DETERMINATION OF NEUTRONIC PARAMETERS OF RTP CORE USING MCNP CODE
The 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency achieved initial criticality on June 28, 1982. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes. This paperdescribes the reactor parameters calculation for the PUSPATI TRIGA REACTOR (RTP); focusing on the application of the developed reactor 3D model for criticality calculation, analysis of power and neutron flux distribution and depletion study of TRIGA fuel. The 3D continuous energy Monte Carlo code MCNP was used to develop a versatile and accurate full model of the TRIGA reactor. The consistency and accuracy of the developed RTP MCNP model was established by comparing calculations to the experimental results and TRIGLAV code.MCNP and TRIGLAV criticality prediction of the critical core loading are in a very good agreement with the experimental results.Power peaking factor calculated with TRIGLAV are systematically higher than the MCNP but the trends are the same.Depletion calculation by both codes show differences especially at high burnup.The results are conservative and can be applied to show the reliability of MCNP code and the model both for design and verification of the reactor core, and future calculation of its neutronic parameters.