openmc.deplete.pool.deplete¶
- openmc.deplete.pool.deplete(func, chain, n, rates, dt, matrix_func=None, transfer_rates=None, *matrix_args)[source]¶
Deplete materials using given reaction rates for a specified time
- Parameters
func (callable) – Function to use to get new compositions. Expected to have the signature
func(A, n0, t) -> n1
chain (openmc.deplete.Chain) – Depletion chain
n (list of numpy.ndarray) – List of atom number arrays for each material. Each array in the list contains the number of [atom] of each nuclide.
rates (openmc.deplete.ReactionRates) – Reaction rates (from transport operator)
dt (float) – Time in [s] to deplete for
maxtrix_func (callable, optional) – Function to form the depletion matrix after calling
matrix_func(chain, rates, fission_yields)
, wherefission_yields = {parent: {product: yield_frac}}
Expected to return the depletion matrix required byfunc
transfer_rates (openmc.deplete.TransferRates, Optional) –
Object to perform continuous reprocessing.
New in version 0.13.4.
matrix_args (Any, optional) – Additional arguments passed to matrix_func
- Returns
n_result – Updated list of atom number arrays for each material. Each array in the list contains the number of [atom] of each nuclide.
- Return type
list of numpy.ndarray