Thermal analysis of IRT-T reactor fuel elements

A. Naymushin, Yu Chertkov, I. Lebedev, M. Anikin

Результат исследований: Материалы для журнала

1 Цитирования (Scopus)

Аннотация

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.

Язык оригиналаАнглийский
Номер статьи012002
ЖурналIOP Conference Series: Materials Science and Engineering
Том93
Номер выпуска1
DOI
СостояниеОпубликовано - 13 окт 2015
Событие21st International Conference for Students and Young Scientists: Modern Technique and Technologies, MTT 2015 - Tomsk, Российская Федерация
Продолжительность: 5 окт 20159 окт 2015

ASJC Scopus subject areas

  • Materials Science(all)
  • Engineering(all)

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