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 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 _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 _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 _load_reaction(self, nuc, rx, temp=300.0):
"""Loads reaction data from ACE files indexed by OpenMC.
Parameters
----------
nuc : int
Nuclide id.
rx : int
Reaction id.
temp : float, optional
The nuclide temperature in [K].
"""
rx = rxname.id(rx)
try:
mt = rxname.mt(rx)
except RuntimeError:
return None
totrx = rxname.id('total')
absrx = rxname.id('absorption')
ace_tables = self._rank_ace_tables(nuc, temp=temp)
lib = ntab = None
for atab in ace_tables:
if atab not in self.libs:
lib = self.libs[atab] = ace.Library(atab.abspath or atab.path)
lib.read(atab.name)
lib = self.libs[atab]
ntab = lib.tables[atab.name]
if mt in ntab.reactions or rx == totrx or rx == absrx:
break
lib = ntab = None
if lib is None:
return None # no reaction available
E_g = self.src_group_struct
E_points = ntab.energy
if rx == totrx:
rawdata = ntab.sigma_t
elif rx == absrx:
rawdata = ntab.sigma_a
else:
ntabrx = ntab.reactions[mt]
if ntabrx.IE is None or ntabrx.IE == 0:
rawdata = ntabrx.sigma
else:
rawdata = np.empty(len(E_points), dtype='f8')
rawdata[:ntabrx.IE] = 0.0
rawdata[ntabrx.IE:] = ntabrx.sigma
if (E_g[0] <= E_g[-1] and E_points[-1] <= E_points[0]) or \
(E_g[0] >= E_g[-1] and E_points[-1] >= E_points[0]):
E_points = E_points[::-1]
rawdata = rawdata[::-1]
rxdata = bins.pointwise_linear_collapse(E_g, E_points, rawdata)
return rxdata
def _load_reaction(self, nuc, rx, temp=300.0):
"""Loads reaction data from ACE files indexed by OpenMC.
Parameters
----------
nuc : int
Nuclide id.
rx : int
Reaction id.
temp : float, optional
The nuclide temperature in [K].
"""
rx = rxname.id(rx)
try:
mt = rxname.mt(rx)
except RuntimeError:
return None
totrx = rxname.id('total')
absrx = rxname.id('absorption')
ace_tables = self._rank_ace_tables(nuc, temp=temp)
lib = ntab = None
for atab in ace_tables:
if atab not in self.libs:
lib = self.libs[atab] = ace.Library(atab.abspath or atab.path)
lib.read(atab.name)
lib = self.libs[atab]
ntab = lib.tables[atab.name]
if mt in ntab.reactions or rx == totrx or rx == absrx:
break
lib = ntab = None
if lib is None:
return None # no reaction available
E_g = self.src_group_struct
E_points = ntab.energy
if rx == totrx:
rawdata = ntab.sigma_t
elif rx == absrx:
rawdata = ntab.sigma_a
else:
ntabrx = ntab.reactions[mt]
if ntabrx.IE is None or ntabrx.IE == 0:
rawdata = ntabrx.sigma
else:
rawdata = np.empty(len(E_points), dtype='f8')
rawdata[:ntabrx.IE] = 0.0
rawdata[ntabrx.IE:] = ntabrx.sigma
if (E_g[0] <= E_g[-1] and E_points[-1] <= E_points[0]) or \
(E_g[0] >= E_g[-1] and E_points[-1] >= E_points[0]):
E_points = E_points[::-1]
rawdata = rawdata[::-1]
rxdata = bins.pointwise_linear_collapse(E_g, E_points, rawdata)
return rxdata
def _load_group_structure(self, nuc, rx, nuc_i=None):
"""Loads the group structure from ENDF file."""
self.library._read_res(nuc)
mt = rxname.mt(rx)
rxdata = self.rxcache[nuc, rx, nuc_i]
xsdata = self.library.get_xs(nuc, rx, nuc_i)[0]
intpoints = xsdata['intpoints']#[::-1]
e_int = xsdata["e_int"]
src_group_struct = [e_int[intpoint-1] for intpoint in intpoints[::-1]]
rxdata['src_group_struct'] = src_group_struct
rxdata['src_ngroups'] = len(intpoints)
rxdata['src_phi_g'] = np.ones(len(intpoints), dtype='f8') \
if rxdata['_src_phi_g'] is None \
else np.asarray(rxdata['src_phi_g'])
def test_mt_ids():
assert_equal(rxname.mt(_hash("a")), 107)
assert_equal(rxname.mt(_hash("total")), 1)
assert_equal(rxname.mt(long(_hash("a"))), 107)
assert_equal(rxname.mt(long(_hash("total"))), 1)
assert_equal(rxname.mt(str(_hash("a"))), 107)
assert_equal(rxname.mt(str(_hash("total"))), 1)
def test_mt_ids():
assert_equal(rxname.mt(_hash("a")), 107)
assert_equal(rxname.mt(_hash("total")), 1)
assert_equal(rxname.mt(long(_hash("a"))), 107)
assert_equal(rxname.mt(long(_hash("total"))), 1)
assert_equal(rxname.mt(str(_hash("a"))), 107)
assert_equal(rxname.mt(str(_hash("total"))), 1)
def test_mt_mts():
assert_equal(rxname.mt(107), 107)
assert_equal(rxname.mt(1), 1)
assert_equal(rxname.mt(long(107)), 107)
assert_equal(rxname.mt(long(1)), 1)
assert_equal(rxname.mt("107"), 107)
assert_equal(rxname.mt("1"), 1)
def test_mt_mts():
assert_equal(rxname.mt(107), 107)
assert_equal(rxname.mt(1), 1)
assert_equal(rxname.mt(long(107)), 107)
assert_equal(rxname.mt(long(1)), 1)
assert_equal(rxname.mt("107"), 107)
assert_equal(rxname.mt("1"), 1)
def _load_group_structure(self, nuc, rx, nuc_i=None):
"""Loads the group structure from ENDF file."""
self.library._read_res(nuc)
mt = rxname.mt(rx)
rxdata = self.rxcache[nuc, rx, nuc_i]
xsdata = self.library.get_xs(nuc, rx, nuc_i)[0]
intpoints = xsdata['intpoints'] #[::-1]
e_int = xsdata["e_int"]
src_group_struct = [
e_int[intpoint - 1] for intpoint in intpoints[::-1]
]
rxdata['src_group_struct'] = src_group_struct
rxdata['src_ngroups'] = len(intpoints)
rxdata['src_phi_g'] = np.ones(len(intpoints), dtype='f8') \
if rxdata['_src_phi_g'] is None \
else np.asarray(rxdata['src_phi_g'])
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 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_mt_alts():
assert_equal(rxname.mt("alpha"), 107)
assert_equal(rxname.mt("tot"), 1)
def test_mt_names():
assert_equal(rxname.mt("a"), 107)
assert_equal(rxname.mt("total"), 1)
def test_mt_nucdelta():
assert_equal(rxname.mt("U235", "U236"), 27)
assert_equal(rxname.mt("U235", "Np236", "p"), 27)
assert_equal(rxname.mt(922350, 912350), 103)
def test_mt_alts():
assert_equal(rxname.mt("alpha"), 107)
assert_equal(rxname.mt("tot"), 1)
def test_mt_names():
assert_equal(rxname.mt("a"), 107)
assert_equal(rxname.mt("total"), 1)
def test_mt_nucdelta():
assert_equal(rxname.mt("U235", "U236"), 27)
assert_equal(rxname.mt("U235", "Np236", "p"), 27)
assert_equal(rxname.mt(922350, 912350), 103)
def pointwise(self, nuc, rx, temp=300.0):
"""Returns pointwise reaction data from ACE files indexed by OpenMC.
Parameters
----------
nuc : int
Nuclide id.
rx : int
Reaction id.
temp : float, optional
The nuclide temperature in [K].
Returns
-------
E_points : array-like
The array or energy points that the reaction is evaluated at.
rawdata : array-like
Raw pointwise reaction data.
"""
nuc = nucname.id(nuc)
rx = rxname.id(rx)
try:
mt = rxname.mt(rx)
except RuntimeError:
return None
totrx = rxname.id("total")
absrx = rxname.id("absorption")
ace_tables = self._rank_ace_tables(nuc, temp=temp)
lib = ntab = None
for atab in ace_tables:
if os.path.isfile(atab.abspath or atab.path):
if atab not in self.libs:
lib = self.libs[atab] = ace.Library(atab.abspath
or atab.path)
lib.read(atab.name)
lib = self.libs[atab]
ntab = lib.tables[atab.name]
if mt in ntab.reactions or rx == totrx or rx == absrx:
break
lib = ntab = None
if lib is None:
return None # no reaction available
E_g = self.src_group_struct
E_points = ntab.energy
if rx == totrx:
rawdata = ntab.sigma_t
elif rx == absrx:
rawdata = ntab.sigma_a
else:
ntabrx = ntab.reactions[mt]
if ntabrx.IE is None or ntabrx.IE == 0:
rawdata = ntabrx.sigma
else:
rawdata = np.empty(len(E_points), dtype="f8")
rawdata[:ntabrx.IE] = 0.0
rawdata[ntabrx.IE:] = ntabrx.sigma
if (E_g[0] <= E_g[-1] and E_points[-1] <= E_points[0]) or (
E_g[0] >= E_g[-1] and E_points[-1] >= E_points[0]):
E_points = E_points[::-1]
rawdata = rawdata[::-1]
return E_points, rawdata