Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method

Accelerator Driven Subcritical Reactor (ADSR), offer advantages in terms of flexibility in using exotic fuels, allowing operation with reactivity variations and in term of intrinsic safety. Neutronic parameters of a modeled ADSR has been investigated using MCNPX 2.6 computational method. According to the obtained data, a neutron flux of ~ 10
¹⁴
(n/s.cm
²
) is suitable for minor actinide incineration. The system can efficiently burn minor actinide with a ~10
¹⁷
atom/s rate and produce power in the fission region with good fission per absorption ratio of 0.863.