def __init__(self, t=0.0, phi=0.0, temp=300.0, tol=1e-7, cwd='',
base_tape9=origen22.BASE_TAPE9, xscache=None,
o2exe='o2_therm_linux.exe', *args, **kwargs):
"""Parameters
----------
t : float
Transmutations time [sec].
phi : float or array of floats
Neutron flux vector [n/cm^2/sec]. Currently this must either be
a scalar or match the group structure of EAF.
temp : float, optional
Temperature [K] of material, defaults to 300.0.
tol : float
Tolerance level for chain truncation.
cwd : str, optional
Current working directory for origen runs. Defaults to this dir.
base_tape9 : str or dict, optional
A base TAPE9.INP file. If this is a str it is interpreted as a path
to a file, which is then read in and parsed. If this is a dict, it is
assumed to be in the format described in the main origen22 module.
xscache : XSCache, optional
A cross section cache to generate cross sections with.
o2exe : str, optional
Name or path to ORIGEN 2.2 executable.
args : tuple, optional
Other arguments ignored for compatibility with other Transmuters.
kwargs : dict, optional
Other keyword arguments ignored for compatibility with other Transmuters.
"""
if not isinstance(base_tape9, Mapping):
base_tape9 = origen22.parse_tape9(tape9=base_tape9)
self.base_tape9 = base_tape9
if xscache is None:
eafds = EAFDataSource()
eafds.load(temp=temp)
gs = np.array([eafds.src_group_struct[0], eafds.src_group_struct[-1]])
eafds.dst_group_struct = gs
xscache = XSCache(group_struct=gs, data_source_classes=[SimpleDataSource,
NullDataSource])
xscache.load(temp=temp)
xscache.data_sources.insert(0, eafds)
self.xscache = xscache
self.t = t
self._phi = None
self.phi = phi
self.temp = temp
self.tol = tol
self.cwd = os.path.abspath(cwd)
self.o2exe = o2exe
def __init__(self, t=0.0, phi=0.0, temp=300.0, tol=1e-7, cwd='',
base_tape9=origen22.BASE_TAPE9, xscache=None,
o2exe='o2_therm_linux.exe', *args, **kwargs):
"""Parameters
----------
t : float
Transmutations time [sec].
phi : float or array of floats
Neutron flux vector [n/cm^2/sec]. Currently this must either be
a scalar or match the group structure of EAF.
temp : float, optional
Temperature [K] of material, defaults to 300.0.
tol : float
Tolerance level for chain truncation.
cwd : str, optional
Current working directory for origen runs. Defaults to this dir.
base_tape9 : str or dict, optional
A base TAPE9.INP file. If this is a str it is interpreted as a path
to a file, which is then read in and parsed. If this is a dict, it is
assumed to be in the format described in the main origen22 module.
xscache : XSCache, optional
A cross section cache to generate cross sections with.
o2exe : str, optional
Name or path to ORIGEN 2.2 executable.
args : tuple, optional
Other arguments ignored for compatibility with other Transmuters.
kwargs : dict, optional
Other keyword arguments ignored for compatibility with other Transmuters.
"""
if not isinstance(base_tape9, Mapping):
base_tape9 = origen22.parse_tape9(tape9=base_tape9)
self.base_tape9 = base_tape9
if xscache is None:
eafds = EAFDataSource()
eafds.load(temp=temp)
gs = np.array([eafds.src_group_struct[0], eafds.src_group_struct[-1]])
eafds.dst_group_struct = gs
xscache = XSCache(group_struct=gs, data_source_classes=[SimpleDataSource,
NullDataSource])
xscache.load(temp=temp)
xscache.data_sources.insert(0, eafds)
self.xscache = xscache
self.t = t
self._phi = None
self.phi = phi
self.temp = temp
self.tol = tol
self.cwd = os.path.abspath(cwd)
self.o2exe = o2exe
def __init__(self, rc):
self.rc = rc
self.statelibs = {}
self.builddir = 'build-' + rc.reactor
if not os.path.isdir(self.builddir):
os.makedirs(self.builddir)
self.eafds = data_source.EAFDataSource()
self.omcds = data_source.OpenMCDataSource(
cross_sections=rc.openmc_cross_sections,
src_group_struct=rc.openmc_group_struct)
data_sources = [self.omcds]
if not rc.is_thermal:
data_sources.append(self.eafds)
data_sources += [data_source.SimpleDataSource(),
data_source.NullDataSource()]
for ds in data_sources[:]:
ds.load(rc.temperature)
self.xscache = XSCache(data_sources=data_sources, scalars={922380000: 1.05})
self.xscache.load()
self.tape9 = None
if self.rc.origen_call is NotSpecified:
if self.rc.is_thermal:
self.origen_call = "o2_therm_linux.exe"
else:
self.origen_call = "o2_fast_linux.exe"
else:
self.origen_call = self.rc.origen_call
def __init__(self,
t=0.0,
phi=0.0,
temp=300.0,
tol=1e-7,
rxs=None,
log=None,
*args,
**kwargs):
"""Parameters
----------
t : float
Transmutations time [sec].
phi : float or array of floats
Neutron flux vector [n/cm^2/sec]. Currently this must either be
a scalar or match the group structure of EAF.
temp : float, optional
Temperature [K] of material, defaults to 300.0.
tol : float
Tolerance level for chain truncation.
rxs : set of ints or strs
Reaction ids or names to use in transmutation which produce well-defined
children. This set should thus not include fission. If None, then the
reactions from EAF are used.
log : file-like or None
The log file object should be written. A None imples the log is
not desired.
args : tuple, optional
Other arguments ignored for compatibility with other Transmuters.
kwargs : dict, optional
Other keyword arguments ignored for compatibility with other Transmuters.
"""
eafds = EAFDataSource()
eafds.load(temp=temp)
gs = np.array([eafds.src_group_struct[0], eafds.src_group_struct[-1]])
eafds.dst_group_struct = gs
self.xscache = XSCache(group_struct=gs,
data_source_classes=(NullDataSource, ))
self.xscache.data_sources.insert(0, eafds)
self.t = t
self._phi = None
self.phi = phi
self.temp = temp
self.log = log
self.tol = tol
if rxs is None:
rxs = [
'gamma', 'gamma_1', 'gamma_2', 'p', 'p_1', 'p_2', 'd', 'd_1',
'd_2', 't', 't_1', 't_2', 'He3', 'He3_1', 'He3_2', 'a', 'a_1',
'a_2', 'z_2a', 'z_2p', 'z_2p_1', 'z_2p_2', 'z_2n', 'z_2n_1',
'z_2n_2', 'z_3n', 'z_3n_1', 'z_3n_2', 'na', 'na_1', 'na_2',
'z_2na', 'np', 'np_1', 'np_2', 'n2a', 'nd', 'nd_1', 'nd_2',
'nt', 'nt_1', 'nt_2', 'nHe3', 'nHe3_1', 'nHe3_2', 'z_4n',
'z_4n_1', 'n', 'n_1', 'n_2', 'z_3np'
]
rxs = set([rxname.id(rx) for rx in rxs])
rxs.discard(rxname.id('fission'))
self.rxs = rxs
def main_gen(ns):
"""Generates an open TAPE9.INP file. by default this only uses completely open
data.
"""
files = glob(os.path.join(ns.build_dir, 'ENSDF', 'ensdf.*'))
if len(files) == 0:
grab_ensdf_decay(ns.build_dir)
files = glob(os.path.join(ns.build_dir, 'ENSDF', 'ensdf.*'))
print("parsing ENSDF decay data")
decays, branches = parse_ensdf(files)
print("creating ORIGEN decay libraries")
t9decay = gendecay(decays, branches, metastable_cutoff=ns.metastable_cutoff)
print("creating ORIGEN cross section libraries")
xsc = XSCache(data_source_classes=[EAFDataSource, SimpleDataSource,
NullDataSource])
xsc.load()
t9xsfpy = origen22.xslibs(xscache=xsc, verbose=True)
t9 = origen22.merge_tape9([t9decay, t9xsfpy])
origen22.write_tape9(t9, outfile=ns.filename)
def main_gen(ns):
"""Generates an open TAPE9.INP file. by default this only uses completely open
data.
"""
files = glob(os.path.join(ns.build_dir, 'ENSDF', 'ensdf.*'))
if len(files) == 0:
grab_ensdf_decay(ns.build_dir)
files = glob(os.path.join(ns.build_dir, 'ENSDF', 'ensdf.*'))
print("parsing ENSDF decay data")
decays, branches = parse_ensdf(files)
print("creating ORIGEN decay libraries")
t9decay = gendecay(decays,
branches,
metastable_cutoff=ns.metastable_cutoff)
print("creating ORIGEN cross section libraries")
xsc = XSCache(
data_source_classes=[EAFDataSource, SimpleDataSource, NullDataSource])
xsc.load()
t9xsfpy = origen22.xslibs(xscache=xsc, verbose=True)
t9 = origen22.merge_tape9([t9decay, t9xsfpy])
origen22.write_tape9(t9, outfile=ns.filename)
def test_xslibs():
exp = {
42: {
"_type": "xsfpy",
"_subtype": "activation_products",
"title": "PyNE Cross Section Data for Activation Products",
},
43: {
"_type": "xsfpy",
"_subtype": "actinides",
"title": "PyNE Cross Section Data for Actinides & Daughters",
},
44: {
"_type": "xsfpy",
"_subtype": "fission_products",
"title": "PyNE Cross Section Data for Fission Products",
},
}
xsc = XSCache(data_sources=[NullDataSource])
nucs = [922350000, 10010000, 461080000]
obs = origen22.xslibs(nucs=nucs, xscache=xsc, nlb=(42, 43, 44))
obs_meta = {}
for n in exp:
obs_meta[n] = {}
for field in ["_type", "_subtype", "title"]:
obs_meta[n][field] = obs[n][field]
assert_equal(exp, obs_meta)
for n in exp:
for field in obs[n]:
if not field.startswith("sigma_"):
continue
assert_true(all([v == 0.0 for v in obs[n][field].values()]))
assert_true(
set(obs[42].keys())
>= set(origen22.ACTIVATION_PRODUCT_FIELDS + origen22.XSFPY_FIELDS)
)
assert_true(
set(obs[43].keys()) >= set(origen22.ACTINIDE_FIELDS + origen22.XSFPY_FIELDS)
)
assert_true(
set(obs[44].keys())
>= set(origen22.FISSION_PRODUCT_FIELDS + origen22.XSFPY_FIELDS)
)
class OpenMCOrigen(object):
"""An that combines OpenMC for k-code calculations and ORIGEN for
transmutation.
"""
reactions = {rxname.id(_) for _ in ('total', 'absorption', 'gamma', 'gamma_1',
'z_2n', 'z_2n_1', 'z_3n', 'proton', 'alpha', 'fission')}
def __init__(self, rc):
self.rc = rc
self.statelibs = {}
self.builddir = 'build-' + rc.reactor
if not os.path.isdir(self.builddir):
os.makedirs(self.builddir)
self.eafds = data_source.EAFDataSource()
self.omcds = data_source.OpenMCDataSource(
cross_sections=rc.openmc_cross_sections,
src_group_struct=rc.openmc_group_struct)
data_sources = [self.omcds]
if not rc.is_thermal:
data_sources.append(self.eafds)
data_sources += [data_source.SimpleDataSource(),
data_source.NullDataSource()]
for ds in data_sources[:]:
ds.load(rc.temperature)
self.xscache = XSCache(data_sources=data_sources, scalars={922380000: 1.05})
self.xscache.load()
self.tape9 = None
if self.rc.origen_call is NotSpecified:
if self.rc.is_thermal:
self.origen_call = "o2_therm_linux.exe"
else:
self.origen_call = "o2_fast_linux.exe"
else:
self.origen_call = self.rc.origen_call
def pwd(self, state, directory):
"""Path to directory we will be running specific physics codes in.
Parameters
----------
state : namedtuple (State)
The state we are running physics codes for.
directory : string
The name of the sub-directory we would like.
Returns
-------
str
The path to the desired directory.
"""
return os.path.join(self.builddir, str(hash(state)), directory)
def context(self, state):
"""Unite parameters in the run-control file and the current state.
Parameters
----------
state : namedtuple (State)
A State tuple that contains perturbation parameters specific to that
state.
Returns
-------
ctx : dict
A dictionary with all relevant perturbation parameters.
"""
rc = self.rc
ctx = dict(rc._dict)
ctx.update(zip(rc.perturbation_params, state))
return ctx
def generate_run(self, run, fname):
"""Generate transmutation tables, neutron production/destruction rates, and
burnup statistics for a sequence of states with the same initial
conditions.
Parameters
----------
run : list of States
A list of States that has the same initial conditions at increasing
burnup times.
Returns
-------
libs : list of dicts
Libraries to write out - one for the full fuel and one for each tracked nuclide.
"""
self.libs = {'xs': [], 'phi_g': {
'E_g': {'EAF': self.eafds.src_group_struct,
'OpenMC': self.omcds.src_group_struct},
'phi_g': []},
"fuel": {
"TIME": [0],
"NEUT_PROD": [0],
"NEUT_DEST": [0],
"BUd": [0],
"material": [self.rc.fuel_material],
"tracked_nucs": {nucname.name(n): [self.rc.fuel_material.comp.get(n, 0) * 1000]
for n in self.rc.track_nucs},
"phi_tot": [0]
}}
for nuc in self.rc.track_nucs:
self.libs[nuc] = {
"TIME": [0],
"NEUT_PROD": [0],
"NEUT_DEST": [0],
"BUd": [0],
"material": [Material({nuc: 1}, 1000)],
"tracked_nucs": {nucname.name(n): [0]
for n in self.rc.track_nucs},
"phi_tot": [0]
}
self.libs[nuc]["tracked_nucs"][nucname.name(nuc)] = [1000]
print([state.burn_times for state in run])
for i, state in enumerate(run):
if i > 0:
transmute_time = state.burn_times - run[i-1].burn_times
results = self.generate(state, transmute_time)
self.libs = self._update_libs_with_results(self.libs, results)
self.rc.writers[0].write(self.libs, fname)
return self.libs
def _update_libs_with_results(self, matlibs, newlibs):
"""Update a set of libraries with results from a single timestep in-place.
Parameters
----------
matlibs : dict
A set of libraries with nuclides as keys.
newlibs: dict
A set of libraries for a single timestep, with nuclides as keys.
Returns
-------
libs : dict
The updated library.
"""
for mat, newlib in newlibs.items():
if mat == 'xs':
matlibs[mat].append(newlib)
continue
elif mat == 'phi_g':
matlibs[mat][mat].append(newlib)
continue
oldlib = matlibs[mat]
for nuc in self.rc.track_nucs:
name = nucname.name(nuc)
nuc_frac = newlib["material"].comp.get(nuc, 0)
mass = newlib["material"].mass
oldlib["tracked_nucs"][name].append(nuc_frac * mass)
for key, value in newlib.items():
if isinstance(key, int):
continue
else:
oldlib[key].append(value)
return matlibs
def generate(self, state, transmute_time):
"""Runs physics codes on a specific state. First runs OpenMC for transport,
then uses the results to run ORIGEN for a single timestep.
Parameters
----------
state : namedtuple (State)
A namedtuple containing the state parameters.
transmute_time : float
The length of the time step we would like to run ORIGEN for.
Returns
-------
results : dict
Dict of physics code results. Keys are either nuclide ID's or "fuel"
for the full fuel results.
"""
print("generating for a state with transmute_time {}".format(transmute_time))
if state in self.statelibs:
return self.statelibs[state]
rc = self.rc
k, phi_g, xstab = self.openmc(state)
results = {"fuel": {}}
results.update(dict(zip(rc.track_nucs, [{} for _ in rc.track_nucs])))
if 'flux' in rc:
phi_tot = state.flux
elif 'fuel_specific_power' in rc:
G = len(phi_g)
fission_id = rxname.id("fission")
if G == 1:
fission_xs = {xs[0]: xs[2] * 1e-24 for xs in xstab # xs is in barns not cm2
if xs[1] == fission_id}
else:
fission_xs = {xs[0]: np.sum(xs[2]) * 1e-24 / len(xs[2])
for xs in xstab # xs is in barns not cm2
if xs[1] == fission_id}
fuel_material = self.libs["fuel"]["material"][-1]
fuel_material.atoms_per_molecule = sum([self.rc.fuel_chemical_form[m]
for m in self.rc.fuel_chemical_form])
fuel_atom_frac = fuel_material.to_atom_frac()
fuel_number_density = 6.022e23 * self.rc.fuel_density / \
(fuel_material.molecular_mass() * fuel_material.atoms_per_molecule)
number_densities = {nuc: fuel_atom_frac[nuc] * fuel_number_density
for nuc in fuel_material.comp}
sum_N_i_sig_fi = sum([number_densities[nuc] * fission_xs.get(nuc, 0)
for nuc in fuel_material.comp])
sum_N_i_sig_fi = sum_N_i_sig_fi[sum_N_i_sig_fi != 0]
fuel_specific_power_mwcc = self.rc.fuel_density * 1e-6 * state.fuel_specific_power
# see http://iriaxp.iri.tudelft.nl/~leege/SCALE44/origens.PDF for formula
# (search for "the specific power due to fission", on p. 22 of the PDF)
phi_tot = sum(3.125e16*fuel_specific_power_mwcc/sum_N_i_sig_fi)
results = self.run_all_the_origens(state, transmute_time, phi_tot, results)
results['xs'] = xstab
results['phi_g'] = {'EAF': self.eafds.src_phi_g,
'OpenMC': self.omcds.src_phi_g}
self.statelibs[state] = results
statedir = os.path.join(self.builddir, str(hash(state)))
for dir in os.listdir(self.builddir):
if(os.path.join(self.builddir, dir) != statedir):
shutil.rmtree(os.path.join(self.builddir, dir))
return results
def run_all_the_origens(self, state, transmute_time, phi_tot, results):
"""Call ORIGEN as much as necessary and unite the results.
Parameters
----------
state : namedtuple (State)
A namedtuple containing the state parameters.
transmute_time : float
The length of the transmutation timestep. Has units of [days].
phi_tot : float
The total neutron flux.
results : dict
A dict with material identifiers as keys, and dictionaries as
values. The basic data structure to fill.
Returns
-------
dict
A dict of all the ORIGEN results.
"""
if self.rc.verbose:
print("making tape9 for {0} with phi={1}".format(state, phi_tot))
mat = self.libs['fuel']['material'][-1]
mat.density = self.rc.fuel_density
mat.atoms_per_molecule = 3.0
atom_dens = mat.to_atom_dens()
for ds in self.xscache.data_sources:
ds.atom_dens = atom_dens
self.tape9 = origen22.make_tape9(self.rc.track_nucs, self.xscache, nlb=(219, 220, 221))
self.tape9 = origen22.merge_tape9((self.tape9,
origen22.loads_tape9(brightlitetape9)))
origen22.write_tape9(self.tape9)
for mat_id in results.keys():
pwd = self.pwd(state, "origen{}".format(mat_id))
mat = self.libs[mat_id]["material"][-1]
if not os.path.isdir(pwd):
os.makedirs(pwd)
with indir(pwd):
if not os.path.isfile("TAPE6.OUT"):
self._make_origen_input(transmute_time, phi_tot, mat)
origen_results = []
if self.rc.threads == 1:
for mat_id in results.keys():
pwd = self.pwd(state, "origen{}".format(mat_id))
origen_params = (state.burn_times,
transmute_time,
phi_tot,
mat_id,
self.libs[mat_id]["material"][-1],
pwd,
self.origen_call)
origen_results.append(_origen(origen_params))
else:
origen_params_ls = [(state.burn_times,
transmute_time,
phi_tot,
mat_id,
self.libs[mat_id]["material"][-1],
self.pwd(state, "origen{}".format(mat_id)),
self.origen_call)
for mat_id in results]
pool = Pool(self.rc.threads)
origen_results = pool.map(_origen, origen_params_ls)
pool.close()
pool.join()
for result in origen_results:
result[1]["material"] = Material(dict(result[1]["material"]),
1000,
attrs={"units": "g"})
return dict(origen_results)
def openmc(self, state):
"""Runs OpenMC for a given state.
Parameters
----------
state : namedtuple (State)
A namedtuple containing the state parameters.
Returns
-------
k : float
Neutron multiplication factor.
phi_g : list of floats
Group flux.
xstab : list of tuples
A list of tuples of the format (nuc, rx, xs).
"""
# make inputs
pwd = self.pwd(state, "omc")
if not os.path.isdir(pwd):
os.makedirs(pwd)
self._make_omc_input(state)
statepoint = _find_statepoint(pwd)
if statepoint is None:
with indir(pwd):
subprocess.check_call(['openmc', '-s', '{}'.format(self.rc.threads)])
statepoint = _find_statepoint(pwd)
# parse & prepare results
k, phi_g, e_g = self._parse_statepoint(statepoint)
if self.rc.plot_group_flux:
plot_e_g, plot_phi_g = self._find_plot_data(statepoint)
with indir(pwd):
self._plot_group_flux(plot_e_g, plot_phi_g)
xstab = self._generate_xs(e_g, phi_g)
return k, phi_g, xstab
def _find_plot_data(self, statepoint_path):
sp = statepoint.StatePoint(statepoint_path)
tally = sp.tallies[3].get_values(['flux'])
phi_g = tally.flatten()
phi_g /= phi_g.sum()
e_g = sp.tallies[3].find_filter('energy').bins
return e_g, phi_g
def _plot_group_flux(self, e_g, phi_g):
"""Plot the group flux output by OpenMC and save plot to file.
Parameters
----------
e_g : array
Energy bins
phi_g : array
Flux values
"""
fig = plt.figure(figsize=(12, 8))
plt.loglog(*stair_step(e_g, phi_g), figure=fig)
plt.title("Flux vs Energy in")
plt.xlabel('E [MeV]')
plt.ylabel('Flux [N/cm$^2\cdot$s]')
plt.savefig("flux")
plt.close()
def _make_omc_input(self, state):
"""Make OpenMC input files for a given state.
Parameters
----------
state : namedtuple (State)
A namedtuple containing the state parameters.
Returns
-------
None
"""
pwd = self.pwd(state, "omc")
ctx = self.context(state)
rc = self.rc
# settings
settings = SETTINGS_TEMPLATE.format(**ctx)
with open(os.path.join(pwd, 'settings.xml'), 'w') as f:
f.write(settings)
# materials
valid_nucs = self.nucs_in_cross_sections()
# discard Cd-119m1 as a valid nuc
valid_nucs.discard(481190001)
ctx['_fuel_nucs'] = _mat_to_nucs(rc.fuel_material[valid_nucs])
curr_fuel = self.libs['fuel']['material'][-1][valid_nucs]
for nuc in curr_fuel.comp:
if curr_fuel.comp[nuc] < self.rc.track_nuc_threshold:
del curr_fuel.comp[nuc]
ctx['_fuel_nucs'] = _mat_to_nucs(curr_fuel[valid_nucs])
ctx['_clad_nucs'] = _mat_to_nucs(rc.clad_material[valid_nucs])
ctx['_cool_nucs'] = _mat_to_nucs(rc.cool_material[valid_nucs])
materials = MATERIALS_TEMPLATE.format(**ctx)
with open(os.path.join(pwd, 'materials.xml'), 'w') as f:
f.write(materials)
# geometry
ctx['lattice'] = ctx['lattice'].strip().replace('\n', '\n ')
ctx['_latt_shape0'] = ctx['lattice_shape'][0]
ctx['_latt_shape1'] = ctx['lattice_shape'][1]
ctx['_latt_x_pitch'] = ctx['unit_cell_pitch'] * ctx['lattice_shape'][0]
ctx['_latt_y_pitch'] = ctx['unit_cell_pitch'] * ctx['lattice_shape'][1]
ctx['_latt_x_half_pitch'] = ctx['_latt_x_pitch'] / 2.0
ctx['_latt_y_half_pitch'] = ctx['_latt_y_pitch'] / 2.0
geometry = GEOMETRY_TEMPLATE.format(**ctx)
with open(os.path.join(pwd, 'geometry.xml'), 'w') as f:
f.write(geometry)
# tallies
ctx['_egrid'] = " ".join(map(str, sorted(ctx['group_structure'])))
ctx['_eafds_egrid'] = " ".join(map(str, sorted(self.eafds.src_group_struct)))
ctx['_omcds_egrid'] = " ".join(map(str, sorted(self.omcds.src_group_struct)))
# nucs = core_nucs & valid_nucs
tallies = TALLIES_TEMPLATE.format(**ctx)
with open(os.path.join(pwd, 'tallies.xml'), 'w') as f:
f.write(tallies)
# plots
plots = PLOTS_TEMPLATE.format(**ctx)
with open(os.path.join(pwd, 'plots.xml'), 'w') as f:
f.write(plots)
def nucs_in_cross_sections(self):
"""Returns the set of nuclides present in the cross_sections.xml file.
Returns
-------
nucs : set
A set of all nuclides known to OpenMC, in ID form.
"""
return {n.nucid for n in self.omcds.cross_sections.ace_tables
if n.nucid is not None}
def _parse_statepoint(self, statepoint_path, tally_id=1):
"""Parses a statepoint file and reads in the relevant fluxes, assigns them
to the DataSources or the XSCache, and returns k, phi_g, and E_g.
Parameters
----------
statepoint : xsgen.statepoint.StatePoint
An OpenMC StatePoint.
tally_id : int
The tally id we wish to read group flux from.
Returns
-------
k : float
Neutron multiplication factor.
phi_g : list of floats
Group flux.
e_g : list of floats
Group structure.
"""
sp = statepoint.StatePoint(statepoint_path)
temp_tally = []
temp_tally.append(sp.tallies[2].get_values(['flux']).flatten())
temp_tally.append(sp.tallies[3].get_values(['flux']).flatten())
# compute group fluxes for data sources
for tally, ds in zip(temp_tally[:2], (self.eafds, self.omcds)):
ds.src_phi_g = np.array(tally[::-1])
ds.src_phi_g /= tally.sum()
# compute return values
k, kerr = sp.k_combined
tally = sp.tallies[tally_id].get_values(['flux'])
phi_g = tally.flatten()
phi_g /= phi_g.sum()
e_g = sp.tallies[tally_id].find_filter('energy').bins
e_g = e_g[::-1]
return k, phi_g, e_g
def _generate_xs(self, e_g, phi_g):
"""Grab xs data from cache depending on group flux.
Parameters
----------
e_g : list of floats
Group structure.
phi_g : list of floats
Group flux.
Returns
-------
data : list of tuples
A list of tuples of the format (nuc, rx, xs).
"""
rc = self.rc
verbose = rc.verbose
xscache = self.xscache
xscache.clear()
xscache['E_g'] = e_g
xscache['phi_g'] = phi_g
G = len(phi_g)
temp = rc.temperature
rxs = self.reactions
nucs = rc.track_nucs
dt = np.dtype([('nuc', 'i4'), ('rx', np.uint32), ('xs', 'f8', G)])
data = np.empty(len(nucs)*len(rxs), dtype=dt)
i = 0
for nuc in nucs:
for rx in rxs:
try:
xs = xscache[nuc, rx, temp]
except KeyError:
continue
if(len(xs) < G):
continue
if verbose:
print("OpenMC XS:", nucname.name(nuc), rxname.name(rx), xs, type(xs), temp)
data[i] = nuc, rx, xs
i += 1
return data
def _make_origen_input(self, transmute_time, phi_tot, mat):
"""Make ORIGEN input files for a given state.
Parameters
----------
transmute_time : float
The time, in days, to run the transmutation for.
phi_tot: float
Total neutron flux.
mat : pyne.material.Material
The fuel material to transmute.
Returns
-------
None
"""
# may need to filter tape4 for Bad Nuclides
# if sum(mat.comp.values()) > 1:
for nuc in mat.comp:
if mat.comp[nuc] < self.rc.track_nuc_threshold:
del mat.comp[nuc]
origen22.write_tape4(mat)
origen22.write_tape5_irradiation("IRF",
transmute_time,
phi_tot,
xsfpy_nlb=(219, 220, 221),
cut_off=self.rc.track_nuc_threshold)
origen22.write_tape9(self.tape9)