Search academic texts

Information × Registration Number 0225U000207, (0123U100211) , R & D reports Title Development of the scientific and technical foundations of modern systems for diagnosing neutron-physical, thermo-hydraulic, and vibration parameters of heat-dissipating assemblies and internal devices when new types of nuclear fuel are introduced in reactor installations from VVER at NPPs of Ukraine during the over design terms of their operation popup.stage_title Розробка науково-технічних основ сучасних систем діагностики нейтронно-фізичних, теплогідравлічних і вібраційних параметрів тепловидільних збірок і внутрішньокорпусних пристроїв Head Borysenko Volodymyr I., Доктор технічних наук Registration Date 07-01-2025 Organization Institute for Safety Problems of Nuclear Power Plants of the National Academy of Sciences of Ukraine popup.description1 Development of the scientific and technical basis of modern diagnostic systems of important safety parameters of VVER power units during their operation in over design terms popup.description2 The object of the study is neutron-physical, thermal-hydraulic and vibrational processes in the VVER-1000 reactor plant. The purpose of the work is to develop scientific and technical foundations of modern systems for diagnosing neutron-physical, thermal-hydraulic and vibrational parameters of fuel assemblies (FA) and internal fuel assemblies (IFA) during the introduction of new types of nuclear fuel in reactor plants (RP) with VVER at Ukrainian NPPs during their beyond-design life. Research methods are determining the safety parameters of nuclear plants based on the use of modern computational codes for modeling neutron-physical, thermal-hydraulic and vibrational processes in nuclear plants. Research results - there are presented results of: research on determining the neutron-physical, thermal-hydraulic and vibrational parameters of fuel assemblies of VVER reactors, as well as the radiation characteristics of irradiated nuclear fuel of nuclear facilities, including spent nuclear fuel repositories. Recommendations for using the results of the work - the results of the research are planned for implementation - when developing the applied software of the Internal Reactor Control System (IRCS-M2) VVER-1000 in the part of developing algorithms and programs for determining the parameters of nuclear fuel burnup to determine its radiation characteristics. Field of application - nuclear facilities: power VVER-440, VVER-1000, research nuclear reactor VVR-M, subcritical assembly "Neutron Source", spent nuclear fuel repositories. Conclusions - the development and implementation in the practice of operating nuclear facilities of modern methods for studying the safety parameters of nuclear facilities: neutron-physical, thermal-hydraulic and vibrational, which relate to fundamental safety tasks, are relevant and work in this direction will be continued. Product Description popup.authors Horanchuk Vadym V. Khvalin Denys I. Sharaievskyi Ihor H. Sharaievskyi Heorhii I. Yurov Maksym S. popup.nrat_date 2025-01-07 Close