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The article describes the methodology of computational determination of specific activity of radionuclides in the radioactive waste in the form of spent neutron measurement channels (NMCs) TVS-2M of VVER-1000 reactor. The results of research on the dependence of the specific activity of radionuclides on the NMC lifetime, number of fuel elements, gadolinium amount, enrichment and initial burn-up of fuel assemblies are given. The calculations have been carried out by the Monte Carlo method using the MCU-6 computer program. To verify the results of calculations, a method based on measurements of the gamma radiation dose rate from activated radioactive waste is proposed.
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Selkin et al. (2024) studied this question.
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