openmc.deplete.Results

class openmc.deplete.Results

Output of a depletion run

Variables:

• k (list of (float, float)) – Eigenvalue and uncertainty for each substep.
• time (list of float) – Time at beginning, end of step, in seconds.
• source_rate (float) – Source rate during timestep in [W] or [neutron/sec]
• n_mat (int) – Number of mats.
• n_nuc (int) – Number of nuclides.
• rates (list of ReactionRates) – The reaction rates for each substep.
• volume (OrderedDict of str to float) – Dictionary mapping mat id to volume.
• mat_to_ind (OrderedDict of str to int) – A dictionary mapping mat ID as string to index.
• nuc_to_ind (OrderedDict of str to int) – A dictionary mapping nuclide name as string to index.
• mat_to_hdf5_ind (OrderedDict of str to int) – A dictionary mapping mat ID as string to global index.
• n_hdf5_mats (int) – Number of materials in entire geometry.
• n_stages (int) – Number of stages in simulation.
• data (numpy.ndarray) – Atom quantity, stored by stage, mat, then by nuclide.
• proc_time (int) – Average time spent depleting a material across all materials and processes

allocate(volume, nuc_list, burn_list, full_burn_list, stages)

Allocates memory of Results.

Parameters:

• volume (dict of str float) – Volumes corresponding to materials in full_burn_dict
• nuc_list (list of str) – A list of all nuclide names. Used for sorting the simulation.
• burn_list (list of int) – A list of all mat IDs to be burned. Used for sorting the simulation.
• full_burn_list (list of str) – List of all burnable material IDs
• stages (int) – Number of stages in simulation.

distribute(local_materials, ranges)

Create a new object containing data for distributed materials

Parameters:

• local_materials (iterable of str) – Materials for this process
• ranges (iterable of int) – Slice-like object indicating indicies of local_materials in the material dimension of data and each element in rates

Returns:

New results object

Return type:

Results

export_to_hdf5(filename, step)

Export results to an HDF5 file

Parameters:

• filename (str) – The filename to write to
• step (int) – What step is this?

classmethod from_hdf5(handle, step)

Loads results object from HDF5.

Parameters:

• handle (h5py.File or h5py.Group) – An HDF5 file or group type to load from.
• step (int) – Index for depletion step

static save(op, x, op_results, t, source_rate, step_ind, proc_time=None)

Creates and writes depletion results to disk

Parameters:

• op (openmc.deplete.TransportOperator) – The operator used to generate these results.
• x (list of list of numpy.array) – The prior x vectors. Indexed [i][cell] using the above equation.
• op_results (list of openmc.deplete.OperatorResult) – Results of applying transport operator
• t (list of float) – Time indices.
• source_rate (float) – Source rate during time step in [W] or [neutron/sec]
• step_ind (int) – Step index.
• proc_time (float or None) – Total process time spent depleting materials. This may be process-dependent and will be reduced across MPI processes.

transfer_volumes(geometry)

Transfers volumes from depletion results to geometry

Parameters:geometry (OpenMC geometry to be used in a depletion restart) – calculation