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- mcnpPWR
MCNP — 17×17 PWR Assembly (baseline)
Heterogeneous 17×17 Westinghouse-style PWR assembly in MCNP6 built from two universes (fuel pin + guide-tube water column) tiled onto a 17×17 square lattice with the standard 24 guide-tube positions, surrounded by a water reflector. Energy-binned F4 track-length flux in a representative pin plus an FMESH14 17×17 pin-power mesh tally for assembly-power distribution. Source: src/pages/mcnp/example-assembly.tsx (audited March 2026).
by @caalh·1 month ago - sconeShielding
SCONE — Fixed-Source Shielding Slab (baseline)
1-D-style fixed-source neutron shielding stack in SCONE: 1 MeV `pointSource` at x=2.5 cm, three water cells (source / shield / detector regions) along x, with a `collisionClerk` flux tally on a 50-bin x-axis `spaceMap`. Uses water as a testLib-safe stand-in for Air/Concrete; the production variant (`tutorial_shielding_slab_production`) keeps the same geometry but swaps in Air + Concrete materials and a full ACE library. Source: scone-examples/verify/tutorial_shielding_slab (in the `run_all.ps1` harness — verified).
by @caalh·1 month ago - mcnpShielding
MCNP — Neutron Shielding (baseline)
Fixed-source neutron shielding analysis in MCNP6: 14 MeV point source (`sdef par=n erg=14`) collimated through a steel slab, then a concrete slab (NBS ordinary), with two point detectors (F5) and surface/cell flux tallies (F2/F4) downstream. Demonstrates importance biasing (`imp:n=1→2→4→2→0`) and 7-group MeV energy binning for shielding work. Source: src/pages/mcnp/example-shielding.tsx (audited March 2026).
by @caalh·1 month ago - mcnpPWR
MCNP — 3×3 Pin-Lattice Criticality (baseline)
Compact 3×3 fuel-pin array criticality benchmark in MCNP6. 5% enriched UO2 pins with Zircaloy clad and water moderator on a 1.26 cm pitch, reflective outer boundary (`*` prefix on the boundary surfaces). `kcode 5000 1.0 50 300` with 5 `ksrc` seeds in the central pin. Small, fast, and useful for testing tally setups before moving to a full assembly. Source: src/pages/mcnp/example-criticality.tsx (audited March 2026).
by @caalh·1 month ago - sconePWR
SCONE — 5×5 PWR Assembly (baseline)
5×5 PWR-style assembly in SCONE using `latUniverse` of three pin types: 21 fuel pins (`pinUniverse 31000`), 3 guide-tube positions (`12000`), and 1 central instrument tube (`14000`). Eigenvalue calculation with a 32×32 `fissionRate` map for pin-power distribution. Materials sized for testLib (ZAID `.03`) so it runs without a production ACE library. Source: scone-examples/verify/tutorial_assembly_5x5_testlib (in the `run_all.ps1` harness — verified).
by @caalh·1 month ago - sconePWR
SCONE — BEAVRS Cycle 1 PWR (baseline benchmark)
MIT BEAVRS Rev 2.0 — Westinghouse 4-loop PWR, 193 assemblies, 17×17 lattice; enrichments 1.6/2.4/3.1% UO2; 975 ppm boron; HFP at 600 K; control rods withdrawn. This deck is the cleaned/sectioned twin of the author-verified `Scone Input` at the repo root and is exercised by `npm run verify:beavrs-parity`. Numerics and topology match the author-verified deck; comments and formatting cleaned up for maintenance.
by @caalh·1 month ago - openmcPWR
OpenMC — PWR Pin Cell (baseline)
Standalone Python script that builds the same PWR pin cell as the MCNP/Serpent baseline templates, using OpenMC 0.15.x. Materials, geometry, settings, and tallies (fuel flux, ν-fission, absorption) all in one file. Requires `OPENMC_CROSS_SECTIONS` to point at a valid cross_sections.xml. Source: openmc-examples/example_pin/build_model.py — kept in sync with ReactorMC /openmc/example-pin/.
by @caalh·1 month ago - serpentPWR
Serpent — PWR Pin Cell (baseline)
Serpent 2 PWR pin cell k-infinity calculation. UO2 fuel, helium gap, Zircaloy-4 cladding (simplified to dominant isotopes), and light-water moderator with H-in-H2O thermal scattering. 1.26 cm pitch with reflective boundaries (`set bc 2`). Run with `sss2 -omp N pin_cell.inp`. Source: ReactorMC tutorial /serpent/example-pin.
by @caalh·1 month ago - openmcPWR
OpenMC — 17×17 PWR Assembly (baseline)
Full 17×17 PWR assembly in OpenMC 0.15.x with fuel pins, guide tubes, and a central instrumentation tube on a 1.26 cm pitch. Tallies: assembly-averaged flux/fission/absorption, a 17×17 pin power mesh tally, and an energy-resolved fuel spectrum. Source: openmc-examples/example_assembly/build_model.py — matches ReactorMC /openmc/example-assembly/.
by @caalh·1 month ago - mcnpPWR
MCNP — PWR Pin Cell (baseline)
Westinghouse 17×17-style PWR fuel pin in MCNP6: UO2 fuel (4% enriched), helium gap, Zircaloy-4 clad, light-water moderator, reflective outer boundary. Uses ENDF/B-VII.1 cross sections (.70c) and an S(α,β) thermal scattering kernel for H-in-H2O. Tallies an energy-binned track-length flux (F4) and fission energy deposition (F7) in the fuel cell. Source: ReactorMC tutorial /mcnp/example-pin.
by @caalh·1 month ago - sconePWR
SCONE — PWR Pin Cell (baseline)
SCONE eigenvalue pin cell at testLib temperature/ZAID (`.03`). Demonstrates the canonical SCONE input layout: top-level physicsPackage settings, geometry with surfaces + pinUniverse, and nuclearData materials. Drop-in runnable against `scone-examples/verify/tutorial_fuel_pin_testlib`. To run with a production ACE library, change the ZAID suffix to `.06` and replace `$SCONE_ACE` with your library path — see the SCONE Simple Examples page on ReactorMC for the production variant.
by @caalh·1 month ago - sconeTest reactor
SCONE — Bare Critical Cylinder (baseline)
Minimal SCONE input for a bare critical assembly (cylindrical stand-in — SCONE has no native sphere surface). One fuel material inside a zCylinder; water reflector outside; vacuum outer boundary. Useful as the smallest possible SCONE eigenvalue calculation. Source: scone-examples/verify/tutorial_bare_sphere_clean.
by @caalh·1 month ago