OpenMC vs StatsBase.jl

OpenMC is a Monte Carlo particle transport code for neutronics and radiation analysis. Since the random ray transport solver landed in 0.15.0 it has received substantial work in every subsequent release, most recently local adjoint sources, temperature and distributed-density feedback, fission-heating tallies and a weight-window bootstrapping workflow. The other consistent thread is shutdown-dose and depletion tooling, where 0.15.3 introduced an R2SManager to automate the rigorous two-step workflow and 0.16.0 extended it with reactivity control, CRAM substeps and multiple meshes.

The project is layering a deterministic-adjacent solver alongside its Monte Carlo core rather than replacing it, and the ratio of random-ray work to core-solver work in each release keeps rising. In parallel it is packaging expert workflows into objects — R2SManager is the clearest case, turning a multi-stage shutdown dose calculation into a class rather than a recipe. The Python API is where most of that packaging surfaces, and it is also where the compatibility breaks land, with the minimum version moving to 3.12 in 0.16.0.

Given that every release since 0.15.0 has expanded the random ray solver's feedback and tally coverage, the next is likely to continue closing the gap between it and the main solver's feature set. The notes do not indicate whether it is intended to become a default path.