OpenMC/scripts/openmc-make-depletion-chain-casl
2019-10-28 11:55:45 -05:00

240 lines
9.3 KiB
Python
Executable file

#!/usr/bin/env python3
import glob
import os
from zipfile import ZipFile
from collections import OrderedDict, defaultdict
from io import StringIO
from itertools import chain
try:
import lxml.etree as ET
_have_lxml = True
except ImportError:
import xml.etree.ElementTree as ET
_have_lxml = False
import openmc.data
import openmc.deplete
from openmc._xml import clean_indentation
from openmc.deplete.chain import _REACTIONS
from openmc.deplete.nuclide import Nuclide, DecayTuple, ReactionTuple
from openmc._utils import download
from casl_chain import CASL_CHAIN
URLS = [
'http://www.nndc.bnl.gov/endf/b7.1/zips/ENDF-B-VII.1-neutrons.zip',
'http://www.nndc.bnl.gov/endf/b7.1/zips/ENDF-B-VII.1-decay.zip',
'http://www.nndc.bnl.gov/endf/b7.1/zips/ENDF-B-VII.1-nfy.zip'
]
def main():
if os.path.isdir('./decay') and os.path.isdir('./nfy') and os.path.isdir('./neutrons'):
endf_dir = '.'
elif 'OPENMC_ENDF_DATA' in os.environ:
endf_dir = os.environ['OPENMC_ENDF_DATA']
else:
for url in URLS:
basename = download(url)
with ZipFile(basename, 'r') as zf:
print('Extracting {}...'.format(basename))
zf.extractall()
endf_dir = '.'
decay_files = glob.glob(os.path.join(endf_dir, 'decay', '*.endf'))
fpy_files = glob.glob(os.path.join(endf_dir, 'nfy', '*.endf'))
neutron_files = glob.glob(os.path.join(endf_dir, 'neutrons', '*.endf'))
# Create a Chain
chain = openmc.deplete.Chain()
print('Reading ENDF nuclear data from "{}"...'.format(os.path.abspath(endf_dir)))
# Create dictionary mapping target to filename
print('Processing neutron sub-library files...')
reactions = {}
for f in neutron_files:
evaluation = openmc.data.endf.Evaluation(f)
name = evaluation.gnd_name
if name in CASL_CHAIN:
reactions[name] = {}
for mf, mt, nc, mod in evaluation.reaction_list:
if mf == 3:
file_obj = StringIO(evaluation.section[3, mt])
openmc.data.endf.get_head_record(file_obj)
q_value = openmc.data.endf.get_cont_record(file_obj)[1]
reactions[name][mt] = q_value
# Determine what decay and FPY nuclides are available
print('Processing decay sub-library files...')
decay_data = {}
for f in decay_files:
data = openmc.data.Decay(f)
name = data.nuclide['name']
if name in CASL_CHAIN:
decay_data[name] = data
for name in CASL_CHAIN:
if name not in decay_data:
print('WARNING: {} has no decay data!'.format(name))
print('Processing fission product yield sub-library files...')
fpy_data = {}
for f in fpy_files:
data = openmc.data.FissionProductYields(f)
name = data.nuclide['name']
if name in CASL_CHAIN:
fpy_data[name] = data
print('Creating depletion_chain...')
missing_daughter = []
missing_rx_product = []
missing_fpy = []
for idx, parent in enumerate(sorted(decay_data, key=openmc.data.zam)):
data = decay_data[parent]
nuclide = Nuclide()
nuclide.name = parent
chain.nuclides.append(nuclide)
chain.nuclide_dict[parent] = idx
if not CASL_CHAIN[parent][0] and \
not data.nuclide['stable'] and data.half_life.nominal_value != 0.0:
nuclide.half_life = data.half_life.nominal_value
nuclide.decay_energy = sum(E.nominal_value for E in
data.average_energies.values())
sum_br = 0.0
for i, mode in enumerate(data.modes):
type_ = ','.join(mode.modes)
if mode.daughter in decay_data:
target = mode.daughter
else:
print('missing {} {} {}'.format(parent, ','.join(mode.modes), mode.daughter))
continue
# Write branching ratio, taking care to ensure sum is unity
br = mode.branching_ratio.nominal_value
sum_br += br
if i == len(data.modes) - 1 and sum_br != 1.0:
br = 1.0 - sum(m.branching_ratio.nominal_value
for m in data.modes[:-1])
# Append decay mode
nuclide.decay_modes.append(DecayTuple(type_, target, br))
if parent in reactions:
reactions_available = set(reactions[parent].keys())
for name, mts, changes in _REACTIONS:
if mts & reactions_available:
delta_A, delta_Z = changes
A = data.nuclide['mass_number'] + delta_A
Z = data.nuclide['atomic_number'] + delta_Z
daughter = '{}{}'.format(openmc.data.ATOMIC_SYMBOL[Z], A)
if name not in chain.reactions:
chain.reactions.append(name)
if daughter not in decay_data:
missing_rx_product.append((parent, name, daughter))
daughter = 'Nothing'
# Store Q value
for mt in sorted(mts):
if mt in reactions[parent]:
q_value = reactions[parent][mt]
break
else:
q_value = 0.0
nuclide.reactions.append(ReactionTuple(
name, daughter, q_value, 1.0))
if any(mt in reactions_available for mt in [18, 19, 20, 21, 38]):
if parent in fpy_data:
q_value = reactions[parent][18]
nuclide.reactions.append(
ReactionTuple('fission', 0, q_value, 1.0))
if 'fission' not in chain.reactions:
chain.reactions.append('fission')
else:
missing_fpy.append(parent)
if parent in fpy_data:
fpy = fpy_data[parent]
if fpy.energies is not None:
nuclide.yield_energies = fpy.energies
else:
nuclide.yield_energies = [0.0]
for E, table_yd, table_yc in zip(nuclide.yield_energies, fpy.independent, fpy.cumulative):
yields = defaultdict(float)
for product in table_yd:
if product in decay_data:
# identifier
ifpy = CASL_CHAIN[product][2]
# 1 for independent
if ifpy == 1:
if product not in table_yd:
print('No independent fission yields found for {} in {}'.format(product, parent))
else:
yields[product] += table_yd[product].nominal_value
# 2 for cumulative
elif ifpy == 2:
if product not in table_yc:
print('No cumulative fission yields found for {} in {}'.format(product, parent))
else:
yields[product] += table_yc[product].nominal_value
# -1 for stable + unstable
elif ifpy == -1:
if product not in table_yd:
print('No independent fission yields found for {} in {}'.format(product, parent))
else:
yields[product] += table_yc[product].nominal_value
product_meta = '{}_m1'.format(product)
if product_meta in table_yd:
yields[product] += table_yc[product_meta].nominal_value
# 3 for special treatment with weight fractions
elif ifpy == 3:
for tuple_i in CASL_CHAIN[product][3]:
name_i, weight_i, ifpy_i = tuple_i
if name_i not in table_yd:
print('No fission yields found for {} in {}'.format(name_i, parent))
else:
if ifpy_i == 1:
yields[product] += weight_i * table_yd[name_i].nominal_value
elif ifpy_i == 2:
yields[product] += weight_i * table_yc[name_i].nominal_value
nuclide.yield_data[E] = []
for k in sorted(yields, key=openmc.data.zam):
nuclide.yield_data[E].append((k, yields[k]))
# Display warnings
if missing_daughter:
print('The following decay modes have daughters with no decay data:')
for mode in missing_daughter:
print(' {}'.format(mode))
print('')
if missing_rx_product:
print('The following reaction products have no decay data:')
for vals in missing_rx_product:
print('{} {} -> {}'.format(*vals))
print('')
if missing_fpy:
print('The following fissionable nuclides have no fission product yields:')
for parent in missing_fpy:
print(' ' + parent)
print('')
chain.export_to_xml('chain_casl.xml')
if __name__ == '__main__':
main()