def test_transmuters_cram():
n0 = {"H3": 1.0}
A = -cram.DECAY_MATRIX * data.half_life("H3")
n1 = transmuters.cram(A, n0, order=16)
assert_equal(2, len(n1))
assert_almost_equal(0.5, n1[nucname.id("H3")])
assert_almost_equal(0.5, n1[nucname.id("He3")])
def get_composition_fresh(in_list, burnup):
""" Returns a dictionary of isotope and composition (in mass fraction)
using vision_recipes for fresh UOX
Parameters
---------
in_list: list
list file containing vision_recipes data.
burnup: int
burnup
Returns
-------
data_dict: dictionary
dictionary with key: isotope, and value: composition.
"""
data_dict = {}
for i in range(len(in_list)):
if i > 1:
if burnup == 33:
data_dict.update({nn.id(in_list[i][0]): float(in_list[i][1])})
elif burnup == 51:
data_dict.update({nn.id(in_list[i][0]): float(in_list[i][3])})
else:
data_dict.update({nn.id(in_list[i][0]): float(in_list[i][5])})
return data_dict
def reaction(self, nuc, rx, nuc_i = None):
"""Get reaction data.
Parameters
----------
nuc : int or str
Nuclide containing the reaction.
rx : int or str
Desired reaction
nuc_i : int or str
Nuclide containing the reaction. Defaults to nuc.
group_bounds : tuple
Low and high energy bounds of the new group.
Returns
----------
rxdict : dict
Dictionary containing source group structure, energy values, cross-
section data, and interpolation data."""
if nuc_i is None:
nuc_i = nuc
nuc = nucname.id(nuc)
rx = rxname.mt(rx)
nuc_i = nucname.id(nuc_i)
if (nuc, rx, nuc_i) not in self.rxcache:
self._load_reaction(nuc, rx, nuc_i)
return self.rxcache[nuc, rx, nuc_i]
def get_composition_spent(in_list, burnup):
""" Returns a dictionary of isotope and composition (in mass fraction)
using vision_recipes for spent nuclear fuel
Parameters
---------
in_list: list
list containing vision_recipes data
burnup: int
burnup
Returns
-------
data_dict: dict
dictionary with key=[isotope],
and value=[composition]
"""
data_dict = {}
for i in range(len(in_list)):
if i > 1:
if burnup == 33:
data_dict.update({nn.id(in_list[i][0]):
float(in_list[i][2])})
elif burnup == 51:
data_dict.update({nn.id(in_list[i][0]):
float(in_list[i][4])})
else:
data_dict.update({nn.id(in_list[i][0]):
float(in_list[i][6])})
return data_dict
def test_zzllaaam_to_id():
assert_equal(nucname.zzllaaam_to_id("94-Pu-239"), nucname.id("Pu-239"))
assert_equal(nucname.zzllaaam_to_id("95-Am-242m"), nucname.id("Am-242m"))
assert_equal(nucname.zzllaaam_to_id("94-Pu-239"), nucname.id("Pu-239"))
assert_equal(nucname.zzllaaam_to_id("95-Am-242"), nucname.id("Am-242"))
assert_equal(nucname.zzllaaam_to_id("95-Am-242m"), nucname.id("Am-242m"))
def reaction(self, nuc, rx, nuc_i=None):
"""Get reaction data.
Parameters
----------
nuc : int or str
Nuclide containing the reaction.
rx : int or str
Desired reaction
nuc_i : int or str
Nuclide containing the reaction. Defaults to nuc.
group_bounds : tuple
Low and high energy bounds of the new group.
Returns
----------
rxdict : dict
Dictionary containing source group structure, energy values, cross-
section data, and interpolation data."""
if nuc_i is None:
nuc_i = nuc
nuc = nucname.id(nuc)
rx = rxname.mt(rx)
nuc_i = nucname.id(nuc_i)
if (nuc, rx, nuc_i) not in self.rxcache:
self._load_reaction(nuc, rx, nuc_i)
return self.rxcache[nuc, rx, nuc_i]
def make_atomic_mass_table(nuc_data, build_dir=""):
"""Makes an atomic mass table in the nuc_data library.
Parameters
----------
nuc_data : str
Path to nuclide data file.
build_dir : str
Directory to place html files in.
"""
# Grab raw data
atomic_abund = get_isotopic_abundances()
atomic_masses = parse_atomic_mass_adjustment(build_dir)
A = {}
# Add normal isotopes to A
for nuc, mass, error in atomic_masses:
if nuc in atomic_abund:
A[nuc] = nuc, mass, error, atomic_abund[nuc]
else:
A[nuc] = nuc, mass, error, 0.0
# Add naturally occuring elements
for element in nucname.name_zz:
nuc = nucname.id(element)
A[nuc] = nuc, 0.0, 0.0, 0.0
for nuc, abund in atomic_abund.items():
zz = nucname.znum(nuc)
element_zz = nucname.id(zz)
element = nucname.zz_name[zz]
_nuc, nuc_mass, _error, _abund = A[nuc]
elem_zz, elem_mass, _error, _abund = A[element_zz]
new_elem_mass = elem_mass + (nuc_mass * abund)
A[element_zz] = element_zz, new_elem_mass, 0.0, float(
0.0 < new_elem_mass)
A = sorted(A.values(), key=lambda x: x[0])
# Open the HDF5 File
kdb = tb.open_file(nuc_data, "a", filters=BASIC_FILTERS)
# Make a new the table
Atable = kdb.create_table(
"/",
"atomic_mass",
atomic_mass_desc,
"Atomic Mass Data [amu]",
expectedrows=len(A),
)
Atable.append(A)
# Ensure that data was written to table
Atable.flush()
# Close the hdf5 file
kdb.close()
def test_zzllaaam_to_id():
assert_equal(nucname.zzllaaam_to_id("94-Pu-239"), nucname.id("Pu-239"))
assert_equal(nucname.zzllaaam_to_id("95-Am-242m"), nucname.id("Am-242m"))
assert_equal(nucname.zzllaaam_to_id("94-Pu-239"), nucname.id("Pu-239"))
assert_equal(nucname.zzllaaam_to_id("95-Am-242"), nucname.id("Am-242"))
assert_equal(nucname.zzllaaam_to_id("95-Am-242m"), nucname.id("Am-242m"))
def _load_reactions(self, num_dens, phi_tot):
"""Loads the group structure from a tally in openMC. It is
assumed that all tallies have the same group structure
Parameters
----------
state_point: openMC statepoint file
The statepoint file that will be used to load the reaction
rates to determine the microscopic cross sections for the
statepoint.
num_dens: map of int to float
A map containing the number densities of the nuclides in the
material used in the statepoint.
phi_tot: array of floats
The total flux within the reactor
"""
for tally in self.tallies:
sp = self.state_point.tallies[tally]
for nuclide in sp.nuclides:
for score in sp.scores:
self.reactions[nucname.id(nuclide.name),
score] = sp.get_values([score], [], [], [
nuclide.name
]).flatten() * self.particles
weight = 1.0E24 / abs(
phi_tot * num_dens[nucname.id(nuclide.name)])
self.reactions[nucname.id(nuclide.name), score] *= weight
def make_atomic_mass_table(nuc_data, build_dir=""):
"""Makes an atomic mass table in the nuc_data library.
Parameters
----------
nuc_data : str
Path to nuclide data file.
build_dir : str
Directory to place html files in.
"""
# Grab raw data
atomic_abund = get_isotopic_abundances()
atomic_masses = parse_atomic_mass_adjustment(build_dir)
A = {}
# Add normal isotopes to A
for nuc, mass, error in atomic_masses:
if nuc in atomic_abund:
A[nuc] = nuc, mass, error, atomic_abund[nuc]
else:
A[nuc] = nuc, mass, error, 0.0
# Add naturally occuring elements
for element in nucname.name_zz:
nuc = nucname.id(element)
A[nuc] = nuc, 0.0, 0.0, 0.0
for nuc, abund in atomic_abund.items():
zz = nucname.znum(nuc)
element_zz = nucname.id(zz)
element = nucname.zz_name[zz]
_nuc, nuc_mass, _error, _abund = A[nuc]
elem_zz, elem_mass, _error, _abund = A[element_zz]
new_elem_mass = elem_mass + (nuc_mass * abund)
A[element_zz] = element_zz, new_elem_mass, 0.0, float(0.0 < new_elem_mass)
A = sorted(A.values(), key=lambda x: x[0])
# Open the HDF5 File
kdb = tb.openFile(nuc_data, 'a', filters=BASIC_FILTERS)
# Make a new the table
Atable = kdb.createTable("/", "atomic_mass", atomic_mass_desc,
"Atomic Mass Data [amu]", expectedrows=len(A))
Atable.append(A)
# Ensure that data was written to table
Atable.flush()
# Close the hdf5 file
kdb.close()
def handle_endtag(self, tag):
if tag == "tr":
row = self._currrow
self._currrow = []
if len(row) == 7 and row[0] == "Fission" and row[1] == "product":
self._fromnucs = [nucname.id(x) for x in row[-4:]]
return
if len(row) != 6:
return
if row[0].endswith("FP"):
return
tonuc = nucname.id(row[0].split("-", 1)[1])
self.fission_product_yields += zip(self._fromnucs, [tonuc] * 4, map(float, row[-4:]))
def _ensure_nl(self, rc):
# Make nuclide lists
if isinstance(rc.core_load_nucs, basestring):
core_load = load_nuc_file(rc.core_load_nucs)
else:
core_load = [nucname.id(nuc) for nuc in rc.core_load_nucs]
rc.core_load = sorted(set(core_load))
if isinstance(rc.core_transmute_nucs, basestring):
core_transmute = load_nuc_file(rc.core_transmute_nucs)
else:
core_transmute = [nucname.id(nuc) for nuc in rc.core_transmute_nucs]
rc.core_transmute = sorted(set(core_transmute))
def handle_endtag(self, tag):
if tag == 'tr':
row = self._currrow
self._currrow = []
if len(row) == 7 and row[0] == 'Fission' and row[1] == 'product':
self._fromnucs = [nucname.id(x) for x in row[-4:]]
return
if len(row) != 6:
return
if row[0].endswith('FP'):
return
tonuc = nucname.id(row[0].split('-', 1)[1])
self.fission_product_yields += zip(self._fromnucs, [tonuc] * 4,
map(float, row[-4:]))
def handle_endtag(self, tag):
if tag == "tr":
row = self._currrow
self._currrow = []
if len(row) == 7 and row[0] == "Fission" and row[1] == "product":
self._fromnucs = [nucname.id(x) for x in row[-4:]]
return
if len(row) != 6:
return
if row[0].endswith("FP"):
return
tonuc = nucname.id(row[0].split("-", 1)[1])
self.fission_product_yields += zip(self._fromnucs, [tonuc] * 4,
map(float, row[-4:]))
def handle_endtag(self, tag):
if tag == 'tr':
row = self._currrow
self._currrow = []
if len(row) == 7 and row[0] == 'Fission' and row[1] == 'product':
self._fromnucs = [nucname.id(x) for x in row[-4:]]
return
if len(row) != 6:
return
if row[0].endswith('FP'):
return
tonuc = nucname.id(row[0].split('-', 1)[1])
self.fission_product_yields += zip(self._fromnucs, [tonuc]*4,
map(float, row[-4:]))
def _copy_radio_abundances(self):
"""Copies the radioactive isotopes onto the corresponding stable
elements. This routine is intended for uses of the mapper during which
the decay is neglected
Notes
-----
Must be called after _remap_abundances.
Raises
------
AttributeError if called before _remap_abundances
"""
try:
self.radio_abundances_interp
except AttributeError:
logger.critical("Abundances must be remapped before radioactive:"
" isotopes are copied onto the stable elements")
raise AttributeError("no radio_abundances_interp; call"
" _remap_abundances first")
for ident in self.radio_abundances_interp.keys():
elemid = nucname.id(ident)
z = nucname.znum(elemid)
self.abundances_interp[z] = \
self.abundances_interp[z] + self.radio_abundances_interp[ident]
def test_parse_dep1():
"""
Tests the parse_dep function with a serpent 1 _dep.m
file. In this, the _VOLUME variable is a float.
"""
dep = serpent.parse_dep("sample1_dep.m")
nuc_set = set([nucname.id(int(nuc)) for nuc in dep["ZAI"][:-2]])
shape = (len(dep["ZAI"]), len(dep["DAYS"]))
for key in dep:
if key.endswith("_VOLUME"):
assert_true(isinstance(dep[key], float))
elif key.endswith("_MATERIAL"):
assert_equal(len(dep[key]), shape[1])
for n in range(shape[1]):
assert_equal(nuc_set, set(dep[key][n].comp.keys()))
elif key.startswith("MAT_") and key.endswith("_BURNUP"):
assert_equal(dep[key].shape, (1, shape[1]))
elif key.startswith("MAT_") or key.startswith("TOT_"):
assert_equal(dep[key].shape, shape)
# Check values
assert_array_equal(dep["BU"], [0.00000e00, 8.40000e01, 1.68000e02])
assert_equal(dep["i952421"], 123)
assert_array_equal(dep["MAT_fuelp1r2_H"][3],
[0.00000e00, 5.56191e-11, 3.22483e-10])
def _decay_abundances(self):
"""Determines the decay of all radioactive isotopes. Afterwards their
mass fractions are added to the stable elements.
Notes
-----
Must be called after _remap_abundances.
Raises
------
AttributeError if called before _remap_abundances
"""
try:
self.radio_abundances_interp
except AttributeError:
logger.critical("Abundances must be remapped before decay is"
" handled")
raise AttributeError("no radio_abundances_interp; call "
"_remap_abundances first")
for i in xrange(self.N_interp):
comp = {}
mass = 0
for ident in self.radio_abundances_interp.keys():
Xi = self.radio_abundances_interp[ident][i]
mass += Xi
comp[nucname.id(ident)] = Xi
inp = material.Material(comp, mass=mass)
res = inp.decay(
(self.t - self.orig.t).to("s").value).mult_by_mass()
for item in res.items():
z = nucname.znum(item[0])
self.abundances_interp[z][i] = \
self.abundances_interp[z][i] + item[1]
def test_ace_table_init():
atab = openmc_utils.AceTable(zaid='92235', path='U235.ace',
cross_sections_path='/tmp/cross_sections.xml')
assert_equal('92235', atab.zaid)
assert_equal('U235.ace', atab.path)
assert_equal('/tmp/U235.ace', atab.abspath)
assert_equal(nucname.id('U235'), atab.nucid)
def test_parse_dep2():
'''
Tests the parse_dep function with a simple _dep.m file,
sample2_dep.m, which was generated using the 2d pin burnup
example from the serpent wiki, changed to have fewer depsteps.
In this, the _VOLUME variable is a numpy array.
http://serpent.vtt.fi/mediawiki/index.php/2D_PWR_pin-cell_burnup_example
'''
dep = serpent.parse_dep('sample2_dep.m')
nuc_set = set([nucname.id(int(nuc)) for nuc in dep['ZAI'][:-2]])
shape = (len(dep['ZAI']), len(dep['DAYS']))
for key in dep:
if key.endswith('_VOLUME'):
assert_equal(len(dep[key]), shape[1])
elif key.endswith('_vol'):
assert_equal(len(dep[key]), shape[1])
elif key.endswith('_MATERIAL'):
assert_equal(len(dep[key]), shape[1])
for n in range(shape[1]):
assert_equal(nuc_set, set(dep[key][n].comp.keys()))
elif key.endswith('_BURNUP'):
assert_equal(len(dep[key]), shape[1])
elif key.startswith('MAT_') or key.startswith('TOT_'):
assert_equal(len(dep[key]), shape[0])
assert_equal(len(dep[key][0]), shape[1])
# Check values
assert_array_equal(dep['BU'], [ 0.00000E+00, 1.00000E-01, 1.00000E+00 ])
assert_equal(dep['i621510'], 22)
assert_array_equal(dep['MAT_fuel_A'][6], [0.00000E+00, 1.73176E+05, 4.96485E+06])
def _load_reaction(self, nuc, rx, nuc_i, src_phi_g=None, temp=300.0):
"""Note: ENDF data does not use temperature information (temp)
Parameters
----------
nuc : int
Nuclide in id form.
rx : int or str
Reaction MT # in nnnm form.
OR:
Reaction key: 'gamma', 'alpha', 'p', etc.
nuc_i: : int
Isotope in id form (optional). Default is None.
Returns
-------
rxdata: ndarray of floats, len ngroups
"""
nuc = nucname.id(nuc)
rx = rxname.mt(rx)
if nuc_i not in self.library.structure[nuc]['data']:
self.library._read_res(nuc)
rxdict = self.library.get_xs(nuc, rx, nuc_i)[0]
rxdict['_src_phi_g'] = src_phi_g
self.rxcache[nuc, rx, nuc_i] = rxdict
self._load_group_structure(nuc, rx, nuc_i)
return rxdict
def reaction(self, nuc, rx, temp=300.0):
"""Gets the cross section data for this reaction channel either directly
from the data source or from the rxcache.
Parameters
----------
nuc : int or str
A nuclide.
rx : int or str
Reaction id or name.
temp : float, optional
Temperature [K] of material, defaults to 300.0.
Returns
-------
rxdata : ndarray
Source cross section data, length src_ngroups.
"""
nuc = nucname.id(nuc)
rx = rxname.id(rx)
rxkey = (nuc, rx, temp) if self._USES_TEMP else (nuc, rx)
if rxkey not in self.rxcache:
self.rxcache[rxkey] = None if self.fullyloaded \
else self._load_reaction(nuc, rx, temp)
return self.rxcache[rxkey]
def test_parse_dep2():
"""
Tests the parse_dep function with a simple _dep.m file,
sample2_dep.m, which was generated using the 2d pin burnup
example from the serpent wiki, changed to have fewer depsteps.
In this, the _VOLUME variable is a numpy array.
http://serpent.vtt.fi/mediawiki/index.php/2D_PWR_pin-cell_burnup_example
"""
dep = serpent.parse_dep("sample2_dep.m")
nuc_set = set([nucname.id(int(nuc)) for nuc in dep["ZAI"][:-2]])
shape = (len(dep["ZAI"]), len(dep["DAYS"]))
for key in dep:
if key.endswith("_VOLUME"):
assert_equal(len(dep[key]), shape[1])
elif key.endswith("_vol"):
assert_equal(len(dep[key]), shape[1])
elif key.endswith("_MATERIAL"):
assert_equal(len(dep[key]), shape[1])
for n in range(shape[1]):
assert_equal(nuc_set, set(dep[key][n].comp.keys()))
elif key.endswith("_BURNUP"):
assert_equal(len(dep[key]), shape[1])
elif key.startswith("MAT_") or key.startswith("TOT_"):
assert_equal(len(dep[key]), shape[0])
assert_equal(len(dep[key][0]), shape[1])
# Check values
assert_array_equal(dep["BU"], [0.00000e00, 1.00000e-01, 1.00000e00])
assert_equal(dep["i621510"], 22)
assert_array_equal(dep["MAT_fuel_A"][6],
[0.00000e00, 1.73176e05, 4.96485e06])
def _to_id(nuc):
if not 'NN' in nuc:
nucid = nucname.id(nuc.strip())
else:
warn('Neutron data not supported!')
return 0
return nucid
def _build_matrix(N):
"""This function builds burnup matrix, A. Decay only."""
A = np.zeros((len(N), len(N)))
# convert N to id form
N_id = []
for i in range(len(N)):
if isinstance(N[i], str):
ID = nucname.id(N[i])
else:
ID = N[i]
N_id.append(ID)
sds = SimpleDataSource()
# Decay
for i in range(len(N)):
A[i, i] -= decay_const(N_id[i])
# Find decay parents
for k in range(len(N)):
if N_id[i] in decay_children(N_id[k]):
A[i,
k] += branch_ratio(N_id[k], N_id[i]) * decay_const(N_id[k])
return A
def read_row(row):
"""Returns a list of the format [int, float, float] for each nuclide.
Parameters
----------
row : tuple
One entry in a q_val file.
"""
# Create tuple
entry = ()
# Evaluate each component of the given row
if row[0] == 'Nuclide' or len(row[0].strip()) == 0:
return
nuclide = nucname.id(''.join(row[0:2]).replace(' ', ''))
if len(row[2]) == 0:
q_val = 0.0
else:
q_val = float(row[2])
if len(row[3]) == 0:
gamma_frac = 0.0
else:
gamma_frac = float(row[3])
entry = (nuclide, q_val, gamma_frac)
return entry
def test_ace_table_init():
atab = openmc.AceTable(zaid='92235', path='U235.ace',
cross_sections_path='/tmp/cross_sections.xml')
assert_equal('92235', atab.zaid)
assert_equal('U235.ace', atab.path)
assert_equal('/tmp/U235.ace', atab.abspath)
assert_equal(nucname.id('U235'), atab.nucid)
def read_row(row):
"""Returns a list of the format [int, float, float] for each nuclide.
Parameters
----------
row : list
One entry in a q_val file.
"""
# Create tuple
entry = ()
# Evaluate each component of the given row
if row[0] == 'Nuclide' or len(row[0].strip()) == 0:
return
nuclide = nucname.id(''.join(row[0:2]).replace(' ', ''))
if len(row[2]) == 0:
q_val = 0.0
else:
q_val = float(row[2])
if len(row[3]) == 0:
gamma_frac = 0.0
else:
gamma_frac = float(row[3])
entry = (nuclide, q_val, gamma_frac)
return entry
def reaction(self, nuc, rx, temp=300.0):
"""Gets the cross section data for this reaction channel either directly
from the data source or from the rxcache.
Parameters
----------
nuc : int or str
A nuclide.
rx : int or str
Reaction id or name.
temp : float, optional
Temperature [K] of material, defaults to 300.0.
Returns
-------
rxdata : ndarray
Source cross section data, length src_ngroups.
"""
nuc = nucname.id(nuc)
rx = rxname.id(rx)
rxkey = (nuc, rx, temp) if self._USES_TEMP else (nuc, rx)
if rxkey not in self.rxcache:
self.rxcache[rxkey] = None if self.fullyloaded \
else self._load_reaction(nuc, rx, temp)
return self.rxcache[rxkey]
def _load_reaction(self, nuc, rx, nuc_i, src_phi_g=None, temp=300.0):
"""Note: ENDF data does not use temperature information (temp)
Parameters
----------
nuc : int
Nuclide in id form.
rx : int or str
Reaction MT # in nnnm form.
OR:
Reaction key: 'gamma', 'alpha', 'p', etc.
nuc_i: : int
Isotope in id form (optional). Default is None.
Returns
-------
rxdata: ndarray of floats, len ngroups
"""
nuc = nucname.id(nuc)
rx = rxname.mt(rx)
if nuc_i not in self.library.structure[nuc]['data']:
self.library._read_res(nuc)
rxdict = self.library.get_xs(nuc, rx, nuc_i)[0]
rxdict['_src_phi_g'] = src_phi_g
self.rxcache[nuc, rx, nuc_i] = rxdict
self._load_group_structure(nuc, rx, nuc_i)
return rxdict
def _to_id(nuc):
if not 'NN' in nuc:
nucid = nucname.id(nuc.strip())
else:
warn('Neutron data not supported!')
return 0
return nucid
def get_rx(self, nuc, p_in, rdesc, rprop, x1=None, p_out=None):
"""get_rx(nuc, p_in, rdesc, rprop, x1=None, p_out=None)
Grab the data for one reaction type.
Parameters
----------
nuc : int
id form of nucleus to read from.
p_in : int
ENDL incident particle designator
rdesc : int
ENDL reaction descriptor
rprop : int
ENDL reaction property
x1 : int or None
ENDL atomic subshell indicator (if applicable)
yo : int or None
ENDL outgoing particle designator (if applicable)
Returns
-------
data : NumPy array
Contains the reaction data in a n-by-m-dimensional array. The
values of n and m depend on the reaction property rprop.
"""
nuc = nucname.id(nuc)
if nuc in self.structure:
return self._read_nuc_pin_rdesc_rprop(nuc, p_in, rdesc, rprop, x1,
p_out)
else:
raise ValueError('Nucleus {} does not exist.'.format(nuc))
def _copy_radio_abundances(self):
"""Copies the radioactive isotopes onto the corresponding stable
elements. This routine is intended for uses of the mapper during which
the decay is neglected
Notes
-----
Must be called after _remap_abundances.
Raises
------
AttributeError if called before _remap_abundances
"""
try:
self.radio_abundances_interp
except AttributeError:
logger.critical("Abundances must be remapped before radioactive:"
" isotopes are copied onto the stable elements")
raise AttributeError("no radio_abundances_interp; call"
" _remap_abundances first")
for ident in self.radio_abundances_interp.keys():
elemid = nucname.id(ident)
z = nucname.znum(elemid)
self.abundances_interp[z] = \
self.abundances_interp[z] + self.radio_abundances_interp[ident]
def _decay_abundances(self):
"""Determines the decay of all radioactive isotopes. Afterwards their
mass fractions are added to the stable elements.
Notes
-----
Must be called after _remap_abundances.
Raises
------
AttributeError if called before _remap_abundances
"""
try:
self.radio_abundances_interp
except AttributeError:
logger.critical("Abundances must be remapped before decay is"
" handled")
raise AttributeError("no radio_abundances_interp; call "
"_remap_abundances first")
for i in xrange(self.N_interp):
comp = {}
mass = 0
for ident in self.radio_abundances_interp.keys():
Xi = self.radio_abundances_interp[ident][i]
mass += Xi
comp[nucname.id(ident)] = Xi
inp = material.Material(comp, mass=mass)
res = inp.decay(
(self.t - self.orig.t).to("s").value).mult_by_mass()
for item in res.items():
z = nucname.znum(item[0])
self.abundances_interp[z][i] = \
self.abundances_interp[z][i] + item[1]
def test_zzzaaa_to_id():
assert_equal(nucname.zzzaaa_to_id(2004), nucname.id(20040))
assert_equal(nucname.zzzaaa_to_id(96244), nucname.id("Cm-244"))
assert_equal(nucname.zzzaaa_to_id(94239), nucname.id("PU239"))
assert_equal(nucname.zzzaaa_to_id(95242), nucname.id(95642))
# Added /10*10 to remove the state information from id (ZZZAAA carries no state
# information, defaults to zero when converting ZZZAAA back to ID)
assert_equal(nucname.zzzaaa_to_id(95242), (nucname.id(95942)//10)*10)
assert_equal(nucname.zzzaaa_to_id(95242), (nucname.id("AM-242m")//10)*10)
assert_equal(nucname.zzzaaa_to_id(2000), nucname.id("he"))
assert_equal(nucname.zzzaaa_to_id(92000), nucname.id("U"))
assert_equal(nucname.zzzaaa_to_id(93000), nucname.id("Np"))
assert_equal(nucname.zzzaaa_to_id(2004), nucname.id(40020))
def test_zzzaaa_to_id():
assert_equal(nucname.zzzaaa_to_id(2004), nucname.id(20040))
assert_equal(nucname.zzzaaa_to_id(96244), nucname.id("Cm-244"))
assert_equal(nucname.zzzaaa_to_id(94239), nucname.id("PU239"))
assert_equal(nucname.zzzaaa_to_id(95242), nucname.id(95642))
# Added /10*10 to remove the state information from id (ZZZAAA carries no state
# information, defaults to zero when converting ZZZAAA back to ID)
assert_equal(nucname.zzzaaa_to_id(95242), (nucname.id(95942) // 10) * 10)
assert_equal(nucname.zzzaaa_to_id(95242), (nucname.id("AM-242m") // 10) * 10)
assert_equal(nucname.zzzaaa_to_id(2000), nucname.id("he"))
assert_equal(nucname.zzzaaa_to_id(92000), nucname.id("U"))
assert_equal(nucname.zzzaaa_to_id(93000), nucname.id("Np"))
assert_equal(nucname.zzzaaa_to_id(2004), nucname.id(40020))
def test_ace_table_init():
atab = openmc_utils.AceTable(zaid="92235",
path="U235.ace",
cross_sections_path="/tmp/cross_sections.xml")
assert_equal("92235", atab.zaid)
assert_equal("U235.ace", atab.path)
assert_equal("/tmp/U235.ace", atab.abspath)
assert_equal(nucname.id("U235"), atab.nucid)
def parse_for_all_isotopes(htmlfile):
"""Parses an elemental html file, returning a set of all occuring isotopes."""
isos = set()
with open(htmlfile, 'r') as f:
for line in f:
m = all_iso_regex.search(line)
if m is not None:
isos.add(nucname.id(m.group(1)))
return isos
def parse_for_natural_isotopes(htmlfile):
"""Parses an elemental html file, returning a set of naturally occuring isotopes."""
nat_isos = set()
with open(htmlfile, "r") as f:
for line in f:
m = nat_iso_regex.search(line)
if m is not None:
nat_isos.add(nucname.id(m.group(1)))
return nat_isos
def parse_for_all_isotopes(htmlfile):
"""Parses an elemental html file, returning a set of all occuring isotopes."""
isos = set()
with open(htmlfile, 'r') as f:
for line in f:
m = all_iso_regex.search(line)
if m is not None:
isos.add(nucname.id(m.group(1)))
return isos
def format_nucs(nucs):
"""
format the nuclide provided by the users into a standard format:
ZZAASSSS.
Parameters
----------
nucs : of nuclides
"""
raise_no_pyne('Unable to format nuclide !', HAVE_PYNE)
return [nucname.id(nuc) for nuc in nucs]
def format_nucs(nucs):
"""
format the nuclide provided by the users into a standard format:
ZZAASSSS.
Parameters
----------
nucs : of nuclides
"""
raise_no_pyne('Unable to format nuclide !', HAVE_PYNE)
return [nucname.id(nuc) for nuc in nucs]
def _ensure_nl(self, rc):
"Validate the tracked nuclides in the run control."
if isinstance(rc.track_nucs, basestring):
track_nucs = self.load_nuc_file(rc.track_nucs)
else:
track_nucs = [nucname.id(nuc) for nuc in rc.track_nucs]
avg_timestep = 60*60*24*np.mean(rc.burn_times[1:]-rc.burn_times[:-1])
min_halflife = rc.track_nuc_threshold * avg_timestep
track_nucs = [nucid for nucid in track_nucs
if half_life(nucid) > min_halflife]
rc.track_nucs = sorted(set(track_nucs))
def discretize(self, nuc, rx, temp=300.0, src_phi_g=None, dst_phi_g=None):
"""Discretizes the reaction channel from the source group structure to that
of the destination weighted by the group fluxes.
Parameters
----------
nuc : int or str
A nuclide.
rx : int or str
Reaction id or name.
temp : float, optional
Temperature [K] of material, defaults to 300.0.
src_phi_g : array-like, optional
Group fluxes for this data source, length src_ngroups.
dst_phi_g : array-like, optional
Group fluxes for the destiniation structure, length dst_ngroups.
Returns
-------
dst_sigma : ndarray
Destination cross section data, length dst_ngroups.
"""
nuc = nucname.id(nuc)
nuc_i = nucname.id(nuc)
rx = rxname.mt(rx)
rxdata = self.reaction(nuc, rx, nuc_i=nuc_i)
xs = rxdata['xs']
dst_group_struct = rxdata['dst_group_struct']
intpoints = [intpt for intpt in rxdata['intpoints'][::-1]]
intschemes = rxdata['intschemes'][::-1]
e_int = rxdata["e_int"]
src_bounds = [e_int[intpoint - 1] for intpoint in intpoints]
src_dict = dict(zip(src_bounds, intschemes))
dst_bounds = zip(dst_group_struct[1:], dst_group_struct[:-1])
dst_sigma = [
self.integrate_dst_group(dst_bound, src_bounds, src_dict, e_int,
xs) for dst_bound in dst_bounds
]
return dst_sigma
def test_tree_log():
"Tests corret implementation of the _log_tree() function"
filename = 'log.txt'
tm.log = open(filename, 'w')
d0 = 0
d1 = 1
d2 = 2
d11 = 1
d20 = 0
nuc0 = nn.id('O16')
nuc1 = nn.id('O17')
nuc2 = nn.id('O18')
nuc11 = nn.id('He4')
nuc20 = nn.id('C12')
N0 = 123.456
N1 = 12.3456
N2 = 1.23456
N11 = 1111.
N20 = 12.
exp = ('--> O16 123.456\n'
' |--> O17 12.3456\n'
' | |--> O18 1.23456\n'
' |--> He4 1111.0\n'
'--> C12 12.0\n')
with open(filename, 'w') as tree:
tm._log_tree(d0, nuc0, N0)
tm._log_tree(d1, nuc1, N1)
tm._log_tree(d2, nuc2, N2)
tm._log_tree(d11, nuc11, N11)
tm._log_tree(d20, nuc20, N20)
tm.log.close()
tm.log = None
with open(filename, 'r') as f:
obs = f.read()
#print repr(exp)
#print repr(obs)
#print obs == exp
assert_equal(exp, obs)
def discretize(self, nuc, rx, temp=300.0, src_phi_g=None, dst_phi_g=None):
"""Discretizes the reaction channel from the source group structure to that
of the destination weighted by the group fluxes.
Parameters
----------
nuc : int or str
A nuclide.
rx : int or str
Reaction id or name.
temp : float, optional
Temperature [K] of material, defaults to 300.0.
src_phi_g : array-like, optional
Group fluxes for this data source, length src_ngroups.
dst_phi_g : array-like, optional
Group fluxes for the destiniation structure, length dst_ngroups.
Returns
-------
dst_sigma : ndarray
Destination cross section data, length dst_ngroups.
"""
nuc = nucname.id(nuc)
nuc_i = nucname.id(nuc)
rx = rxname.mt(rx)
rxdata = self.reaction(nuc, rx, nuc_i = nuc_i)
xs = rxdata['xs']
dst_group_struct = rxdata['dst_group_struct']
intpoints = [intpt for intpt in rxdata['intpoints'][::-1]]
intschemes = rxdata['intschemes'][::-1]
e_int = rxdata["e_int"]
src_bounds = [e_int[intpoint-1] for intpoint in intpoints]
src_dict = dict(zip(src_bounds, intschemes))
dst_bounds = zip(dst_group_struct[1:], dst_group_struct[:-1])
dst_sigma = [self.integrate_dst_group(dst_bound, src_bounds, src_dict, e_int, xs)
for dst_bound in dst_bounds]
return dst_sigma
def test_tree_log():
"Tests corret implementation of the _log_tree() function"
filename = 'log.txt'
tm.log = open(filename, 'w')
d0 = 0
d1 = 1
d2 = 2
d11 = 1
d20 = 0
nuc0 = nn.id('O16')
nuc1 = nn.id('O17')
nuc2 = nn.id('O18')
nuc11 = nn.id('He4')
nuc20 = nn.id('C12')
N0 = 123.456
N1 = 12.3456
N2 = 1.23456
N11 = 1111.
N20 = 12.
exp = ('--> O16 123.456\n'
' |--> O17 12.3456\n'
' | |--> O18 1.23456\n'
' |--> He4 1111.0\n'
'--> C12 12.0\n')
with open(filename, 'w') as tree:
tm._log_tree(d0, nuc0, N0)
tm._log_tree(d1, nuc1, N1)
tm._log_tree(d2, nuc2, N2)
tm._log_tree(d11, nuc11, N11)
tm._log_tree(d20, nuc20, N20)
tm.log.close()
tm.log = None
with open(filename, 'r') as f:
obs = f.read()
#print repr(exp)
#print repr(obs)
#print obs == exp
assert_equal(exp, obs)
def test_tree_log():
"Tests corret implementation of the _log_tree() function"
filename = "log.txt"
tm.log = open(filename, "w")
d0 = 0
d1 = 1
d2 = 2
d11 = 1
d20 = 0
nuc0 = nn.id("O16")
nuc1 = nn.id("O17")
nuc2 = nn.id("O18")
nuc11 = nn.id("He4")
nuc20 = nn.id("C12")
N0 = 123.456
N1 = 12.3456
N2 = 1.23456
N11 = 1111.0
N20 = 12.0
exp = ("--> O16 123.456\n"
" |--> O17 12.3456\n"
" | |--> O18 1.23456\n"
" |--> He4 1111.0\n"
"--> C12 12.0\n")
with open(filename, "w") as tree:
tm._log_tree(d0, nuc0, N0)
tm._log_tree(d1, nuc1, N1)
tm._log_tree(d2, nuc2, N2)
tm._log_tree(d11, nuc11, N11)
tm._log_tree(d20, nuc20, N20)
tm.log.close()
tm.log = None
with open(filename, "r") as f:
obs = f.read()
# print repr(exp)
# print repr(obs)
# print obs == exp
assert_equal(exp, obs)
def read_row(row):
"""Returns a list for each nuclide. Form varies based on type of dose rate factor:
1. External DF in Air: [int, float, float]
2. External DF in Soil: [int, float, float, float]
3. Ingestion DF: [int, float, float, float, float]
4. Inhalation DF: [int, string, float, float, float]
Parameters
----------
row : tuple
One entry in a dose factor file.
"""
# Create list
entry = []
# Evaluate each component of the given row
if row[0].endswith("+D"):
row[0] = row[0][:-2]
nuclide = nucname.id(row[0])
# Case 1: DF from External Air
if len(row) == 3:
dose_air = float(row[1])
if len(row[2]) == 0:
ratio = None
else:
ratio = float(row[2])
entry = [nuclide, dose_air, ratio]
# Case 2: DF from External Soil
elif len(row) == 6:
genii = float(row[1])
epa = float(row[2])
doe = float(row[3])
entry = [nuclide, genii, epa, doe]
# Case 4: DF from Inhalation
elif len(row) == 7 and row[1].isalpha():
lungmodel = row[1]
genii = float(row[2])
epa = float(row[3])
doe = float(row[4])
entry = [nuclide, genii, epa, doe, lungmodel]
# Case 4: DF from Ingestion
else:
f1 = float(row[1])
genii = float(row[2])
epa = float(row[3])
doe = float(row[4])
entry = [nuclide, genii, epa, doe, f1]
return entry
def read_row(row):
"""Returns a list for each nuclide. Form varies based on type of dose rate factor:
1. External DF in Air: [int, float, float]
2. External DF in Soil: [int, float, float, float]
3. Ingestion DF: [int, float, float, float, float]
4. Inhalation DF: [int, string, float, float, float]
Parameters
----------
row : tuple
One entry in a dose factor file.
"""
# Create list
entry = []
# Evaluate each component of the given row
if row[0].endswith('+D'):
row[0] = row[0][:-2]
nuclide = nucname.id(row[0])
# Case 1: DF from External Air
if len(row) == 3:
dose_air = float(row[1])
if len(row[2]) == 0:
ratio = None
else:
ratio = float(row[2])
entry = [nuclide, dose_air, ratio]
# Case 2: DF from External Soil
elif len(row) == 6:
genii = float(row[1])
epa = float(row[2])
doe = float(row[3])
entry = [nuclide, genii, epa, doe]
# Case 4: DF from Inhalation
elif len(row) == 7 and row[1].isalpha():
lungmodel = row[1]
genii = float(row[2])
epa = float(row[3])
doe = float(row[4])
entry = [nuclide, genii, epa, doe, lungmodel]
# Case 4: DF from Ingestion
else:
f1 = float(row[1])
genii = float(row[2])
epa = float(row[3])
doe = float(row[4])
entry = [nuclide, genii, epa, doe, f1]
return entry
def load_nuc_file(self, path):
"""Load list nucs from a file. Should be a file containing just a Python list.
Parameters
----------
path : str
The path to the nuc file.
Returns
-------
nucs : list of ints
The nuclides listed in the file, in nuc ID form.
"""
with open(path, 'r') as f:
text = f.read()
if text[0] == "[" and text[-1] == "]":
nucs = exec(text)
nucs = [nucname.id(nuc) for nuc in nucs]
return nucs
def test_parse_dep1():
dep = serpent.parse_dep("sample_dep.m")
nuc_set = set([nucname.id(int(nuc)) for nuc in dep["ZAI"][:-2]])
shape = (len(dep["ZAI"]), len(dep["DAYS"]))
for key in dep:
if key.endswith("_VOLUME"):
assert_true(isinstance(dep[key], float))
elif key.endswith("_MATERIAL"):
assert_equal(len(dep[key]), shape[1])
for n in range(shape[1]):
assert_equal(nuc_set, set(dep[key][n].comp.keys()))
elif key.startswith("MAT_") and key.endswith("_BURNUP"):
assert_equal(dep[key].shape, (1, shape[1]))
elif key.startswith("MAT_") or key.startswith("TOT_"):
assert_equal(dep[key].shape, shape)
# Check values
assert_array_equal(dep["BU"], [0.00000e00, 8.40000e01, 1.68000e02])
assert_equal(dep["i952421"], 123)
assert_array_equal(dep["MAT_fuelp1r2_H"][3], [0.00000e00, 5.56191e-11, 3.22483e-10])
def _build_matrix(N):
""" This function builds burnup matrix, A. Decay only.
"""
A = np.zeros((len(N), len(N)))
# convert N to id form
N_id = []
for i in xrange(len(N)):
ID = id(N[i])
N_id.append(ID)
sds = SimpleDataSource()
# Decay
for i in xrange(len(N)):
A[i, i] -= decay_const(N_id[i])
# Find decay parents
for k in xrange(len(N)):
if N_id[i] in decay_children(N_id[k]):
A[k, i] += decay_const(N_id[k])
return A
def conv_to_id(nuc):
"""Converts html nuclide names to nuclide ids
"""
parts = nuc.split('-')
return nucname.id(parts[1] + parts[2])
def gendecay(decays, branches, metastable_cutoff=1.0):
"""This computes ORIGEN TAPE9 decay data based on ENSDF data.
Parameters
----------
decays : list
decay list from parse_ensdf()
branches : list
branches list from parse_ensdf()
metastable_cutoff : float, optional
minimum lifetime of metastable state (in seconds) to be included.
Returns
-------
t9 : dict
a TAPE9 dictionary for the decay library
"""
t9 = {1: {'_type': 'decay', 'title': 'PyNE Decay Data for Activation Products'},
2: {'_type': 'decay', 'title': 'PyNE Decay Data for Actinides & Daughters'},
3: {'_type': 'decay', 'title': 'PyNE Decay Data for Fission Products'},
}
for nlb, lib in t9.items():
for field in origen22.DECAY_FIELDS:
lib[field] = {}
longest = {}
longest2 = {}
for item in decays:
nuc = nucname.id(item[0])
key = nucname.zzaaam(nuc)
if _is_metastable_beta_decay_0(item, metastable_cutoff):
if 'B-' in item[5]:
_plus_eq_decay_t9(t9, 'frac_beta_minus_x', nuc, key, item[6]/100.0)
if 'B+' in item[5] or "EC" in item[5]:
_plus_eq_decay_t9(t9, 'frac_beta_plus_or_electron_capture_x', nuc,
key, item[6]/100.0)
if _is_metastable_beta_decay_x(item, metastable_cutoff):
key += 1
longest2[key] = longest2.get(key, 0)
if item[1] == longest2[key]:
if 'B-' in item[5]:
_plus_eq_decay_t9(t9, 'frac_beta_minus_x', nuc, key,
item[6]/100.0)
#item[6]*item[8]/100.0)
if 'B+' in item[5] or "EC" in item[5]:
_plus_eq_decay_t9(t9, 'frac_beta_plus_or_electron_capture_x', nuc,
key, item[6]/100.0)
#key, item[6]*item[8]/100.0)
elif item[1] > longest2[key]:
longest2[key] = item[1]
if 'B-' in item[5]:
#_eq_decay_t9(t9, 'frac_beta_minus_x', nuc, key, item[6]*item[8]/100.0)
_eq_decay_t9(t9, 'frac_beta_minus_x', nuc, key, item[6]/100.0)
if 'B+' in item[5] or "EC" in item[5]:
_eq_decay_t9(t9, 'frac_beta_plus_or_electron_capture_x', nuc,
key, item[6]/100.0)
#key, item[6]*item[8]/100.0)
for item in branches:
nuc = nucname.id(item[0])
key = nucname.zzaaam(nuc)
if (item[1] == 0) and (item[2] > metastable_cutoff):
_set_branch_item(t9, nuc, key, item)
if (item[1] != 0) and (item[2] > metastable_cutoff):
key += 1
longest[key] = longest.get(key, 0)
if (item[2] <= longest[key]):
continue
_set_branch_item(t9, nuc, key, item)
for nucs, hl in zip([origen22.ACTIVATION_PRODUCT_NUCS,
origen22.ACTINIDE_AND_DAUGHTER_NUCS,
origen22.FISSION_PRODUCT_NUCS],
[t9[i]['half_life'] for i in range(1, 4)]):
for nuc in nucs:
key = nucname.zzaaam(nuc)
if key not in hl:
hl[key] = data.half_life(nuc)
return t9
import os
import shutil
from pyne import nucname
dirname = "JENDL-AN-2005-linux-patched"
zaiddirname = dirname + "-ZAID/"
if not os.path.exists(zaiddirname):
os.makedirs(zaiddirname)
files = [ f for f in os.listdir(dirname) if (os.path.isfile(os.path.join(dirname,f)) & f.endswith(".dat")) ]
for file in files:
nucid = nucname.id(os.path.splitext(file)[0])
zaid = nucname.zzzaaa(nucid)
zaidfile = str(zaid) + ".dat"
shutil.copyfile(os.path.join(dirname , file), os.path.join(zaiddirname, zaidfile ))
def test_id():
assert_equal(nucname.id(20040), 20040000)
assert_equal(nucname.id("he4"), 20040000)
assert_equal(nucname.id("Cm-244"), 962440000)
assert_equal(nucname.id("PU239"), 942390000)
assert_equal(nucname.id("AM242M"), 952420001)
assert_equal(nucname.id(2004), 20040000)
assert_equal(nucname.id(95642), 952420000)
assert_equal(nucname.id(95242), 952420001)
assert_equal(nucname.id(92636), 922360001)
assert_equal(nucname.id(95942), 952420004)
assert_equal(nucname.id("Am-242m"), 952420001)
assert_equal(nucname.id("he"), 20000000)
assert_equal(nucname.id("U"), 920000000)
assert_equal(nucname.id("Np"), 930000000)
assert_equal(nucname.id("Cl"), 170000000)
assert_equal(nucname.id("4he"), 20040000)
assert_equal(nucname.id("244CM"), 962440000)
assert_equal(nucname.id("239Pu"), 942390000)
assert_equal(nucname.id("242AM"), 952420000)
assert_equal(nucname.id(40020), 20040000)
assert_equal(nucname.id(2440961), 962440001)
assert_equal(nucname.id(2390940), 942390000)
assert_equal(nucname.id(2420950), 952420000)
assert_equal(nucname.id(92), 920000000)
assert_equal(nucname.id("94-Pu-239"), nucname.id("Pu-239"))
assert_equal(nucname.id("95-Am-242m"), nucname.id("Am-242m"))
assert_equal(nucname.id("94-Pu-239"), nucname.id("Pu-239"))
assert_equal(nucname.id("95-Am-242"), nucname.id("Am-242"))
def _ensure_mats(self, rc):
"Ensure we have a fuel material, clad material, and cooling material."
if 'fuel_material'in rc:
rc.fuel_material = ensure_mat(rc.fuel_material)
elif 'fuel_chemical_form' in rc and 'initial_heavy_metal' in rc:
ihm_mat = Material(rc.initial_heavy_metal)
atom_frac = {nucname.id(k): v for k, v in
rc.fuel_chemical_form.items() if k != "IHM"}
atom_frac[ihm_mat] = rc.fuel_chemical_form.get("IHM", 0.0)
rc.fuel_material = from_atom_frac(atom_frac)
else:
raise ValueError("Please specify a fuel.")
if 'clad_material' in rc:
rc.clad_material = ensure_mat(rc.clad_material)
else:
rc.clad_material = Material({
# Natural Zirconium
400900: 0.98135 * 0.5145,
400910: 0.98135 * 0.1122,
400920: 0.98135 * 0.1715,
400940: 0.98135 * 0.1738,
400960: 0.98135 * 0.0280,
# The plastic is all melted and the natural Chromium too..
240500: 0.00100 * 0.04345,
240520: 0.00100 * 0.83789,
240530: 0.00100 * 0.09501,
240540: 0.00100 * 0.02365,
# Natural Iron
260540: 0.00135 * 0.05845,
260560: 0.00135 * 0.91754,
260570: 0.00135 * 0.02119,
260580: 0.00135 * 0.00282,
# Natural Nickel
280580: 0.00055 * 0.68077,
280600: 0.00055 * 0.26223,
280610: 0.00055 * 0.01140,
280620: 0.00055 * 0.03634,
280640: 0.00055 * 0.00926,
# Natural Tin
501120: 0.01450 * 0.0097,
501140: 0.01450 * 0.0065,
501150: 0.01450 * 0.0034,
501160: 0.01450 * 0.1454,
501170: 0.01450 * 0.0768,
501180: 0.01450 * 0.2422,
501190: 0.01450 * 0.0858,
501200: 0.01450 * 0.3259,
501220: 0.01450 * 0.0463,
501240: 0.01450 * 0.0579,
# We Need Oxygen!
80160: 0.00125,
})
if 'cool_material' in rc:
rc.cool_material = ensure_mat(rc.cool_material)
else:
MW = (2 * 1.0) + (1 * 16.0) + (0.199 * 550 * 10.0**-6 * 10.0) + \
(0.801 * 550 * 10.0**-6 * 11.0)
rc.cool_material = Material({
10010: (2 * 1.0) / MW,
80160: (1 * 16.0) / MW,
50100: (0.199 * 550 * 10.0**-6 * 10.0) / MW,
50110: (0.801 * 550 * 10.0**-6 * 11.0) / MW,
})