“…Many traditionally developed neutron-transport codes are export-controlled (e.g. MCNP (Rising et al, 2023), Shift (Hamilton & Evans, 2019), and MCATK (Adams et al, 2015)) and some are known to be difficult to install, use, and develop in. MC/DC is open-source, and thus, similar to other open-source Monte Carlo neutron-transport codes (e.g., OpenMC (Romano et al, 2015)), it promotes knowledge sharing, collaboration, and inclusive, community-driven development.…”