5 results about "High-level waste" patented technology

The invention relates to a high-radioactive waste disposal simulation method and system based on multi-field coupling. The method comprises the following steps: constructing a three-dimensional finite element model of a high-radioactive waste repository and a surrounding geological medium based on physical field simulation; simulating temperature change around the high-radioactive waste repository, underground water flow velocity change and radionuclide concentration change; based on a geochemical calculation model, performing chemical reaction calculation on the distribution of the radioactive concentration of the high-radioactive waste in underground water and rock-soil media, including dissolution, precipitation, adsorption and ion exchange of the high-radioactive waste; and carrying out iterative coupling on the physical field simulation and the geochemical calculation model, and outputting a high-radioactive waste disposal simulation result which comprises a radionuclide concentration three-dimensional distribution diagram, a migration flux vector diagram and temperature field distribution. Through iterative coupling of a physical field and a chemical field, high-precision simulation prediction of nuclide migration behaviors in a high-radioactive waste long-term disposal environment is realized, and a simulation result is close to an actual migration process.

This invention belongs to the field of high-level radioactive waste treatment technology, specifically relating to an apparatus and method for studying the diffusion of radionuclides in barrier materials. The apparatus includes a sample holding unit, a first fluid circulation unit, a second fluid circulation unit, and a fluid circulation drive unit. The sample holding unit is used to fix the barrier material sample, and its end caps are detachably sealed. The first and second fluid circulation units each include a water tank disposed inside the end caps and connected inlet and outlet holes. The water tank has two interchangeable structural forms: a concave water tank and a spiral channel. The fluid circulation drive unit is used to drive the fluid to circulate independently within the two water tanks to maintain a constant concentration. By changing the water tank structure, this apparatus can use a concave water tank to adapt to rigid monolithic media, or a spiral channel combined with a porous filter membrane to adapt to soft powder media, thereby achieving complete diffusion simulation of various barrier materials in the disposal repository.

The application discloses a backfilling method of spherical bentonite group particles in irregular structures, which comprises the preparation of the spherical bentonite group particles, the backfilling of the spherical bentonite group particles and the compaction of the spherical bentonite group particles. The application proposes the idea of backfilling by using bentonite group particles aiming at the high-quality backfilling problem of irregular structures in narrow spaces in radioactive waste disposal, determines the preparation conditions of the spherical bentonite group particles, designs a bentonite group particle spraying device, and proposes the backfilling ratio of the bentonite group particles + dry powder and the compaction mode by using a vibrating pipe, so that the backfilling quality and efficiency of irregular structures in radioactive waste disposal can be significantly improved. Meanwhile, the technology can be popularized to the backfilling engineering of the entire radioactive waste disposal structure and other waste disposal fields. The application solves the problem of low backfilling efficiency and quality of irregular parts or narrow spaces in radioactive waste disposal, and guarantees the quality and reliability of the backfilling structure.

This application discloses a manufacturing process for a transport container of highly radioactive materials, relating to the field of radioactive material transport container manufacturing technology. The process includes the following steps: S1: Fabricating inner and outer shells and a shielding plug shell; S2: Tinning and lead-plating the outer surface of the inner shell and the inner surface of the outer shell, and tinning the inner surface of the shielding plug; S3: Testing the adhesion rate of the lead-plated layers of the inner and outer shells; S4: Welding the inner and outer shells into a cylindrical body; S5: Pouring lead into the cylindrical body and the shielding plug shell; S6: Removing the lead-filled riser; S7: Sealing and welding the bottom plates of the cylindrical body and the shielding plug; S8: Final machining; S9: Conducting acceptance tests on the transport container. This application uses a cylindrical body and a shielding plug to form the transport container. Tinning and lead-plating the cylindrical body before pouring lead ensures better adhesion between the lead layer and the cylindrical body after the lead liquid solidifies, reducing the likelihood of separation.

The invention belongs to the technical field of high radioactive waste treatment, and relates to a high-entropy ferrite rare earth based perovskite ceramic solidified body and a preparation method and application thereof.The general formula of the solidified body is A1 / n (FexBy) O3, n represents the number of element types of the A lattice site of the high-entropy A1 / n (FexBy) O3 ferrite rare earth based perovskite ceramic solidified body, n is an integer and is larger than or equal to 3 and smaller than or equal to 7, and the A element types include Bi, Sc, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Y, Ho, Er, Tm, Yb and Lu; m is at least three of transition metal elements including Cr, Mn, Co, Ni, Al, Ti, Zr, Hf, Nb, Ta and Ce, x is equal to 0.01 to 1.00, and x is equal to 0 to 0.99. According to the method, a high-entropy strategy is introduced into the ferrite rare earth perovskite ceramic solidified body, the ceramic solidified body not only can solidify various key high-radionuclides, but also has excellent chemical stability, low leaching rate and low preparation temperature, and the disadvantage that ceramic solidified nuclides are high in selectivity and single is effectively avoided. Due to the excellent performance of the ceramic solidified body, the ceramic solidified body has great application potential in the field of solidification treatment of high-radioactivity nuclear waste of a spent fuel reprocessing plant.