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The exact calculation of point kinetic parameters is very important in nuclear reactor safety assessment, and most sophisticated safety codes such as RELAP5, PARCS, DYN3D, and PARET are using these parameters in their dynamic models. These parameters include effective delayed neutron fractions as well as mean generation time. These parameters are adjoint-weighted, and adjoint flux is employed as a weighting function in their evaluation. Adjoint flux calculation is an easy task for most of deter-ministic codes, but its evaluation is cumbersome for Monte Carlo codes. However, in recent years, some sophisticated techniques have been proposed for Monte Carlo-based point kinetic parameters calculation without any need of adjoint flux. The most straightforward scheme is known as the "prompt method" and has been used widely in litera-ture. The main objective of this article is dedicated to point kinetic parameters calculation in Tehran research reactor (TRR) using deterministic as well as probabilistic tech-niques. WIMS-D5B and CITATION codes have been used in deterministic calculation of forward and adjoint fluxes in the TRR core. On the other hand, the MCNP Monte Carlo code has been employed in the "prompt method" scheme for effective delayed neutron fraction evaluation. Deterministic results have been cross-checked with prob-abilistic ones and validated with SAR and experimental data. In comparison with experimental results, the relative differences of deterministic as well as probabilistic meth-ods are 7.6 and 3.2％, respectively. These quantities are 10.7 and 6.4％, respectively, in comparison with SAR report.