4 is a graph showing the thermal expansion coefficient of Ca-Ti-Y-Al-Si-O glass in example 1 of the present invention.
FIG. 5 is a DSC chart of Ca-Ti-Y-Al-Si-O glass in example 1 of the present invention
FIG. 6 is an XRD graph of Ca-Ti-Y-Al-Si-O glass in example 1 of the present invention
FIGS. 7 and 8 are the microtopography of CTYAS glasses in examples 1, 2 and 3 of the present invention
Detailed Description
The invention will now be further described with reference to the following examples and drawings:
example 1
CaO and TiO with the particle size of 1 mu m2、Y2O3、Al2O3、SiO2The powder comprises the following components in percentage by mass: 5% of CaO and 5% of TiO 220% of Y2O330% of Al2O340% SiO2Putting the four powder materials into a ball milling tank, ball milling for 12h at the rotating speed of 300r/min, putting the ball milled mixed powder into an alumina crucible, carrying out heat treatment under the air atmosphere, wherein the heat treatment temperature is 1650 ℃, the heat preservation time is 2 hours, directly putting the ball milled mixed powder into cold water after heat treatment, and carrying out quenching to form the Ca-Ti-Y-Al-Si-O glass block. And crushing and ball-milling the glass blocks, and sieving the glass blocks by a 150-mesh sieve to obtain Ca-Ti-Y-Al-Si-O glass powder. And adding alcohol into the glass powder to form the packaging agent, wherein the mass fraction of the added alcohol is 90%. Coating the encapsulant on the inner wall of the cladding tube and the surface to be encapsulated of the plug head of the cladding tube, placing a glass pressing sheet with the thickness of 4mm on the plug head of the cladding tube, and mixing with SiCfAnd finishing assembly of the/SiC nuclear cladding tube. Placing the assembled core cladding tube and the plug head into a tube furnace for heat treatment, wherein the heat treatment atmosphere is argon, the heat treatment temperature is 1400 ℃, the heat preservation time is 30min, cooling to room temperature along with the furnace, and finishing the SiCfAnd sealing the port of the SiC core cladding tube.
Example 2
CaO and TiO with the particle size of 1 mu m2、Y2O3、Al2O3、SiO2The powder comprises the following components in percentage by mass: 3% of CaO and 2% of TiO 230% of Y2O325% of Al2O340% SiO2Ball-milling the four powder materials in a ball-milling tank at a rotating speed of 200r/min for 15h, placing the ball-milled mixed powder in an alumina crucible, carrying out heat treatment in air atmosphere at the heat treatment temperature of 1630 ℃ for 2h, directly placing the ball-milled mixed powder in cold water for quenching after heat treatment to form Ca-Ti-Y-Al-Si-OA glass block. And crushing and ball-milling the glass blocks, and sieving the glass blocks by a 150-mesh sieve to obtain Ca-Ti-Y-Al-Si-O glass powder. And adding alcohol into the glass powder to form the packaging agent, wherein the mass fraction of the added alcohol is 70%. Coating the encapsulant on the inner wall of the cladding tube and the surface to be encapsulated of the plug head of the cladding tube, placing a glass pressing sheet with the thickness of 3mm on the plug head of the cladding tube, and mixing with SiCfAnd finishing assembly of the/SiC nuclear cladding tube. Placing the assembled cladding tube and the plug head into a tube furnace for heat treatment, wherein the heat treatment atmosphere is argon, the heat treatment temperature is 1420 ℃, the heat preservation time is 45min, cooling to room temperature along with the furnace, and finishing the SiCfAnd sealing the port of the SiC core cladding tube.
Example 3
CaO and TiO with the particle size of 1 mu m2、Y2O3、Al2O3、SiO2The powder comprises the following components in percentage by mass: 5% of CaO and 3% of TiO227% of Y2O320% of Al2O345% SiO2Putting the four powder materials into a ball milling tank, ball milling for 13h at the rotating speed of 200r/min, putting the ball milled mixed powder into an alumina crucible, carrying out heat treatment in the air atmosphere, wherein the heat treatment temperature is 1600 ℃, the heat preservation time is 4 hours, directly putting the ball milled mixed powder into cold water for quenching after heat treatment, and forming the Ca-Ti-Y-Al-Si-O glass block. And crushing and ball-milling the glass blocks, and sieving the glass blocks by a 150-mesh sieve to obtain Ca-Ti-Y-Al-Si-O glass powder. And adding alcohol into the glass powder to form the packaging agent, wherein the mass fraction of the added alcohol is 90%. Coating the encapsulant on the inner wall of the cladding tube and the surface to be encapsulated of the plug head of the cladding tube, placing a glass pressing sheet with the thickness of 5mm on the plug head of the cladding tube, and mixing with SiCfAnd finishing assembly of the/SiC nuclear cladding tube. Placing the assembled cladding tube and the plug head into a tube furnace for heat treatment, wherein the heat treatment atmosphere is argon, the heat treatment temperature is 1400 ℃, the heat preservation time is 30min, cooling to room temperature along with the furnace, and finishing the SiCfAnd sealing the port of the SiC core cladding tube.
Example 4
CaO and TiO with the particle size of 1 mu m2、Y2O3、Al2O3、SiO2The powder comprises the following components in percentage by mass: 6% of CaO, 4% TiO225% of Y2O320% of Al2O345% SiO2Putting the four powder materials into a ball milling tank, ball milling for 13h at the rotating speed of 300r/min, putting the ball milled mixed powder into an alumina crucible, carrying out heat treatment in the air atmosphere, wherein the heat treatment temperature is 1600 ℃, the heat preservation time is 4 hours, directly putting the ball milled mixed powder into cold water for quenching after heat treatment, and forming the Ca-Ti-Y-Al-Si-O glass block. And crushing and ball-milling the glass blocks, and sieving the glass blocks by a 150-mesh sieve to obtain Ca-Ti-Y-Al-Si-O glass powder. And adding alcohol into the glass powder to form the packaging agent, wherein the mass fraction of the added alcohol is 70%. Coating the encapsulant on the inner wall of the cladding tube and the surface to be encapsulated of the plug head of the cladding tube, placing a glass pressing sheet with the thickness of 5mm on the plug head of the cladding tube, and mixing with SiCfAnd finishing assembly of the/SiC nuclear cladding tube. Placing the assembled cladding tube and the plug head into a tube furnace for heat treatment, wherein the heat treatment atmosphere is argon, the heat treatment temperature is 1420 ℃, the heat preservation time is 60min, cooling to room temperature along with the furnace, and finishing the SiCfAnd sealing the port of the SiC core cladding tube.
Example 5
CaO and TiO with the particle size of 1 mu m2、Y2O3、Al2O3、SiO2The powder comprises the following components in percentage by mass: 4.8% of CaO, 19.0% of Y2O328.6% of Al2O347.6% SiO2Putting the four powder materials into a ball milling tank, ball milling for 12h at the rotating speed of 300r/min, putting the ball milled mixed powder into an alumina crucible, carrying out heat treatment in the air atmosphere, wherein the heat treatment temperature is 1600 ℃, the heat preservation time is 4 hours, directly putting the ball milled mixed powder into cold water for quenching after heat treatment, and forming the Ca-Y-Al-Si-O glass block. And crushing and ball-milling the glass blocks, and sieving the glass blocks by a 150-mesh sieve to obtain Ca-Y-Al-Si-O glass powder. And adding alcohol into the glass powder to form the packaging agent, wherein the mass fraction of the added alcohol is 90%. Coating the encapsulant on the inner wall of the cladding tube and the surface to be encapsulated of the plug head of the cladding tube, placing a glass pressing sheet with the thickness of 3mm on the plug head of the cladding tube, and mixing with SiCfAnd finishing assembly of the/SiC nuclear cladding tube. Placing the assembled cladding tube and the plug head into a tube furnace for heat treatment in argon atmosphereGas, heat treatment temperature is 1400 ℃, heat preservation time is 30min, furnace cooling is carried out to room temperature, and SiC is completedfAnd sealing the port of the SiC core cladding tube.
The embodiment of the invention can be used for preparing SiC from domestic third-generation SiC fibersfGlass encapsulation/connection of the/SiC nuclear cladding tube ports, it can again be seen from the examples that the following beneficial effects are achieved:
1. the Ca-Ti-Y-Al-Si-O glass solder, the solder and SiC are prepared by a melting-water cooling methodfThe SiC composite material has good wettability, and can realize SiC at the applicable temperature (less than or equal to 1450 ℃) and under the non-pressure condition of the domestic third-generation SiC fiberfThe SiC core cladding tube is packaged and connected, and the prepared connecting joint has a compact and stable internal structure, excellent mechanical property and air tightness, and the thermal expansion coefficient of the joint and SiCfThe matching of the/SiC composite material can meet the dual requirements of the cladding tube on mechanical property and air tightness.
2. The invention is at CaO-Y2O3-Al2O3-SiO2Adding a certain amount of TiO on the basis of glass2The prepared connecting joint has both glass phase and crystal phase, the XRD spectrum of the connecting joint has unique steamed bread peaks in amorphous state and yttrium silicate and mullite crystal peaks, the glass phase can provide high-temperature sealing capability, and has obvious infiltration filling effect, thereby ensuring SiCfThe air tightness of the port of the SiC nuclear cladding tube; the crystal phase improves the high-temperature mechanical property, can further meet the dual requirements of the nuclear cladding tube port on the mechanical property and the air tightness, and is favorable for promoting the promotion of SiCfThe application of the SiC nuclear cladding tube reduces the risk of accidents such as nuclear radiation, nuclear leakage and the like and improves the safety of nuclear reactor operation. The components which are varied according to the invention are not freely determinable.
3. According to the invention, the problem of insufficient brazing filler metal caused by sintering, curing and infiltration is solved by placing the glass pressing sheet on the plug head of the cladding tube, the probability of generating welding seams after heat treatment is reduced, a compact sealing layer can be formed above the plug head, and a compact connecting layer is further formed between the cladding tube and the plug head, so that the SiC is further effectively improvedfThe SiC core cladding tube has air tightness.
Claims (6)
1. SiCfThe Ca-Ti-Y-Al-Si-O microcrystalline glass solder at the end port of the SiC nuclear cladding tube is characterized by comprising the following components in percentage by mass: 3-10 wt.% of CaO and 1-5 wt.% of TiO210 to 35 wt.% of Y2O320 to 40 wt.% of Al2O3And 30 to 50 wt.% of SiO2(ii) a The mass percentage of each component in the raw material composition is 100%.
2. The SiC of claim 1fThe preparation method of the Ca-Ti-Y-Al-Si-O microcrystalline glass solder at the end port of the SiC nuclear cladding tube is characterized by comprising the following steps of: the mass fraction ratio is as follows: 3-10 wt.% of CaO and 1-5 wt.% of TiO210 to 35 wt.% of Y2O320 to 40 wt.% of Al2O3And 30 to 50 wt.% of SiO2Placing the mixture into a ball mill, performing ball milling and uniformly mixing to obtain mixed powder, placing the mixed powder into an alumina crucible, placing the alumina crucible into a heat treatment furnace, performing heat preservation for 3-5 hours under the conditions of air atmosphere and heat treatment temperature of 1580-1680 ℃, taking out the mixed powder and pouring the heat preservation solution into cold water to obtain a transparent colorless glass block; and crushing and ball-milling the obtained glass blocks, and sieving to obtain the microcrystalline glass solder.
3. The method of claim 2, wherein: the ball milling time is not less than 7h, and the rotating speed of the ball mill is 200-300 r/min.
4. The method of claim 2, wherein: the particle size of the mixed powder is 0.5-1.5 μm.
5. Use of the SiC of claim 1fCa-Ti-Y-Al-Si-O microcrystalline glass solder pair SiC at end port of SiC nuclear cladding tubefThe method for encapsulating the port of the/SiC nuclear cladding tube is characterized by comprising the following steps:
step 1: uniformly mixing 70-90 wt.% of absolute ethyl alcohol with the glass solder to obtain a glass powder sealant;
step 2: putting the glass powder sealant into a circular tabletting mold, and pressing under the pressure of 6-12 MPa to obtain a glass tablet; the diameter of the circular tabletting mould is matched with the diameter of the bulge of the plug head of the cladding tube; the thickness of the circular pressing sheet is not less than 3 mm;
and step 3: uniformly coating the glass powder sealant on SiCfCoating the inner wall of the SiC nuclear cladding tube and the protruding part of the plug head of the cladding tube to a depth greater than the protruding height of the plug head of the cladding tube; placing the glass pressing sheet on the convex part of the plug head of the cladding tube, and assembling the glass pressing sheet on the SiCfthe/SiC nuclear cladding tube is arranged inside the shell;
and 4, step 4: SiC to be assembled with plugfPlacing the/SiC nuclear cladding tube in a heat treatment furnace, heating at 2-10 ℃/min under the argon atmosphere, preserving heat at 1350-1430 ℃ for 30-60 min, and cooling to room temperature at 2-10 ℃/min after heat preservation is finished to finish SiCfAnd encapsulating the SiC core cladding tube.
6. The method of claim 1, further comprising: the SiCfPutting the SiC nuclear cladding tube and the cladding tube plug head into absolute ethyl alcohol for ultrasonic cleaning, and cleaning the cleaned SiCfAnd putting the/SiC nuclear cladding tube and the cladding tube plug head into an oven for drying and then assembling.
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