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CN-121782361-B - Insulating sealing gasket for nuclear power equipment and preparation method thereof

CN121782361BCN 121782361 BCN121782361 BCN 121782361BCN-121782361-B

Abstract

The application relates to the field of sealing materials, and particularly discloses an insulating sealing gasket for nuclear power equipment and a preparation method thereof. The insulating sealing gasket for the nuclear power equipment comprises an outer layer material and an inner layer material, wherein the outer layer material is coated on the surface of the inner layer material, the outer layer material comprises, by mass, 50% -60% of silane coupling agent modified phenolic resin, 35% -45% of composite fibers and 3% -5% of epoxy functional silane adhesion promoters, and the inner layer material comprises, by mass, 45% -55% of fluorine-containing modified epoxy resin, 30% -40% of polyimide fibers and 10% -20% of high-temperature-resistant nano-reinforcing microspheres. The insulating sealing gasket for the nuclear power equipment has the advantages of high pressure resistance and high temperature resistance.

Inventors

  • MA QIONGXIU
  • ZHANG LI
  • HUANG DEZHONG

Assignees

  • 成都俊马密封科技股份有限公司

Dates

Publication Date
20260505
Application Date
20260304

Claims (9)

  1. 1. The insulating sealing gasket for the nuclear power equipment is characterized by comprising an outer layer material and an inner layer material, wherein the outer layer material is coated on the surface of the inner layer material, the outer layer material comprises, by mass, 50% -60% of silane coupling agent modified phenolic resin, 35% -45% of composite fibers and 3% -5% of epoxy functional silane bonding promoters, and the inner layer material comprises, by mass, 45% -55% of fluorine-containing modified epoxy resin, 30% -40% of polyimide fibers and 10% -20% of high-temperature resistant nano reinforcing microspheres; The fluorine-containing modified epoxy resin is prepared by the following steps of mixing 80-120 parts by weight of bisphenol A epoxy resin and 5-10 parts by weight of reactive diluent at 80-85 ℃, adding 0.5-1.5 parts by weight of catalyst, adding 8-12 parts by weight of fluorine-containing anhydride modifier, and reacting for 2-3 hours at 80-90 ℃.
  2. 2. The insulating mat for nuclear power plant according to claim 1, wherein the composite fiber comprises an aramid fiber and an insulation-treated carbon fiber, and the mass ratio of the insulation-treated carbon fiber to the aramid fiber is (3-4): 2.
  3. 3. The insulating mat for nuclear power plant according to claim 2, wherein the insulation-treated carbon fiber is prepared by reflux-oxidizing the carbon fiber in concentrated nitric acid at 60-80 ℃, washing and drying, immersing in an ethyl orthosilicate hydrolysate, and then heat-treating at 500-600 ℃ for 1-2 hours.
  4. 4. The insulating gasket for nuclear power equipment according to claim 1, wherein the high-temperature-resistant nano-reinforced microspheres are polyimide microspheres or silica nano-microspheres surface-modified by a silane coupling agent, and the particle size of the high-temperature-resistant nano-reinforced microspheres is 100-300nm.
  5. 5. The insulating gasket for nuclear power equipment according to claim 1, wherein the inner layer material is further embedded with a three-dimensional mesh-shaped reinforcing skeleton, and the three-dimensional mesh-shaped reinforcing skeleton is prepared from one or two of silicon carbide ceramic powder and silicon nitride ceramic powder by a 3D printing technology.
  6. 6. The insulating mat for a nuclear power plant according to claim 5, wherein the method for manufacturing the three-dimensional mesh-like reinforcing skeleton comprises: Mixing 60-80 parts of ceramic powder, 1-5 parts of dispersing agent and 20-40 parts of solvent for ball milling, adding 25-35 parts of chopped carbon fiber, and dispersing to form slurry; 3D printing is carried out on the sizing agent through an adhesive spraying technology, the thickness of the layer is set to be 100-150 mu m, and after printing, infrared curing and shaping are carried out; Degreasing the shaped blank, and sintering for 2-3 hours at 1800-2000 ℃ under the protection of argon.
  7. 7. A method of manufacturing an insulating gasket for a nuclear power plant as claimed in any one of claims 1 to 6, comprising the steps of: S1, blending silane coupling agent modified phenolic resin, composite fiber and adhesion promoter at 100-120 ℃, hot-pressing and preforming at 140-160 ℃ and 8-12MPa pressure, and maintaining the pressure for 15-25 minutes to obtain an outer layer material preform; s2, heating the fluorine-containing modified epoxy resin to 80-85 ℃, adding high-temperature-resistant nano reinforced microspheres, performing ultrasonic dispersion for 20-30 minutes, then adding polyimide fibers, stirring and mixing to obtain an inner layer material premix, and performing pre-curing for 60-80 minutes at 95-105 ℃ to obtain an inner layer material preform; S3, placing the inner layer material preformed body into the outer layer material preformed body, hot-pressing and compounding for 40-50 minutes under the pressure of 145-155 ℃ and 13-15MPa, and then performing step post-curing under the protection of nitrogen, namely heating to 120-130 ℃ at the speed of 1-2 ℃ per minute, keeping the temperature for 2 hours, continuously heating to 150-160 ℃ and keeping the temperature for 4 hours, heating to 180-190 ℃ and keeping the temperature for 6 hours, and cooling along with a furnace to obtain the insulating sealing gasket.
  8. 8. The method of manufacturing an insulation mat for nuclear power plants according to claim 7, wherein a three-dimensional mesh reinforcement matrix is placed in the inner layer material premix prior to the pre-curing in step S2.
  9. 9. The method for producing an insulating gasket for nuclear power equipment according to claim 7, wherein the insulating gasket obtained after the step post-curing treatment in step S3 is subjected to surface plasma treatment using a mixed gas of argon and oxygen in a volume ratio (7-4): 1, wherein the plasma power in the plasma treatment is 300-400W, the treatment time is 120-140 seconds, and the pressure is 45-55Pa.

Description

Insulating sealing gasket for nuclear power equipment and preparation method thereof Technical Field The application relates to the field of sealing materials, in particular to an insulating sealing gasket for nuclear power equipment and a preparation method thereof. Background In the field of nuclear power generation, the safe and stable operation of nuclear power equipment is important. The sealing ring in the nuclear power equipment is used as a key sealing component, and plays an important role in preventing medium leakage, maintaining the pressure stability in the equipment and ensuring the nuclear safety. The working environment is extremely harsh, and the sealing performance and the mechanical performance are good in the long-term operation process, and the sealing device is required to bear the effects of high temperature, high pressure, strong radiation and various chemical corrosive mediums. At present, common sealing materials in the market, such as common rubber, polyurethane and the like, are widely applied in conventional industrial scenes and have certain sealing capability, but have obvious short plates in pressure resistance and temperature resistance. The common rubber has a temperature resistant range of 20 ℃ below zero to 120 ℃ below zero, and when the temperature exceeds the temperature range, the rubber gradually hardens or softens to cause the sealing performance to be drastically reduced, and the pressure resistant capability of the common rubber can only bear a few megapascals and is difficult to cope with high-pressure environment. Although the polyurethane material has good wear resistance, the upper limit of the polyurethane material is generally 80-150 ℃ and creep easily occurs under high pressure, so that the sealing effect is affected. And the nuclear power field has extremely severe requirements on tightness. When the reactor cooling system of the nuclear power station is operated, the internal pressure can reach 15MPa, the temperature is more than 300 ℃, and the intense neutron radiation is accompanied. Under such extreme conditions, the conventional sealing material cannot meet the use requirements at all. Once a sealing failure occurs in a nuclear power plant, even a very small leakage of a common sealing material can cause serious safety accidents, so that radioactive substances leak, and immeasurable harm is caused to the environment and human health. Therefore, a new sealing gasket needs to be developed for the use of nuclear power equipment. Disclosure of Invention In order to improve the high-pressure resistance and the high-temperature resistance of the sealing material and enable the sealing material to meet the requirements of safe use of nuclear power equipment, the application provides an insulating sealing gasket for the nuclear power equipment and a preparation method thereof. The application provides an insulating sealing gasket for nuclear power equipment, which adopts the following technical scheme: the insulating sealing gasket for the nuclear power equipment comprises an outer layer material and an inner layer material, wherein the outer layer material is coated on the surface of the inner layer material, the outer layer material comprises, by mass, 50% -60% of silane coupling agent modified phenolic resin, 35% -45% of composite fibers and 3% -5% of epoxy functional silane adhesion promoters, and the inner layer material comprises, by mass, 45% -55% of fluorine-containing modified epoxy resin, 30% -40% of polyimide fibers and 10% -20% of high-temperature resistant nano reinforcing microspheres; The fluorine-containing modified epoxy resin is prepared by the following steps of mixing 80-120 parts by weight of bisphenol A epoxy resin and 5-10 parts by weight of reactive diluent at 80-85 ℃, adding 0.5-1.5 parts by weight of catalyst, adding 8-12 parts by weight of fluorine-containing anhydride modifier, and reacting for 2-3 hours at 80-90 ℃. By adopting the technical scheme, the outer layer material takes the silane coupling agent modified phenolic resin as a matrix, the silane coupling agent is adopted to modify the phenolic resin, the matrix is effectively toughened and the brittleness is reduced, high-proportion composite fibers are introduced to form a dense reinforced network, the fracture toughness is greatly improved through a crack pinning and deflection mechanism, and a bearing framework is formed to bear extreme high pressure. The inner layer material takes fluorine-containing modified epoxy resin as a matrix, and the fluorine-containing chain segment is introduced, so that the chemical medium corrosion resistance of the resin matrix is remarkably improved, meanwhile, excellent cohesiveness and toughness are maintained, the combination of the inner layer material and the outer layer material and the certain deformation of the overall structure of the inner layer and the outer layer design after being pressed are ensured, and the sealing effect is im