diff --git a/openmc/deplete/chain.py b/openmc/deplete/chain.py index 662106a696..608d45a437 100644 --- a/openmc/deplete/chain.py +++ b/openmc/deplete/chain.py @@ -189,7 +189,7 @@ class Chain(object): return len(self.nuclides) @classmethod - def from_endf(cls, decay_files, fpy_files, neutron_files): + def from_endf(cls, decay_files, fpy_files, neutron_files, progress=True): """Create a depletion chain from ENDF files. Parameters @@ -200,12 +200,20 @@ class Chain(object): List of ENDF neutron-induced fission product yield sub-library files neutron_files : list of str List of ENDF neutron reaction sub-library files + progress : bool, optional + Flag to print status messages during processing. Does not + effect warning messages + + Returns + ------- + Chain """ chain = cls() # Create dictionary mapping target to filename - print('Processing neutron sub-library files...') + if progress: + print('Processing neutron sub-library files...') reactions = {} for f in neutron_files: evaluation = openmc.data.endf.Evaluation(f) @@ -219,7 +227,8 @@ class Chain(object): reactions[name][mt] = q_value # Determine what decay and FPY nuclides are available - print('Processing decay sub-library files...') + if progress: + print('Processing decay sub-library files...') decay_data = {} for f in decay_files: data = openmc.data.Decay(f) @@ -228,13 +237,15 @@ class Chain(object): continue decay_data[data.nuclide['name']] = data - print('Processing fission product yield sub-library files...') + if progress: + print('Processing fission product yield sub-library files...') fpy_data = {} for f in fpy_files: data = openmc.data.FissionProductYields(f) fpy_data[data.nuclide['name']] = data - print('Creating depletion_chain...') + if progress: + print('Creating depletion_chain...') missing_daughter = [] missing_rx_product = [] missing_fpy = []