Alpha-Eigenvalue Monte Carlo neutron transport calculations with SCONE

The work aims at adding approximate time-dependent asymptotic criticality simulation capabilities to SCONE - a framework for carrying out particle transport Monte Carlo calculations - through a fundamental α-eigenvalue solver for arbitrary geometries, materials, and boundary conditions. Making use of recent developments, the implementation comes in the form of an α-k source iteration scheme in which neutrons are transported from release to termination in a series of generations. The scheme includes, inter alia, new mechanics for neutron tracking and collision processing (both analog and implicit) along with a physical update procedure for estimating α. Several test cases were examined to assess different aspects of the implemented scheme proving performance and agreement with benchmarks. (authors)