Thermal analysis of IRT-T reactor fuel elements

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

Research output: Contribution to journalConference article

1 Citation (Scopus)

Abstract

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.

Original languageEnglish
Article number012002
JournalIOP Conference Series: Materials Science and Engineering
Volume93
Issue number1
DOIs
Publication statusPublished - 13 Oct 2015
Event21st International Conference for Students and Young Scientists: Modern Technique and Technologies, MTT 2015 - Tomsk, Russian Federation
Duration: 5 Oct 20159 Oct 2015

ASJC Scopus subject areas

  • Materials Science(all)
  • Engineering(all)

Fingerprint Dive into the research topics of 'Thermal analysis of IRT-T reactor fuel elements'. Together they form a unique fingerprint.

  • Cite this