دراسة نترونية لعملية تحويل المفاعل المرجعي IAEA MTR 10 MW من الوقود عالي الإغناء باليورانيوم إلى الوقود منخفض الإغناء

Abstract EN

In this research work a neutronic design for the IAEA MTR 10 MW research reactor was developed using the MTRMC code, in view of the conversion process from the use of Highly Enriched Uranium fuel (HEU) to the use of Low Enriched Uranium fuel (LEU).

The effective multiplication factor, the neutron flux for the three energy groups (fast, epithermal, thermal), and the power distribution for a standard core with fresh fuel for the 2 percentage of enrichment.

The results of the present work are compared with previously published results.

The results of this work show a good agreement with published results in the International Atomic Energy Agency report, IAEA-TECDOC-233, as the effective multiplication factor calculated value was (1.20720) for the fuel with enrichment of 93 %, and (1.16152) for the fuel with enrichment of 20 %, while the maximum value of the thermal neutronic flux was (3.058E+14) for the fuel with high enrichment, and (2.7988E+14) for the fuel with low enrichment, with relative difference smaller than 8 %