mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-29 06:35:48 -04:00
Minor tweaks to Operator, EnergyScoreHelper
Per reviewer comments
This commit is contained in:
parent
cfbd4f2fd6
commit
2ab3ad7b78
2 changed files with 2 additions and 7 deletions
|
|
@ -205,7 +205,7 @@ class EnergyScoreHelper(EnergyHelper):
|
|||
the number of MPI processes
|
||||
"""
|
||||
super().reset()
|
||||
if not comm.rank:
|
||||
if comm.rank == 0:
|
||||
self._energy = self._tally.results[0, 0, 1]
|
||||
|
||||
# ------------------------------------
|
||||
|
|
|
|||
|
|
@ -84,8 +84,7 @@ class Operator(TransportOperator):
|
|||
Indicator for computing system energy. ``"energy-deposition"`` will
|
||||
compute with a single energy deposition tally, taking fission energy
|
||||
release data and heating into consideration. ``"fission-q"`` will
|
||||
use the fission Q values from the depletion chain, not taking
|
||||
heating into consideration.
|
||||
use the fission Q values from the depletion chain
|
||||
fission_q : dict, optional
|
||||
Dictionary of nuclides and their fission Q values [eV]. If not given,
|
||||
values will be pulled from the ``chain_file``. Only applicable
|
||||
|
|
@ -261,8 +260,6 @@ class Operator(TransportOperator):
|
|||
# Update status
|
||||
self.number.set_density(vec)
|
||||
|
||||
time_start = time.time()
|
||||
|
||||
# Update material compositions and tally nuclides
|
||||
self._update_materials()
|
||||
nuclides = self._get_tally_nuclides()
|
||||
|
|
@ -274,8 +271,6 @@ class Operator(TransportOperator):
|
|||
openmc.lib.reset()
|
||||
openmc.lib.run()
|
||||
|
||||
time_openmc = time.time()
|
||||
|
||||
# Extract results
|
||||
op_result = self._unpack_tallies_and_normalize(power)
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue