mcdc.iQMC

mcdc.iQMC(phi0=None, g=None, t=None, x=None, y=None, z=None, source0=None, source_x0=None, source_y0=None, source_z0=None, krylov_restart=None, fixed_source=None, maxit=25, tol=1e-06, fixed_source_solver='source iteration', sample_method='halton', mode='fixed', scores=[])

Activate the iterative Quasi-Monte Carlo (iQMC) neutron transport method.

Parameters

phi0array_like[float], optional

Initial scalar flux approximation (default None).

garray_like[float], optional

Energy values that define energy mesh (default None).

tarray_like[float], optional

Time values that define time mesh (default None).

xarray_like[float], optional

x-coordinates that define spacial mesh (default None).

yarray_like[float], optional

y-coordinates that define spacial mesh (default None).

zarray_like[float], optional

z-coordinates that define spacial mesh (default None).

Other Parameters

source0array_like[float], optional

Initial particle source (default None).

source_x0array_like[float], optional

Initial source for source-x (default None).

source_y0array_like[float], optional

Initial source for source-y (default None).

source_z0array_like[float], optional

Initial source for source-z (default None).

krylov_restartint, optional

Max number of iterations for Krylov iteration (default same as maxit).

fixed_sourcearray_like[float], optional

Fixed source (default same as phi0).

iterations_maxint, optional

Maximum number of iterations allowed before termination (default 25).

tolfloat, optional

Convergence tolerance (default 1e-6).

fixed_source_solver{‘source iteration’, ‘gmres’}

Deterministic solver for fixed-source problem (default “source iteration”). Solver for k-eigenvalue problem (default “power_iteration”).

sample_method: {‘halton’, ‘random’}

Method for generating particle samples.

mode: {‘fixed’, batched}

Set iQMC to run with a fixed-seed or batched iteration scheme.

scoreslist of str, optional

List of tallies to score in addition to the mandatory flux and source strength. Additional scores include {‘source-x’, ‘source-y’, ‘source-z’, ‘fission-power’} (default empty list).

Returns

None (in-place card alterations).

Notes

phi0 is used to estimate the initial source strength. If source0 is provided, source0 will be used instead of phi0. Either phi0 or source0 must be provided as they are used to initialize particle weights.