Neutronic analysis for Tehran Research Reactor mixed-core

In this research, neutronic calculation of current low enriched uranium control fuel elements replacement with high enriched uranium control fuel elements in the reference core of Tehran Research Reactor (TRR) has been investigated and the results of calculations are compared with the TRR neutronic safety criteria. Results show that all neutronic parameters of the reference and each mixed-core are lower than the safety criteria. Nuclear reactor analysis codes including MTR_PC package and MCNP5 were employed to carry out these calculations.

► Neutronic analysis of Tehran Research Reactor mixed-core has been done.
► Replacement of LEU–CFE with HEU–CFE in the TRR core has been investigated.
► Results of each mixed-core were compared to the reference core and safety criteria.
► All neutronic parameters of each mixed-core are lower than the safety criteria.