Features of fuel burnup calculations for IRT-T reactor using MCU-PTR code

A. Naymushin, M. Anikin, I. Lebedev, A. Busygin, S. Dmitriev, D. Zolotykh

Research output: Contribution to journalArticlepeer-review

2 Citations (Scopus)


The article considers computation methods of the kinetics of changes of fuel nuclide composition vs. fuel burnup. Calculations were carried out at different intervals of operating time at a constant level of power of the IRT-T research reactor for different types of fuel assemblies. The analysis of the reaction rate of absorption for the isotopes included in the fuel composition is given. It is shown that the use of piecewise linear interpolation is the most preflerred in order to calculate the long fuel campaigns as there is a high convergence of calculation data.

Original languageEnglish
Pages (from-to)449-452
Number of pages4
JournalJournal of Industrial Pollution Control
Issue number2
Publication statusPublished - 2016


  • Burnup
  • Fuel nuclide composition
  • IRT-T reactor
  • Isotopes
  • Neutron

ASJC Scopus subject areas

  • Water Science and Technology
  • Ocean Engineering
  • Pollution
  • Fluid Flow and Transfer Processes
  • Atmospheric Science

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