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.
- Control rods calibration
- MCU-PTR code
- Monte Carlo code
- Research reactor
- Validation of neutronics codes
ASJC Scopus subject areas
- Nuclear Energy and Engineering