Thermal analysis of IRT-T reactor fuel elements; IOP Conference Series: Materials Science and Engineering; Vol. 93: Modern Technique and Technologies (MTT'2015)

Xehetasun bibliografikoak
Parent link:IOP Conference Series: Materials Science and Engineering
Vol. 93: Modern Technique and Technologies (MTT'2015).— 2015.— [012002, 5 p.]
Erakunde egilea: Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра физико-энергетических установок (№ 21) (ФЭУ)
Beste egile batzuk: Naymushin A. G. Artem Georgievich, Chertkov Yu. B. Yuri Borisovich, Lebedev I. I. Ivan Igorevich, Anikin M. N. Mikhail Nikolaevich
Gaia: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
Hizkuntza:ingelesa
Argitaratua: 2015
Saila:Power industry
Gaiak:
Sarrera elektronikoa:http://dx.doi.org/10.1088/1757-899X/93/1/012002
http://earchive.tpu.ru/handle/11683/19996
Formatua: Baliabide elektronikoa Liburu kapitulua
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=644504

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330 |a 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. 
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