YAMC

Yet Another Monte Carlo: an open-source Monte Carlo particle transport code for neutron and photon simulations, with a focus on fusion neutronics workflows.

Documentation 📝 | PyPI 🐍

pip install yamc

import yamc

yamc.cross_section_data = "endf-b8.1"

steel = yamc.Material({"Fe56": 1.0}, density=7.87)
sphere = yamc.Sphere(radius=10.0, boundary="vacuum")
cell = yamc.Cell(region=sphere.below, material=steel)
geometry = yamc.Geometry([cell])

source = yamc.NeutronSource(energy=yamc.sources.Discrete([14.06e6], [1.0]))
tally = yamc.Tally(scores=["flux"])

model = yamc.Model(geometry=geometry, source=source, tallies=[tally])
results = model.simulate_transport(total_particles=10_000)
print(results[tally].mean)

What it does

Continuous-energy neutron and photon transport over CSG or unstructured mesh geometry, on CPU or GPU, with tallies, variance reduction, transport-coupled transmutation and shutdown dose rates. The solver is Rust; the wheel needs no compiler and no external toolchain.

Transmutation without transport

If you already have a spectrum and want none of the transport stack, install yani instead: same materials, same schedules, same nuclear data, no geometry.