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Information × Registration Number 0224U001320, 0123U101904 , R & D reports Title Radiation safety during transportation of spent nuclear fuel and handling of radioactive waste at Ukrainian NPPs popup.stage_title Head Hirka Ihor O., Доктор фізико-математичних наук Registration Date 21-01-2024 Organization V.N. Karazin Kharkiv National University popup.description2  With the help of MCNP, Geant4 and PHITS packages, thermal and ionizing radiation fields of spent nuclear fuel (SNF) when passing through protections and auxiliary structures with different geometry and elemental composition of the HI-STAR 190 UA transport container (NOLTEC INTERNATIONAL Corporation) were investigated. The new result is an effective radiation protection made of Pb+Al alloy with boron additive to weaken gamma-quantum and neutron radiation. It has been established that the combined Pb-Fe protection for the HI-STAR 190 UA TC is an effective barrier against gamma radiation when placed in the BCC 31 VTVZ nuclear power plant with an initial fuel enrichment of 4.4%, a burn-up of 55 MW×d/t.U after a three-year campaign in reactor VVER-1000 and aging in reactor basins for 7 years or more. Numerically, it is shown that there are areas in TC where the level of dose load exceeds the limit level, which was established according to the calculations of the company HOLTEC, and reducing the number of VTVZ in itself is not expedient. To ensure the minimization of the dose load, it is necessary to surround the most active VTVZ-A with less active VTVZ. It was established that the most optimal option for transporting 31 VTVZ is a TC with additional protection against neutrons in the lower part and with BCC with a mixed arrangement of 24 VTVZ and 7 VTVZ-A. It was established that ensuring the required level of radiation safety is possible only when an additional layer of Holtite-B type neutron protection material is installed in the lower part of the TC. Transportation of 31 fuel assemblies in a TC with a total heat output of 37.2 kW will not violate thermal safety standards (investigated using the SolidWorks Flow Simulation software package). The results of the work can be used in the transportation and storage of spent nuclear fuel of the NPP, during the training of specialists, in scientific research. Product Description popup.authors Azarenkov Mykola Oleksiyovych Alyokhina Svitlana V. Berezhny Yuri A. Gakh Andrii H. Kovtyn Volodymyr E. Mazilin Bohdan O Prokhorets Svitlana Ivanivna Rudychev Yegor V popup.nrat_date 2024-01-21 Close