Registration Number
0221U107057,
(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
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Розрахунок стаціонарних паливних циклів для ВВЕР-440 з паливом альтернативного постачальника. Матеріалознавчі дослідження в обґрунтування застосування конструкційних матеріалів толерантного палива та нейтроно-фізичні розрахунки основних характеристик твелів легководних енергетичних реакторів з цими матеріалами.
Head
Krasnorutskyi Volodymyr S., Кандидат фізико-математичних наук
Registration Date
26-12-2021
Organization
National Science Center "Kharkiv Institute of Physics and Technology"
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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.
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Calculations of stationary fuel cycles for WWER-440 with fuel from an alternative supplier showed that:
• the design of Westinghouse's fuel assemblies ensures the fulfillment of neutron-physical design criteria;
• stationary fuel loads a.z. WWER-440 (RU B-230) of Units №1 and №2 of RNPP with RK and ARC of Westinghouse meet the requirements of NTD and the main neutron-physical characteristics (duration of the campaign, depth of fuel burnout, unevenness coefficients, etc.) are close to the current fuel cycles ;
• the proposed fuel cycles are not inferior to current fuel cycles in terms of key economic indicators.
The paper studies the materials of the shells of tolerant fuel that can prevent the development of severe accidents at nuclear power plants.
Studies have shown that the corrosion rate of 42HNM alloy is almost 9 times lower than the corrosion rate of austenitic stainless steel grades 06X18H10T and 08X18H10T and coincides with the corrosion rate of zirconium alloy with chrome coating. It is shown that the corrosion of the 42HNM alloy proceeds at a low rate of dissolution of the upper oxide layers, so there will be no excessive load on the primary coolant purification system from activated corrosion products, and will not increase the dose to service personnel. Under conditions of maximum design basis accidents associated with core overheating, the amount of hydrogen released during the oxidation of shells made of 42HNM alloy will be ten times less than that of zirconium alloy. However, to use this alloy as fuel shells in WWER, in order to reduce the parasitic capture of thermal neutrons, it is necessary to perform structural adaptation, one of the steps of which will be to reduce the wall thickness to the limit that will not lose its stability.
Product Description
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Chernov Ihor O.
Valerii A. Zuiok
Olha S. Kirsanova
Leleko Yuriy Ya
Hanna Р. Riedkina
Volodymyr V. Hann
Volodymyr Z. Baidulin
Vitalii P. Chernukha
Kolotilov Oleksandr M
Volodymyr M. Yevseiev
Volodymyr V. Vorozhko
Anton V. Kushtym
Volodymyr S. Krasnorutskyi
Volodymyr O. Puzik
Ryabchikov Sergiy D
Slabospytska Olena O.
Vadym V. Hrudnytskyi
Yana O. Kushtym
Valerii A. Dolhii
Zhukov Oleksandr I.
Grytsyna Viktor M
Maryokhin Sergiy V.
Oleh I. Hamov
Kostromin Andriy S.
Volodymyr V. Zihunov
Sleptsov Oleksii M
Moskvitina Yuliya K
Serhii P. Klymenko
Serhii A. Soldatov
Kulish Gregory V
Roman O. Rud
Natalia V. Rud
Tretyakov Mikhail V
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2022-03-09