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Information × Registration Number 0224U033163, (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 Розробка перспективних 12-18 місячних паливних циклів для АЕС України. Дослідження впливу високотемпературних перегрівів та циклічних змін температури на характеристики сплаву 42ХНМ і зварних з’єднань у виробах з нього для обґрунтування використання в якості конструкційного матеріалу для толерантного палива енергетичних реакторів. Head Krasnorutskyi Volodymyr S., Кандидат фізико-математичних наук Registration Date 19-12-2024 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 This study develops an advanced 12-month fuel cycle and compares it with the traditional cycles. The calculations show that the advanced fuel cycle uses an average of 1.25 fuel assemblies less than traditional cycles, and the fuel assemblies reach a higher burnup. An advanced fuel cycle was also developed with a lifetime of 490.8 effective days, which, taking into account the reloading time, makes up almost 18 months. The developed advanced fuel cycle meets the criteria for the peaking factor and reactivity coefficient and will be proposed to JSC NNEGC Energoatom for implementation. An analysis of the design basis accidents progression for VVER-1000 reactor with first circuit depressurization was performed. It was shown that under all design basis conditions, decreasing the coolant flow rate through the core initiates departure from nucleate boiling and fuel rod cladding temperature growth. It was found that the maximum fuel rod cladding temperature is 1078 °C in the event of a MCP rupture. Investigations of the dummy fuel rods were carried out. Mechanical tests of the 42ХНМ alloy dummy fuel rods after a short-term heating in a water vapor environment to a temperature of 1000...1200 °C were conducted. It was shown that the 42ХНМ cladding strength limit is in the range of 748-823 МPа (1008-1108 kgf), and the relative elongation is 48-54%. Fracture occurs in the middle area of the fuel rod cladding, which confirms reliability and integrity of the welds made using the electric arc welding operating modes. The lowest fracture force was observed in the fuel rod dummy tested at 1200 °C in water vapor. The paper presents the results of investigations of the corrosion rate of alternative materials for tolerant fuel cladding of austenitic stainless steel grade X18H10T and chromium-nickel alloy 42ХНМ in the water vapor environment produced by OSCAR PG LTD (Nikopol). It was shown that 42ХНМ alloy could be used for fuel rod cladding as an alternative to zirconium alloys. Product Description popup.authors Yevseiev Volodymyr M. Baidulin Volodymyr Z. Bondarenko Serhii L. Vysotskyi Volodymyr O. Vorozhko Volodymyr V. Hamov Oleh I. Hann Volodymyr V. Hordiienko Yuliia O. Hrytsyna Viktor M. Hrudnytskyi Vadym V. Dzhamirzoiev Albert D. Dykyi Іvan V. Dolhii Valerii A. Zhukov Oleksandr I. Zihunov Volodymyr V. Zorchenko Olena S. Zuiok Valerii A. Kirsanova Olha S. Kisil Mykhailo V. Kantemirov Andrii V. Klymenko Serhii P. Krasnorutskyi Volodymyr S. Kushtym Anton V. Kushtym Yana O. Lavrentiev Mykola O. Lehenkyi Yehor S. Mukhin Mykhailo V. Pasenov Fedor A. Pasko Mykola V. Pylypenko Oleksandr V. Prokhorenko Yurii P. Puzik Volodymyr O. Pushkin Serhii V. Riedkina Hanna Р. Romankov Viktor O. Rud Nataliia V. Rud Roman O. Svyrydenko Serhii P. Semenov Anatolii K. Semenov Maksym A. Slabospytska Olena O. Soldatov Serhii A. Starolat Mariia V. Tretiakov Mykhailo V. Chernov Ihor O. Chernukha Vitalii P. Shevchenko Ihor V. popup.nrat_date 2024-12-19 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: Розробка перспективних 12-18 місячних паливних циклів для АЕС України. Дослідження впливу високотемпературних перегрівів та циклічних змін температури на характеристики сплаву 42ХНМ і зварних з’єднань у виробах з нього для обґрунтування використання в якості конструкційного матеріалу для толерантного палива енергетичних реакторів.). National Science Center "Kharkiv Institute of Physics and Technology". № 0224U033163
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Updated: 2026-03-22