The study deals with the neutronic analysis of the reference core and six reconfigured cores (C-1 to C-6) of the existing BAEC (Bangladesh Atomic Energy Commission) TRIGA Research Reactor using MCNP. The developed reference core model was validated by benchmarking the neutronic parameters with the experimental, calculation and Safety Analysis Report (SAR). The reconfigured cores were developed by considering three factors: (i) sub-criticality, (ii) symmetrical geometry, and (iii) substitution between fuel and graphite dummy element. Under room temperature conditions global, local and the kinetic parameters were calculated for the reconfigured cores and compared with the reference core. Cores burnup simulations were carried out up to 1200 MWD to investigate fuel depletion, flux trend, and activity accumulation. Based on neutronic performance, the results show that the reconfigured cores C-1 and C-3 are more qualified than the reference core and, in some cases; C-3 represents a better performance than the core C-1.