Input Definition

Full API documentation.

Defining materials

mcdc.Material	Define a continuous-energy material from a nuclide composition.
mcdc.MaterialMG	Define a multigroup material.

Defining geometry

mcdc.Cell	Define a cell from a region and a fill.
mcdc.Lattice	Define a regular lattice of universes.
mcdc.Surface	Geometric surface primitive with optional boundary condition and motion.
mcdc.Universe	Define a list of cells as a universe.

Defining meshes

mcdc.MeshUniform	Define a uniform rectilinear mesh.
mcdc.MeshStructured	Define a structured rectilinear mesh with arbitrary bin edges.

Defining sources

mcdc.Source

Define a particle source.

Defining tallies

mcdc.Tally

Define a tally.

Defining simulation settings

Settings are configured by assigning attributes on the mcdc.settings singleton. Key attributes include:

• mcdc.settings.N_particle — Number of particles.

• mcdc.settings.N_batch — Number of batches.

• mcdc.settings.rng_seed — RNG seed.

• mcdc.settings.output_name — Output file name (default: "output").

• mcdc.settings.time_boundary — Time boundary.

Methods:

• mcdc.settings.set_eigenmode(N_inactive=..., N_active=..., k_init=...) — Enable k-eigenvalue mode.

• mcdc.settings.set_time_census(time, tally_frequency=...) — Set time census parameters.

• mcdc.settings.set_source_file(source_file_name) — Load source particles from file.

Defining techniques

Techniques are enabled by calling methods on the mcdc.simulation singleton:

• mcdc.simulation.implicit_capture(active=True)

• mcdc.simulation.global_weight_roulette(weight_threshold=0.0, weight_target=1.0)

• mcdc.simulation.population_control(active=True)

• mcdc.simulation.weighted_emission(active=True, weight_target=1.0)

• mcdc.simulation.weight_windows(weight_windows, mesh=None, energy=None)

Running

mcdc.run

Execute the MC/DC simulation.