55 results about "Radiation stability" patented technology

The invention discloses a 3-sulfoglutaramide type extraction agent. The invention simultaneously provides a preparation method and application of the extraction agent. The preparation method comprises the following steps: firstly reacting methanol with thiodiacetic acid to obtain dimethyl thiodiacetate, and finally reacting corresponding amine with dimethyl thiodiacetate to obtain corresponding 3-sulfoglutaramide. The extraction efficiency of the extraction agent against a precious metal, namely palladium, is 98.16%-99.22%. The extraction agent can be simultaneously applied to a mixed solution containing palladium, platinum, copper, iron, zinc and other base metals for recovering palladium. The preparation method disclosed by the invention is simple and easy to operate, and the extraction agent has excellent extraction performance against palladium ions in a high-acid solution; and furthermore, the extraction agent is stable to a strong acid and good in radiation stability, the synthesis method is simple, and the cost is low.

The invention discloses a preparation method of heat-resisting and corrosion-resisting engineering plastic. The preparation method disclosed by the invention is characterized in that a third phenolphthalein monomer is introduced in a preparation process of master batch, and a flexible diethanol part in a polyester macromolecular chain is replaced by a rigid phenolphthalein group, so that a rigid diacid monomer and rigid phenolphthalein monomer connected segment is formed, the rigidity and the crystallization performance of a whole molecule are enhanced, and glass-transition temperature and a melting point are raised. According to the preparation method disclosed by the invention, by adopting a radiation crosslinking process, heat resistance and corrosion resistance of the engineering plastic are improved; according to an adopted radiation crosslinking agent, benzene-containing anhydride is used as a synthetic raw material, and a benzene ring structure is introduced, so that the melting point of a crosslinking promoter is improved, and the radiation resisting stability of the crosslinking promoter is further improved; prepared engineering plastic adopts the radiation crosslinking promoter; having increased molecular weight, a benzene ring structure and low high-temperature volatility, the radiation crosslinking promoter has good compatibility with the engineering plastic; according to the preparation method disclosed by the invention, flame retardant materials such as graphene, titanium dioxide and halloysite nanotubes and aging-resisting materials such as wollastonite needle-like fibers form a compound synergistic effect, so that the flame retardant property and the aging resisting property of the engineering plastic are greatly improved.

The invention discloses a nuclear-grade ion exchange resin based core-shell-structure composite material and a preparation method thereof. The core-shell-structure composite material takes a rare earth oxide as a core and takes nuclear-grade strong-alkali anion exchange resin as a shell. The rare earth oxide refers to cerium oxide, lanthanum oxide or praseodymium oxide. The nuclear-grade strong-alkali anion exchange resin is made from styrene, divinyl benzene, pore-forming agents and initiators. The preparation method of the composite material includes preparing the rare earth oxide, adding the rare earth oxide into oil-phase mixed liquor comprising the styrene, the divinyl benzene, the pore-forming agents and the initiators, sequentially allowing polymerization, chloromethylation, amination and transformation reactions, and allowing the nuclear-grade strong-alkali anion exchange resin to grow on the surface of the rare earth oxide through polymerization. The obtained core-shell-structure composite material has extremely high surface purity, high radiation element exchange volume, and high chemical and radiation resisting stability, and can directly serve as a water treating agentin primary-circuit water circulating systems in the nuke industry.

The invention discloses a preparation method of a SiC-based multi-phase ceramic solidified body used for radioactive graphite solidification treatment, and the preparation method is characterized by comprising the following steps: using silicon powder, graphite powder, MgO and Al (OH) 3 as raw materials, preparing MgAl2O4 powder, preparing Si-C powder, preparing SiC-MgAl2O4 multi-phase powder, adding polyvinyl alcohol, performing sol-granulating, shaping and glue discharging, vacuum hot-pressing sintering and the like to obtain the SiC-based multi-phase ceramic solidified body at low temperature. The SiC-based multi-phase ceramic solidified body with excellent anti-radiation stability, chemical stability, mechanical stability and thermal stability is prepared from the safe and cheap raw materials by a simple and practical vacuum hot-pressing sintering technique at the low temperature. The prepared SiC-based multi-phase ceramic solidified body is particularly suitable for the ceramic solidification treatment of high-radioactive activity graphite waste.