Computational Determination of Radiation Characteristics of Activated Medium- and High-Level Radioactive Waste Produced During Operation of NPPs with VVER

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