Thermo-Physical Properties of Dispersion Nuclear Fuel for a New-Generation Reactors: A Computational Approach; AIP Conference Proceedings; Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018)

Thermo-Physical Properties of Dispersion Nuclear Fuel for a New-Generation Reactors: A Computational Approach; AIP Conference Proceedings; Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018)

Detalhes bibliográficos
Parent link:AIP Conference Proceedings
Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018).— 2019.— [020002, 7 p.]
Corporate Authors: Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла, Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Лаборатория плазменных гибридных систем, Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Научная лаборатория изотопного анализа и технологий
Outros Autores: Bedenko S. V. Sergey Vladimirovich, Karengin A. G. Aleksander Grigorievich, Nima Ghal-Eh, Alekseev N. Nikita, Knyshev V. V. Vladimir Vladimirovich, Shamanin I. V. Igor Vladimirovich
Resumo:Title screen
Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O[2] of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O[2] and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.
Режим доступа: по договору с организацией-держателем ресурса
Idioma:inglês
Publicado em: 2019
Assuntos:
электронный ресурс
труды учёных ТПУ
теплофизические свойства
ядерное топливо
дисперсионное топливо
реакторы
инновационные системы
теплопроводность
топливные таблетки
ториевые реакторы
облучение
Acesso em linha:https://doi.org/10.1063/1.5099594
Formato: Recurso Electrónico Capítulo de Livro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=660276
Descrição
Resumo:Title screen
Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O[2] of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O[2] and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.1063/1.5099594

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