M. Aziz et K. Andrzejewski, Criticality calculations for the spent fuel storage pools for Etrr_1 and Etrr_2 reactors, NUKLEONIKA, 45(2), 2000, pp. 141-144
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 resul
ts 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.