محاكاة حجب النترونات لخرسانة بناء مستخدمة في المنطقة الوسطى من سورية

الملخص EN

The MCNP-5BETA code was used to simulate the neutron shielding characteristics of the concrete, as building material, used in the Central Region of Syria.

The simulation is done for all the experimental conditions from source to dosimeter up to the laboratory .The calculated doses were found to have between 0.008% and 8% relative differences with respect to the experimentally determined values.

Since these differences are universally acceptable the MCNP-5BETA code could be used to estimate the shielding characteristics against neutrons for these concrete by adding absorption or moderation materials to it.

The same could be also valid for new concretes which experimental shielding characteristics against neutrons were not experimentally measured