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Information × Registration Number 0217U006302, 0116U007187 , R & D reports Title In materials research and study estimated the use of structural, neutron-absorbing material in nuclear and advanced nuclear fuel cycle, Ukraine popup.stage_title Head Krasnorutskyy Volodymyr Semenovich, Кандидат фізико-математичних наук Registration Date 16-03-2017 Organization National Science Center "Kharkiv Institute of Physics and Technology popup.description2 The synthesis of dysprosium titanate and dysprosium hafnate when sintering pellets at temperatures 1250 ... 1650 °C was researched. It was established that the synthesis is the formation and decomposition of low-temperature and intermediate modifications of dysprosium titanate solid solutions and intermediate solid solutions of dysprosium hafnate. In such a case composite compound (e.g. the ratio of the initial oxides - TiO2 and Dy2O3) significantly influence on the phase formation and quantitative content of different phases in the synthesized material; - There were established the main directions of improving the performance and quality of nuclear fuel pellets made of uranium dioxide for power plants, which is based on the modification of the microstructure of fuel pellets UO2 to increase grain size and porosity structure optimization (increase of density of UO2 pellets to 97% of the theoretical and reduction of open porosity). Patent search and analysis of technology concepts of the largest producers of nuclear fuel (Open Joint Stock Company "TVEL", Russian Federation, Westinghouse, Areva), ways of injection and the quantity of doping microadditives that activate grain growth during sintering of fuel pellets were carried out; - The model of selection gaseous fission products (GFP) in UO2 fuel depending on the grain size was considered; - Also there were established the main directions of improving the dispersion characteristics of nuclear fuel for research reactors. The technological process of manufacturing fuel based on uranium dioxide in an aluminum matrix of rod type fuel rods was developed. The main characteristics of working efficiency of dispersion type fuel (quantity fraction of matrix that is damaged by fission products depending on the size of fuel particles) and temperature conditions of fuel performance in the experimental nuclear facilities during normal operation (subcritical assembly (SCA), Kharkiv, reactor WWR-M , Kyiv) were estimated. Product Description popup.authors Євсеєв В.М. Іванцова Н.І. Іщенко Н.І. Абдулаєв А.М.о Антонова Г.І. Бєлік В.М. Бєлаш М.М. Байдулін В.З. Большак О.І. Борисенко Л.Г. Валежний Є.Б Висоцький В.О. Ворожко В.В. Гамов О.І. Ганн В.В. Грицина В.М. Гулько В.М. Гущін В.А. Джамірзоєв А.Д. Дикий І.В. Долгий В.А. Жуков О.І. Зігунов В.В. Зеленська Н.А. Зуйок В.А. Кірсанова О.С. Клименко С.П. Козіонов С.А. Колотилов О.М. Корнєєва В.В. Костромін А.С. Красноруцький Володимир Семенович Кривошея С.О. Кузовлева Л.В. Куліш Г.В. Кулик Б.О. Куштим А.В. Куштим Я.О. Лаврентьєв М.О. Лелеко Ю.Я. Марьохін С.В. Марьохіна О.П. Матющенко Р.В. МухінМ.В. Пасенов Ф.А. Пасько М.В. Петельгузов І.А. Пузік В.О. Пушкін С.В. Рєдкіна Г.П. Рудь Н.В. Рудь Р.О. Рябчиков С.Д. Свириденко С.П. Семенов А.К. Семенов М.А. Слєпцов О. М. Слєпцов С.М. Слабоспицька О.О. Солдатов С.А. Степаненко О.М. Татарінов В.Р. Трет'яков М.В. Федченко І.В. Черницький С.В. Чернов І.О. Чернуха В.П. Черняєва Т.П. Чуносов В.О. Шемет Т.О. popup.nrat_date 2020-04-02 Close