A criticality analysis of two spent fuel storage pools for Etrr_1 and Etrr_2 research reactors was performed. The multiplication factor for the pools was calculated as a function of relevant lattice physics parameters. Monte Carlo code MCNP-4A code was used in the criticality calculations. The results were compared with those given by CITATION code and the results obtained formerly during the design phase of the pools [9] with the MONK 6.3 code. Safety of the pools was confirmed.
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