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Fix MPI depletion hang (#3910)

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Md. Ariful Islam 2026-04-02 12:30:09 -04:00 • committed by GitHub
parent 8223099ed9
commit 97d9a839c2
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2 changed files with 4 additions and 4 deletions
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4
openmc/deplete/abc.py
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@ -201,7 +201,7 @@ class TransportOperator(ABC):
Returns
-------
volume : dict of str to float
Volumes corresponding to materials in burn_list
Volumes corresponding to materials in full_burn_list
nuc_list : list of str
A list of all nuclide names. Used for sorting the simulation.
burn_list : list of int
@ -210,7 +210,7 @@ class TransportOperator(ABC):
full_burn_list : list of int
All burnable materials in the geometry.
name_list : list of str
Material names corresponding to materials in burn_list
Material names corresponding to materials in full_burn_list
"""
def finalize(self):

4
openmc/deplete/stepresult.py
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@ -154,14 +154,14 @@ class StepResult:
full_burn_list : list of str
List of all burnable material IDs
name_list : list of str, optional
Material names corresponding to materials in burn_list
Material names corresponding to materials in full_burn_list
"""
self.volume = copy.deepcopy(volume)
self.index_nuc = {nuc: i for i, nuc in enumerate(nuc_list)}
self.index_mat = {mat: i for i, mat in enumerate(burn_list)}
self.mat_to_hdf5_ind = {mat: i for i, mat in enumerate(full_burn_list)}
self.mat_to_name = dict(zip(burn_list, name_list)) if name_list is not None else {}
self.mat_to_name = dict(zip(full_burn_list, name_list)) if name_list is not None else {}
# Create storage array
self.data = np.zeros((self.n_mat, self.n_nuc))