Search academic texts

Information × Registration Number 0226U002855, (0123U101904) , R & D reports Title Radiation safety during transportation of spent nuclear fuel and handling of radioactive waste at Ukrainian NPPs popup.stage_title Інженерна модель ТК з (Pb+Al) та варіанти легких ангарних сховищ на території АЕС Head Hirka Ihor O., Доктор фізико-математичних наук Registration Date 09-03-2026 Organization V.N. Karazin Kharkiv National University popup.description1 The objective of this work is to develope effective radiation protection of transport casks (TC) and options for modification of TC "HI-STAR 190 UA", the methodology of placement of spent fuel assembly (SFA) to ensure radiation safety and heat loads during the transportation of nuclear fuel, as well as the justification of radiation safety of temporary storage of conditioned radioactive waste (RAW) in light hangar storages on the territory nuclear power plant. a) Development of additional radiation protection and heat-conducting elements in the HI-STAR 190 UA TC model while minimizing their weight and maintaining dimensional characteristics. b) Study of the effectiveness of radiation shields made of Pb+Al alloy with boron addition for weakening the gamma-quantum and neutron radiation of spent nuclear fuel in MCNP and PHITS packages. c) Calculating the gamma and neutron radiation of spent fuel outside the TC "HI-STAR 190 UA" with additional radiation protection in the MCNP and PHITS packages. d) Calculations of heat release in the "HI-STAR 190 UA" TC model with heat-conducting elements and determination of the permissible time of spent fuel in the TC. e) Development of an engineering model of TC based on a Pb+Al alloy with boron addition and determination of permissible burnout and holding time of spent fuel (31 SFA) to ensure radiation safety and thermal regimes during transportation. f) Analysis of characteristics of RAW after processing: burning, pressing and vaporization at the Rivne, Khmelnytskyi and Pivdenno-Ukrainian NPPs. g) Justification of the radiation safety of storage of conditioned radioactive waste for light hangar storage options on the territory of the RNPP, KhNPP, PUNPP. popup.description2 The storage of spent nuclear fuel (SNF) from Ukrainian NPPs in the central SNF storage facility using the dry method involves its transportation in the HI-STAR 190 UA transport container (TC) developed by Holtec. The existing design of this TC does not provide the necessary heat removal, and the neutron component of the dose loads exceeds the permissible limits. The neutron radiation dose near the middle of the side surface of the TC is shown not to be the maximum, and therefore there are areas where the dose load exceeds the limit level predicted by Holtec. The required level of radiation safety can only be ensured by installing an additional layer of Holtite-B neutron shielding material in the lower part of the TC. To minimize the dose load, it is proposed to surround the most active spent fuel assemblies (SFA) in the TC with less active SFAs. It has been shown that if there are no violations of thermal safety criteria under stationary conditions, the relevant criteria will also be met during fuel transportation. It is proposed to replace lead as a TC material with a composite consisting of 95% lead and 5% boron, and to add aluminum to this composite in the form of a spiral roll-like structure as a heat conductor. This preserves the external geometric parameters and prevents radiation from being channeled through the aluminum. The use of this new type of protection reduces the total weight of the thermal shield by 4.6 tons and bring the dose load level closer to the maximum permissible level or even reduce it by more than half. It is shown that when containers with pressed solid radioactive waste (PSRW) are installed in rows along the perimeter of a light-type storage facility (LTSF), it is not necessary to construct a radiation protection wall. It is proved that radiation safety standards for category B workers are met behind the disciplinary fence. Criteria are formulated for selecting containers containing PSRW for placement on the perimeter of the LTFS. Product Description popup.authors Kovtun Volodymyr Ye. Zuiok Valerii A. Mykola O. Azarienkov Lazurik Valentine Timofeevich Berezhnoy Yuri Anatolievich Prokhorets Svitlana Ivanivna Sereda Kostyantyn M. Dudina Nataliia H. Ivan I. Okseniuk Hakh Andrii H. Halyna V. Makhnenko Lazuryk Valentyna M. Popenko Nataliia V. Svitlana V. Alokhina Svitlana Viktorivna Yehor V. Rudychev Yehor Volodymyrovych Anna V. Kalashnyk Anna Viacheslavivna popup.nrat_date 2026-03-09 Close