Python tutorials

Hands-on Python guides for Nucleide. Each tutorial is short, self-contained, and assumes you have already installed the project (see Getting started).

Suggested order

1. Parse MCNP output — read common MCNP output files.
2. Parse Serpent output — read Serpent _res.m, _dep.m, and _det.m files.
3. Parse FLUKA output — read FLUKA USRBIN .lis tally files.
4. Build materials — build, mix, and serialize materials.
5. Run depletion — run a CRAM depletion solve.
6. Enrichment cascade — solve a multicomponent enrichment cascade.
7. Activation analysis — read ALARA, FISPACT-II, and ORIGEN files and assemble an R2S workflow.
8. Deterministic I/O — read ISOTXS and flux files and write PARTISN decks.
9. Emit code cards — render one material to MCNP, Serpent, FLUKA, ALARA, and PARTISN cards with a mass-drift report showing how much mass each dialect kept.
10. Run kinetics — solve prescribed-reactivity point-kinetics transients.
11. Run spectroscopy — smooth spectra, count peaks, calibrate energy/efficiency, evaluate X-ray lines, and read .spe files.
12. MCPL particle interchange — read and write MCPL particle lists; merge, subset, and summarize them; repair interrupted writes.
13. UQ sampling — draw seeded MVN, log-normal, and LHS samples over caller-supplied covariance blocks and perturb decay and fission-yield data.
14. VR and MAGIC — derive weight-window lower bounds with MAGIC and sample birth voxels through alias tables.
15. Reaction names — resolve reaction names/ids/MT numbers and walk the parent/daughter reaction graph.
16. Translate CSG — translate scoped MCNP CSG decks to OpenMC, Serpent, or PHITS geometry with a drift report listing every approximation the translator made.
17. Run tritium — steady-state and transient 1D tritium permeation solves with traps and recombination boundaries.
18. Damage metrics — fold multigroup fluxes into dpa and gas production, and propagate uncertainty through the fold.
19. Fusion sources — build ring, point, and parametric tokamak neutron sources and emit MCNP/Serpent source cards.
20. Unfold a spectrum — recover a neutron spectrum from activation detector measurements with SAND-II, least-squares, or GRAVEL adjustment, including the IRDFF response pack.
21. Clearance screening — classify parsed activation inventories against the EU or Spanish clearance tables.

End-to-end notebooks

Single-topic pages above compose into full workflows in notebooks/: first-wall damage + UQ, activation screening + radiological totals, and tokamak source sampling + card emission. Every notebook executes in CI with fixed seeds over committed fixtures, so the workflows are verified examples, not sketches.