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Moved tally names from statepoint to summary files

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This commit is contained in:
Will Boyd 2015-04-29 23:05:18 -04:00
parent 615724a686
commit ef9e51a2c0
4 changed files with 82 additions and 29 deletions
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8
src/hdf5_summary.F90
View file

@ -547,6 +547,14 @@ contains
! Get pointer to tally
t => tallies(i)
! Write the name for this tally
call su % write_data(len(t % name), "name_size", &
group="tallies/tally " // trim(to_str(t % id)))
if (len(t % name) > 0) then
call su % write_data(t % name, "name", &
group="tallies/tally " // trim(to_str(t % id)))
endif
! Write size of each tally
call su % write_data(t % total_score_bins, "total_score_bins", &
group="tallies/tally " // trim(to_str(t % id)))

14
src/state_point.F90
View file

@ -236,13 +236,6 @@ contains
! Get pointer to tally
tally => tallies(i)
call sp % write_data(len(tally % name), "name_size", &
group="tallies/tally " // trim(to_str(tally % id)))
if (len(tally % name) > 0) then
call sp % write_data(tally % name, "name", &
group="tallies/tally " // trim(to_str(tally % id)))
endif
call sp % write_data(tally % estimator, "estimator", &
group="tallies/tally " // trim(to_str(tally % id)))
call sp % write_data(tally % n_realizations, "n_realizations", &
@ -826,13 +819,6 @@ contains
tally => tallies(i)
curr_key = key_array(id_array(i))
call sp % read_data(j, "name_size", group="tallies/tally " // &
trim(to_str(curr_key)))
if (j > 0) then
call sp % read_data(name, "name", group="tallies/tally " // &
trim(to_str(curr_key)))
end if
call sp % read_data(tally % estimator, "estimator", &
group="tallies/tally " // trim(to_str(curr_key)))
call sp % read_data(tally % n_realizations, "n_realizations", &

17
src/utils/openmc/statepoint.py
View file

@ -298,18 +298,6 @@ class StatePoint(object):
# Iterate over all Tallies
for tally_key in self._tally_keys:
# Read user-specified Tally name (if specified)
name_size = self._get_int(
path='{0}{1}/name_size'.format(base, tally_key))[0]
if name_size > 0:
name = self._get_string(
name_size, path='{0}{1}/name'.format(base, tally_key))
# Remove leading and trailing characters from string name
name = name.lstrip('[\'')
name = name.rstrip('\']')
# Read integer Tally estimator type code (analog or tracklength)
estimator_type = self._get_int(
path='{0}{1}/estimator'.format(base, tally_key))[0]
@ -319,7 +307,7 @@ class StatePoint(object):
path='{0}{1}/n_realizations'.format(base, tally_key))[0]
# Create Tally object and assign basic properties
tally = openmc.Tally(tally_key, name)
tally = openmc.Tally(tally_key)
tally.estimator = ESTIMATOR_TYPES[estimator_type]
tally.num_realizations = n_realizations
@ -674,6 +662,9 @@ class StatePoint(object):
for tally_id, tally in self._tallies.items():
# Get the Tally name from the summary file
tally.name = summary.tallies[tally_id].name
nuclide_zaids = copy.deepcopy(tally._nuclides)
for nuclide_zaid in nuclide_zaids:

72
src/utils/openmc/summary.py
View file

@ -26,6 +26,7 @@ class Summary(object):
self._read_metadata()
self._read_geometry()
self._read_tallies()
def _read_metadata(self):
@ -398,8 +399,8 @@ class Summary(object):
self.lattices[index] = lattice
if lattice_type == 'hexagonal':
n_rings = self._f['geometry/latties'][key]['n_rings'][0]
n_axial = self._f['geometry/latties'][key]['n_axial'][0]
n_rings = self._f['geometry/lattices'][key]['n_rings'][0]
n_axial = self._f['geometry/lattices'][key]['n_axial'][0]
center = self._f['geometry/lattices'][key]['center'][...]
pitch = self._f['geometry/lattices'][key]['pitch'][...]
outer = self._f['geometry/lattices'][key]['outer'][0]
@ -464,6 +465,73 @@ class Summary(object):
self.openmc_geometry.root_universe = root_universe
def _read_tallies(self):
# Initialize dictionaries for the Tallies
# Keys - Tally IDs
# Values - Tally objects
self.tallies = {}
# Read the number of tallies
self.n_tallies = self._f['tallies/n_tallies'][0]
# OpenMC Tally keys
all_keys = self._f['tallies/'].keys()
tally_keys = [key for key in all_keys if 'tally' in key]
base = 'tallies/tally '
# Iterate over all Tallies
for tally_key in tally_keys:
tally_id = int(tally_key.strip('tally '))
subbase = '{0}{1}'.format(base, tally_id)
# Read Tally name metadata
name_size = self._f['{0}/name_size'.format(subbase)][0]
if (name_size > 0):
tally_name = self._f['{0}/name'.format(subbase)][0]
tally_name = tally_name.lstrip('[\'')
tally_name = tally_name.rstrip('\']')
else:
tally_name = ''
# Create Tally object and assign basic properties
tally = openmc.Tally(tally_id, tally_name)
# Read score metadata
score_bins = self._f['{0}/score_bins'.format(subbase)][...]
for score_bin in score_bins:
tally.add_score(openmc.SCORE_TYPES[score_bin])
num_score_bins = self._f['{0}/n_score_bins'.format(subbase)][...]
tally.num_score_bins = num_score_bins
# Read filter metadata
num_filters = self._f['{0}/n_filters'.format(subbase)][0]
# Initialize all Filters
for j in range(1, num_filters+1):
subsubbase = '{0}/filter {1}'.format(subbase, j)
# Read filter type (e.g., "cell", "energy", etc.)
filter_type = self._f['{0}/type_name'.format(subsubbase)][0]
# Read the filter bins
num_bins = self._f['{0}/n_bins'.format(subsubbase)][0]
bins = self._f['{0}/bins'.format(subsubbase)][...]
# Create Filter object
filter = openmc.Filter(filter_type, bins)
filter.num_bins = num_bins
# Add Filter to the Tally
tally.add_filter(filter)
# Add Tally to the global dictionary of all Tallies
self.tallies[tally_id] = tally
def make_opencg_geometry(self):
if self.opencg_geometry is None:
self.opencg_geometry = get_opencg_geometry(self.openmc_geometry)