Moustafa Aziz1, Krzysztof Andrzejewski2
1 Nuclear Safety Centre, 3 Ahmed Alzomer Str., Nasr City, Cairo, Egypt,
2 Institute of Atomic Energy, Nuclear Safety Analysis Group, 05-400 Otwock-Świerk, Poland
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 with the MONK 6.3 code. Safety of the pools was confirmed.