- class openmc.deplete.StepResult¶
Result of a single depletion timestep
Changed in version 0.13.1: Name changed from
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)¶
Allocate memory for depletion step data
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
local_materials (iterable of str) – Materials for this process
ranges (iterable of int) – Slice-like object indicating indicies of
local_materialsin the material dimension of
dataand each element in
New results object
- Return type
- export_to_hdf5(filename, step)¶
Export results to an HDF5 file
- classmethod from_hdf5(handle, step)¶
Loads results object from HDF5.
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
op (openmc.deplete.abc.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.
Transfers volumes from depletion results to geometry
model (OpenMC model to be used in a depletion restart) – calculation