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Registration Number

0225U001262, (0124U000451) , R & D reports

Title

Improvement of heat-dissipating properties and neutron-absorbing elements of active zones of nuclear power plant reactors for of domestic nuclear technologies during the post-war modernization and development of Ukraine's nuclear power industry.

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Визначення впливу властивостей конструкційних ядерних матеріалів твелів і пелів на ефективність, надійність і безпеку роботи реакторів АЕС та аналіз впливу зовнішніх чинників на ці властивості.

Head

Yefimov Oleksandr V., д.т.н.

Registration Date

28-01-2025

Organization

National Technical University "Kharkiv Polytechnic Institute"

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The goal of the project is to improve, based on the use of interval and polynomial regression models for processing of experimental data, physico-mechanical and physico-chemical properties of fuels and pellets, their assemblies and clusters of active zones of nuclear reactors of NPPs using thermal neutrons with water under pressure, from the indicators of which directly depends on the nuclear and radiation safety of the NPP under the conditions of normal operation and under the conditions of design and pre-design accidents with the loss of the coolant of the first circuit of the LOCA or SBO type, which can lead to melting of the active zone of the reactor.

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 Scientific research on the first stage topic M3022 aimed at determining the influence of the properties of structural nuclear materials such as fuel rods and pellets on the efficiency, reliability, and safety of NPP reactors and analyzing the impact of external factors on these properties. The object of research is the fuel elements (fuel rods) and their assemblies and neutron-absorbing elements (pellets) of the control bodies of the active zones of thermal neutron nuclear reactors with pressurized water of double-circuit nuclear power plants with a campaign length of 6-7 years and the physicochemical processes occurring in them during operation. The subject of research is the physicomechanical and physicochemical properties (impact strength, hardness, microhardness, corrosion resistance, radiation resistance, heat resistance, resource characteristics) of zirconium fuel cladding, fuel assembly components and hafnium neutron-absorbing rods (pellets) and their clusters of domestic post-war production in cooperation with the Westinghouse concern based on Ukrainian nuclear technologies for the cores of VVER reactors (PWR) with a campaign length of 6-7 years, as well as mathematical models built using interval regression analysis methods used to assess and optimize these properties. The purpose of the fundamental research work is to improve, based on the use of interval and polynomial regression models for processing of experimental data, physico-mechanical and physico-chemical properties of fuels and pellets, their assemblies and clusters of active zones of nuclear reactors of NPPs using thermal neutrons with water under pressure, from the indicators of which directly depends on the nuclear and radiation safety of the NPP under the conditions of normal operation and under the conditions of design and pre-design accidents with the loss of the coolant of the first circuit of the LOCA or SBO type, which can lead to melting of the active zone of the reactor.

Product Description

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Harkusha Tetiana A.
Zhydetskyi Olekcandr I.
Lifshyts Petro V.
Pylypenko Mykola M.
Potanina Tetiana V.
Sydorkin Ihor D.
Khavin Henadii L.
Chyzhyk Oleksandr V.

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2025-01-28