Testing the new stochastic neutronic code ANET in simulating safety important parameters
Annals of Nuclear Energy(2017)
Abstract
•ANET is a new neutronics stochastic code.•Criticality calculations in both subcritical and critical nuclear systems of conventional design were conducted.•Simulations of thermal, lower epithermal and fast neutron fluence rates were performed.•Axial fission rate distributions in standard and MOX fuel pins were computed.
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Key words
Monte Carlo,Neutronics analysis,Code validation
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