← ClaudeAtlas

openmclisted

Use when writing OpenMC Python code for neutron/photon transport simulations, geometry construction (CSG surfaces, cells, universes, lattices), material definition (nuclides, elements, enrichment, density), settings configuration (eigenvalue, fixed-source, batches, particles, source distributions), or when debugging OpenMC Python errors. Covers fission reactor design and research neutronics workflows.
itaybnv/openmc-claude-skills · ★ 0 · AI & Automation · score 78
Install: claude install-skill itaybnv/openmc-claude-skills
# OpenMC Knowledge Base **Coverage:** Materials · CSG Geometry · Lattice Geometry · Settings · Tallies · Statepoint · Model API · Gotchas · Depletion · MGXS · Nuclear Data · openmc.lib · **Patterns · Overview · Parallel · Plots** **Not yet covered** (Phase 6): README, community docs, public release ## Task Routing ## Entry Points **Broad / orientation / "how does OpenMC work" / "getting started" / unclear scope:** Read `docs/overview.md` **Complete example / end-to-end script / "full simulation" / "copy-paste runnable" / workflow:** Read `docs/patterns.md` --- Load the docs relevant to the task at hand. For narrow questions, load one file (e.g., only tallies.md for a filter question). For cross-cutting tasks, load the files that span the question (e.g., tallies.md + statepoint.md for construction-through-readback). Never load all docs indiscriminately — choose based on what the task actually requires. --- ## Cluster A — Build a Model **Materials / nuclides / enrichment / density:** Read `docs/materials.md` **CSG geometry — surfaces, cells, regions, universes:** Read `docs/geometry-csg.md` **Simulation settings — batches, particles, source, run mode:** Read `docs/settings.md` **Building a complete model (geometry + materials + settings together):** Read `docs/geometry-csg.md` + `docs/materials.md` + `docs/settings.md` ## Cluster B — Lattice Geometry **Lattice geometry — RectLattice, HexLattice, nested universes, assembly geometry:** Read `docs/geometry-lattices