Abstract
This paper discusses the capability of the deterministic code system DRAGON-5 and DONJON-5 to reliably simulate the SLOWPOKE-2 research reactor. The characteristics of complex geometry, highly heterogeneity and large leakage of the SLOWPOKE-2 core, poses a challenge for classical neutronics calculation tools and schemes for power reactors. The simulation model is presented (geometry, cross section library, assumption, etc.), and the results obtained by DRAGON-5/DONJON-5 codes and the evaluated nuclear data from WLUP project were compared to the calculations performed with Monte Carlo code MCNP 4A using a detailed geometrical model of the reactor and the experimental data. Criticality calculations have been performed to verify and validate the model based on the multiplication factor comparisons for 4 energy groups with two different leakage models. The results indicate that the DRAGON-5 and DONJON-5 codes system agrees well with the MCNP 4A continuous-energy Monte Carlo simulation and experiment. Since created model properly describes the reactor core it can be used for calculations of reactor core parameters and for optimization of research reactor application.
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