Thermal analysis of IRT-T reactor fuel elements

Detalles Bibliográficos
Parent link:IOP Conference Series: Materials Science and Engineering
Vol. 93: Modern Technique and Technologies (MTT'2015).— 2015.— [012002, 5 p.]
Autor Corporativo: Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра физико-энергетических установок (№ 21) (ФЭУ)
Otros Autores: Naymushin A. G. Artem Georgievich, Chertkov Yu. B. Yuri Borisovich, Lebedev I. I. Ivan Igorevich, Anikin M. N. Mikhail Nikolaevich
Sumario:Title screen
The article describes the method and results of thermo-physical calculations of IRT-T reactor core. Heat fluxes, temperatures of cladding, fuel meat and coolant were calculated for height of core, azimuth directions of FA and each fuel elements in FA. Average calculated values of uniformity factor of energy release distribution for height of fuel assemblies were shown in this research. Onset nucleate boiling temperature and ONB-ratio were calculated. Shows that temperature regimes of fuel elements at rated power of the reactor keep within limit values and meet safety requirements. Obtained results could be applied at feasibility study of increasing thermal power of IRT-T research reactor to 12 MW level.
Режим доступа: по договору с организацией-держателем ресурса
Publicado: 2015
Colección:Power industry
Materias:
Acceso en línea:http://dx.doi.org/10.1088/1757-899X/93/1/012002
http://earchive.tpu.ru/handle/11683/19996
Formato: Electrónico Capítulo de libro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=644504
Descripción
Sumario:Title screen
The article describes the method and results of thermo-physical calculations of IRT-T reactor core. Heat fluxes, temperatures of cladding, fuel meat and coolant were calculated for height of core, azimuth directions of FA and each fuel elements in FA. Average calculated values of uniformity factor of energy release distribution for height of fuel assemblies were shown in this research. Onset nucleate boiling temperature and ONB-ratio were calculated. Shows that temperature regimes of fuel elements at rated power of the reactor keep within limit values and meet safety requirements. Obtained results could be applied at feasibility study of increasing thermal power of IRT-T research reactor to 12 MW level.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.1088/1757-899X/93/1/012002