Solving the problem of environmentally safe management of radioactive waste in addition to ensuring the safe operation of nuclear power plants is a main condition for the acceptability of nuclear power as a reliable source of electricity. The problem of liquid radioactive waste management is updated. The ion-selective purification method was chosen as the optimal option for liquid radioactive waste for final isolation of conditioned RW has been substantiated. High efficiency of new generation inorganic sorbents increases the efficiency of ion-selective sorption units provided that the problem of safe storage of spent medium and high activity sorbent in places of processing, transportation and burial is solved. In this connection, an important condition for realization of this technology is optimization of radiation protection of a container with radioactive waste. The task on optimization of the effective dose received from the spent filter-container is specified. The structure and dimensions of the container are stipulated. The protective materials for the inner capsule and the outer protective coating, as well as the material of the filler located between the capsule and the container shell are selected. Monte Carlo (MC) simulations with an input value of F6 and six detectors on each side of the container were performed to predict the released energy at a distance of 1 m from the outer shell of the container. The results of the analysis of the effect of the radioactive waste capsule material and its wall thickness, the type of the filler and its thickness on the radiation protection characteristics of the container are presented. Isotopes 137Cs and 60Co in concentrations of 90% and 10% respectively were chosen as solid RAW filling the container. Dependence of allocated energy, equivalent dose, changes in transmittance and radiation shielding coefficients on the material and thickness of the receiving capsule were obtained based on simulation results. Conclusions on the optimal parameters of the filter-container are formulated and the advantages of the investigated solutions are substantiated.
Translated title of the contributionOPTIMIZATION OF RADIATION PROTECTION OF CONTAINERS FOR SOLIDIFIED LIQUID RADIOACTIVE WASTE
Original languageRussian
Pages (from-to)54-63
Number of pages10
JournalМеждународный научный журнал "Альтернативная энергетика и экология"
Issue number2 (407)
DOIs
Publication statusPublished - 2023

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