Abstract
Different methods of generating homogenized few-group cross sections using continuous energy Monte Carlo codes MCU-PTR and Serpent 2.1.27 for full core diffusion calculation of small-size light water reactor were studied. Few-group cross sections were used in core diffusion nodal simulator TIGRIS for the calculation of the simplified cores with fuel of CROCUS reactor and IRT-type reactor in light water reflector. Special attention is paid to the impact of diffusion coefficients on the results of diffusion calculation. Three different ways of diffusion coefficient generation were compared: usual “out-scatter” approximation, using of the hydrogen transport correction curve and migration area method.
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