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Information × Registration Number 0222U005460, (0121U108949) , R & D reports Title Research to substantiate the use of nuclear fuel cycles for reactors that are considered in the structure of nuclear energy of Ukraine popup.stage_title Обґрунтування теплофізичної надійності зберігання палива компанії Вестінгауз в ССВЯП ВП ЗАЕС. Розробка, створення і впровадження стандартних зразків підприємства уранвміщуючих матеріалів в широкому діапазоні концентрацій ізотопів урану, основних і домішкових елементів та дослідження їх характеристик ядерно-фізичними методами. Head Krasnorutskyi Volodymyr S., Кандидат фізико-математичних наук Registration Date 30-12-2022 Organization National Science Center "Kharkiv Institute of Physics and Technology" popup.description1 Complex problems of development of nuclear technologies and nuclear energy include a number of specific physical and materials science tasks in substantiation of operation of existing elements of nuclear installations, design and technological developments of perspective elements of active zones, experimental and computational developments on designing active zones with improved fuel cycles. neutron-physical and economic indicators and justification of their application for of reactors of Ukraine, substantiation of thermophysical reliability of Westinghouse fuel storage in SSVYAP VP ZNPP, development of reactor models, in-hull devices (VKP) and the active zone WWER-1000 to perform calculations of the fluence of fast neutrons on VKP reactor vessel and energy release in VKP, conducting research for the active zone of a small modular reactor, research and testing to study processes and phenomena occurring in materials at design and design accidents. popup.description2 The paper analyzes the temperature characteristics of WWER-WR fuel rods/fuel claddings and the most critical structural elements of BSC, PC and VSC during storage in the DSFSF under conditions of NEE and NE. It is shown that in normal operation and in modes of deviations from normal conditions, the DSFSF system with WWER-WR remains within the temperature limits provided by the design. The maximum cladding temperature of the WWR fuel rod cladding in normal operation modes in the DSFSF system does not exceed 350 ºС. Despite the conservatism in the calculation of the SFA temperature condition, there is a margin for the maximum cladding temperature of the WWER-WR fuel assemblies, which, if necessary, can be used to increase the residual power of the fuel assemblies to be loaded and reduce their spent fuel assembly holding time in the spent fuel assemblies. The optimal geometric parameters of SFAs made of uranium-containing materials in different physical forms were evaluated for manufacturing working reference samples on their basis. The design of a container for packaging reference samples of uranium-containing materials was determined and design documentation for containers for packaging working reference samples was developed. Uranium dioxide-based SFPs were produced by mechanical mixing of powders with enrichment of 235U 0.4 and 19.7 %. The methodology for measuring the elemental composition of the experimental batch of uranium dioxide fuel pellets for the experimental fuel assembly TVZ-X, which was designed to be compatible and to replace the TVZ VVR-M2 in the nuclear facility "Electron Accelerator Controlled Neutron Source", was tested. Product Description popup.authors Sleptsov Oleksiy M. Igor Chernov Kushtym Anton V. Gann Volodymyr V. Volodymyr O. Vysotskyi Valerii A. Zuiok Krasnorutskyi Volodymyr S Mykola V. Pasko Olha S. Kirsanova Leleko Yuriy Ya Volodymyr Z. Baidulin Vitalii P. Chernukha Kolotilov Oleksandr M Fedor A. Pasenov Serhii P. Svyrydenko Volodymyr M. Yevseiev Volodymyr V. Vorozhko Mykhailo V. Mukhin Serhii V. Pushkin Volodymyr O. Puzik Mykola O. Lavrentiev Yuliia O. Hordiienko Ryabchikov Sergiy D Vadym V. Hrudnytskyi Yana O. Kushtym Grytsyna Viktor M. Riedkina Ganna P. Valerii A. Dolhii Chunosov Vitaliy O. Maryokhin Sergiy V. Oleh I. Hamov Kostromin Andriy S. Olena O. Slabospytska Volodymyr V. Zihunov Oleksandr I. Zhukov Moskvitina Yuliya K Serhii P. Klymenko Serhii A. Soldatov Kulish Gregory V Roman O. Rud Natalia V. Rud Tretyakov Mikhail V Ihor V. Shevchenko Anatolii K. Semenov popup.nrat_date 2022-12-30 Close
R & D report
Head: Krasnorutskyi Volodymyr S.. Research to substantiate the use of nuclear fuel cycles for reactors that are considered in the structure of nuclear energy of Ukraine. (popup.stage: ). National Science Center "Kharkiv Institute of Physics and Technology". № 0222U005460
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