Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor

M. V. Shchurovskaya, V. P. Alferov, N. I. Geraskin, A. I. Radaev, A. G. Naymushin, Yu B. Chertkov, M. N. Anikin, I. I. Lebedev

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5 Citations (Scopus)

Abstract

This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at the National Research Nuclear University MEPhI and the IRT-T reactor at the National Research Tomsk Polytechnic University. Calculations were performed using the continuous energy Monte Carlo code MCU-PTR. Full 3-D models for the IRT MEPhI and IRT-T reactors were developed. Measured critical cases during the control rod calibrations are analyzed in benchmarking studies. A procedure for the comparison of the measured and the calculated control rod worth based on the detailed calibration simulation is proposed.

Original languageEnglish
Pages (from-to)332-343
Number of pages12
JournalAnnals of Nuclear Energy
Volume96
DOIs
Publication statusPublished - 1 Oct 2016

Keywords

  • Control rods calibration
  • MCU-PTR code
  • Monte Carlo code
  • Research reactor
  • Validation of neutronics codes

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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    Shchurovskaya, M. V., Alferov, V. P., Geraskin, N. I., Radaev, A. I., Naymushin, A. G., Chertkov, Y. B., Anikin, M. N., & Lebedev, I. I. (2016). Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor. Annals of Nuclear Energy, 96, 332-343. https://doi.org/10.1016/j.anucene.2016.06.015