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This paper is dealing with the reactor parameter determination experiments performed at the light water subcritical reactor (LWSCR) in Esfahan. The parameter determination methods are derived from a theory based on neutron source position. The LWSCR reactor system is modeled by Monte Carlo calculations (MCNP4C), WIMSD5B and CITATION, and the criticality safety and neutron flux distribution problems are presented and analyzed. The analysis of the multiplication factors obtained by MCNP4C are in fairly good agreement with the results obtained by WIMSD5B and CITATION. For the flux distribution calculations, the MCNP4C results differ from the experimental observations by less than 12% and by ~5% for the WIMSD5B and CITATION.