Abstract
Abstract The CB6 benchmark on VVER-440 final disposal consists of two parts. The decay calculation part is aimed at determination of isotopic composition of irradiated fuel material over the time scale relevant to long-term spent fuel disposal. The second part involves calculation of keff values in a 3D cask configuration at various time points. In this study, the code Serpent is applied in solution of the benchmark. Serpent is a continuous energy Monte Carlo reactor physics code developed at VTT Technical Research Center of Finland. The decay calculation part of the benchmark is, in addition to Serpent, also carried out using point-depletion calculation code ORIGEN. This enables comparison of the results obtained using the two codes exploiting two different methods in solution of the decay equations. The paper demonstrates the decay and keff calculation results as determined in the benchmark specification. The differences in results arising between the two calculation codes in decay calculation, and between the ENDF/B-VII and JEFF-3.1.1 based cross section libraries in keff calculation, are depicted and discussed.
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