2012, Vol.15, No.3, pp.305-308
Influence of metal shells and size of cells in a fuel storage pool on the value of the effective neutron multiplication factor was studied. Monte Carlo code MCU-FREE was used in the criticality calculations. A criticality analysis of spent fuel storage pools for different degrees of packing of cells in the rack was performed.
Key words:
criticality calculations, safety analysis, pool storage,
Monte Carlo simulation
Full text: Acrobat PDF (217KB)
Copyright © Nonlinear Phenomena in Complex Systems. Last updated: December 5, 2012