V. F. Tsibulsky scite author profile

The paper presents a description of benchmark cases, achieved results, analysis of possible reasons of differences of calculation results obtained by various neutronic codes. The comparative analysis is presented showing the benchmark–results obtained with reference and design codes by Russian specialists (WIMS-D, JAR-HTGR, UNK, MCU, MCNP5-MONTEBURNS1.0-ORIGEN2.0), by French specialists (APOLLO2, TRIPOLI4 codes), and by Korean specialists (HELIOS, MASTER, MCNP5 codes). The analysis of possible reasons for deviations was carried out, which was aimed at the decrease of uncertainties in calculated characteristics. This additional investigation was conducted with the use of 2D models of a fuel assembly cell and a reactor plane section.

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V. F. Tsibulsky

The Admissibility of the Closed Fuel Cycle of Nuclear Power Engineering

The influence of a non-uniform radial temperature distribution in the fuel on the results of calculation of transients

Acceptability of the Closed Fuel Cycle of Nuclear Power Engineering

Comments to the paper “Computational problems in the calculation of temperature effects for heterogeneous nuclear reactor unit cells” (. Annals of Nuclear Energy 27 (2), 175–183)

Results of Neutronic Benchmark Analysis for a High Temperature Reactor of the GT-MHR Type

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