Material product cup in nuclear fuel post-processing plant

Abstract

The invention belongs to the technical field of radiation shielding design of radioactive materials in a nuclear fuel post-processing plant, and particularly relates to a material product cup in the nuclear fuel post-processing plant for storing radioactive materials extracted by the nuclear fuel post-processing plant. The material product cup includes an outer cup body (1) which is arranged at the outer layer and can be sealed by an outer cup cover (2) and an inner cup body (3) which is arranged inside the outer cup body (1) and can be sealed by an inner cup cover, wherein the inner cup body(3) is used for storing the radioactive materials, alpha particles, beta particles and other charged particles generated by the radioactive materials in the inner cup body (3) can be shielded completely through the sealed outer cup body (1) and the sealed inner cup body (3), and heat generated by the radioactive materials can be transferred. A variety of radioactive rays radiated by the radioactive materials can be shielded through the product cup, the irradiation dose of bremsstrahlung photons to workers can be reduced, the contact dose rate of the surface of the product cup can be reduced by15-40%, and the operation cost of the nuclear fuel post-processing plant is reduced.

Description

technical field [0001] The invention belongs to the technical field of radiation shielding design for radioactive materials in nuclear fuel reprocessing plants, and in particular relates to a material product cup for nuclear fuel reprocessing plants. Background technique [0002] After a period of storage, the spent fuel unloaded from the nuclear power plant will be transported to the nuclear fuel reprocessing plant for processing, and the fuel that can be reused for production will be extracted. Spent fuel reprocessing generally undergoes processes such as chemical shearing, dissolution, purification, purification, and collection. Finally, the extracted and produced radioactive materials will be placed in product cups or other storage containers and stored in product warehouses. . [0003] The source item nuclide composition of the material is relatively complex. It usually contains not only isotopes of actinide elements such as U, Pu, Np, Am, and Cm, but also doped with o...

AI Technical Summary

Problems solved by technology

[0013] The purpose of the present invention is to optimize the design of radiation shielding for material product cups in nuclear fuel reprocessing plants, to propose a shielding design scheme that can effectively reduce the exposure dose of workers, and to solve the problem of insufficient shielding effect during the operation and transportation of material product cups in the current design. The problem of excessive exposure dose to personnel (especially the problem of exposure to bremsstrahlung photons), to ensure that the exposure dose of staff is as low as possible when working in the surrounding area

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