حساب معامل التضاعف الفعال و توزع التدفق النتروني و الاستطاعة في مفاعل البحث المصري الثاني 2-ETRR باستخدام الكود MCNP4C2

الملخص EN

The MCNP4C2 Monte Carlo code was used to model the Egyptian Second research reactor in this paper, to calculate the effective multiplication factor keff, distribution of the thermal and fast neutron fluxes and power in reactor core with two type of fuels: standard and mixed.

The values of the keff were 1.21842 and 1.05272, the maximum thermal flux were 2.975x10+14 and 3.352x10+14 n/cm2 s, and the maximum fast flux was 2.950x10+14 and 2.389x10+14 n/cm2 s for standard and mixed fuels respectively.

The results showed good agreements with previous results available in the literature.