الفهرس 
Neutronics and shielding calculations for power upgrading of research reactor using low enriched uranium (LEU) fuel
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Abstract
The main objective of this work is to study the upgrade of a research reactor type WWR-S by increasing its power from 2 MW to 5 MW, using EK-10 fuel type with enrichment 10%, then also up to 10 MW with fuel type (IRT- 4m) of 19.75% enrichment, eventually, the thermal neutron flux increases. All neutronic parameters were studied using the computer codes such as WIMS-D5 for cell calculations, CITTATION, and CITVAP for the core of the reactor. The comparison with the available experimental data shows a good agreement with the calculated results at the same experimental conditions which set the confidence of the performed calculations. The thermal neutron flux at power 2 MW was 2x10¹³ (n/cm².s) at the center of active core and 1.8x10¹³ (n/cm².s) at the peripheries, after upgrade to power 5 MW the values raised to 4.5 x 10¹³ (n/cm².s) in the center of active core and 7 x 10¹³ (n/cm².s) at the peripheries, while the control rod is up, and the irradiation channels are closed. For the upgrading to 10 MW the value of the thermal neutron flux at the active core is 3.8 x 10¹⁴ (n/cm².s) at the center and 1 x 10¹⁴ (n/cm².s) at the peripheries. The design of a nuclear reactor core requires basic thermal-hydraulic information concerning the heat transfer regime to maintain safe performance of the reactor through the upgrading process