Criticality calculations of the effective multiplication factor (K eff) were executed for each of the twelve cases results show a reasonable agreement with published benchmark values for both reactors. Neutronics calculations were performed for fresh fuel, the beginning of life cycle (BOL) and end of life cycle (EOL) for each of the three enrichments for both the IAEA 10 MW generic reactor and core 1/98 of the ETRR-2 reactor. A 3D full core model with three uranium enrichment of 93%, 45%, and 20% was constructed utilizing the OpenMC particle transport Monte Carlo code. This study investigates the neutron flux in the central experimental facility of two material test reactors (MTR), the IAEA generic10 MW benchmark reactor and the 22 MW s Egyptian Test and Research Reactor (ETRR-2). Preserving the reactor capability to produce the needed flux to perform its intended research functions, determines the conversion feasibility. However, fuel conversion from highly enriched uranium (HEU) to low enriched uranium (LEU) driven by the ongoing effort to diminish proliferation risk, will impact reactor physics parameters. Research reactors in-core experimental facilities are designed to provide the highest steady state flux for user's irradiation requirements.
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