Source code for openmc.element

from collections import OrderedDict
import os
import re
from xml.etree import ElementTree as ET

import openmc.checkvalue as cv
from openmc.data import NATURAL_ABUNDANCE, atomic_mass, \
    isotopes as natural_isotopes


[docs]class Element(str): """A natural element that auto-expands to add the isotopes of an element to a material in their natural abundance. Internally, the OpenMC Python API expands the natural element into isotopes only when the materials.xml file is created. Parameters ---------- name : str Chemical symbol of the element, e.g. Pu Attributes ---------- name : str Chemical symbol of the element, e.g. Pu """ def __new__(cls, name): cv.check_type('element name', name, str) cv.check_length('element name', name, 1, 2) return super().__new__(cls, name) @property def name(self): return self
[docs] def expand(self, percent, percent_type, enrichment=None, enrichment_target=None, enrichment_type=None, cross_sections=None): """Expand natural element into its naturally-occurring isotopes. An optional cross_sections argument or the :envvar:`OPENMC_CROSS_SECTIONS` environment variable is used to specify a cross_sections.xml file. If the cross_sections.xml file is found, the element is expanded only into the isotopes/nuclides present in cross_sections.xml. If no cross_sections.xml file is found, the element is expanded based on its naturally occurring isotopes. Parameters ---------- percent : float Atom or weight percent percent_type : {'ao', 'wo'} 'ao' for atom percent and 'wo' for weight percent enrichment : float, optional Enrichment of an enrichment_taget nuclide in percent (ao or wo). If enrichment_taget is not supplied then it is enrichment for U235 in weight percent. For example, input 4.95 for 4.95 weight percent enriched U. Default is None (natural composition). enrichment_target: str, optional Single nuclide name to enrich from a natural composition (e.g., 'O16') .. versionadded:: 0.12 enrichment_type: {'ao', 'wo'}, optional 'ao' for enrichment as atom percent and 'wo' for weight percent. Default is: 'ao' for two-isotope enrichment; 'wo' for U enrichment .. versionadded:: 0.12 cross_sections : str, optional Location of cross_sections.xml file. Default is None. Returns ------- isotopes : list Naturally-occurring isotopes of the element. Each item of the list is a tuple consisting of a nuclide string, the atom/weight percent, and the string 'ao' or 'wo'. Raises ------ ValueError No data is available for any of natural isotopes of the element ValueError If only some natural isotopes are available in the cross-section data library and the element is not O, W, or Ta ValueError If a non-naturally-occurring isotope is requested ValueError If enrichment is requested of an element with more than two naturally-occurring isotopes. ValueError If enrichment procedure for Uranium is used when element is not Uranium. ValueError Uranium enrichment is requested with enrichment_type=='ao' Notes ----- When the `enrichment` argument is specified, a correlation from `ORNL/CSD/TM-244 <https://doi.org/10.2172/5561567>`_ is used to calculate the weight fractions of U234, U235, U236, and U238. Namely, the weight fraction of U234 and U236 are taken to be 0.89% and 0.46%, respectively, of the U235 weight fraction. The remainder of the isotopic weight is assigned to U238. When the `enrichment` argument is specified with `enrichment_target`, a general enrichment procedure is used for elements composed of exactly two naturally-occurring isotopes. `enrichment` is interpreted as atom percent by default but can be controlled by the `enrichment_type` argument. """ # Check input if enrichment_type is not None: cv.check_value('enrichment_type', enrichment_type, {'ao', 'wo'}) if enrichment is not None: cv.check_less_than('enrichment', enrichment, 100.0, equality=True) cv.check_greater_than('enrichment', enrichment, 0., equality=True) # Get the nuclides present in nature natural_nuclides = {name for name, abundance in natural_isotopes(self)} # Create dict to store the expanded nuclides and abundances abundances = OrderedDict() # If cross_sections is None, get the cross sections from the # OPENMC_CROSS_SECTIONS environment variable if cross_sections is None: cross_sections = os.environ.get('OPENMC_CROSS_SECTIONS') # If a cross_sections library is present, check natural nuclides # against the nuclides in the library if cross_sections is not None: library_nuclides = set() tree = ET.parse(cross_sections) root = tree.getroot() for child in root.findall('library'): nuclide = child.attrib['materials'] if re.match(r'{}\d+'.format(self), nuclide) and \ '_m' not in nuclide: library_nuclides.add(nuclide) # Get a set of the mutual and absent nuclides. Convert to lists # and sort to avoid different ordering between Python 2 and 3. mutual_nuclides = natural_nuclides.intersection(library_nuclides) absent_nuclides = natural_nuclides.difference(mutual_nuclides) mutual_nuclides = sorted(list(mutual_nuclides)) absent_nuclides = sorted(list(absent_nuclides)) # If all naturally ocurring isotopes are present in the library, # add them based on their abundance if len(absent_nuclides) == 0: for nuclide in mutual_nuclides: abundances[nuclide] = NATURAL_ABUNDANCE[nuclide] # If some naturally occurring isotopes are not present in the # library, check if the "natural" nuclide (e.g., C0) is present. If # so, set the abundance to 1 for this nuclide. elif (self + '0') in library_nuclides: abundances[self + '0'] = 1.0 elif len(mutual_nuclides) == 0: msg = ('Unable to expand element {} because the cross ' 'section library provided does not contain any of ' 'the natural isotopes for that element.' .format(self)) raise ValueError(msg) # If some naturally occurring isotopes are in the library, add them. # For the absent nuclides, add them based on our knowledge of the # common cross section libraries (ENDF, JEFF, and JENDL) else: # Add the mutual isotopes for nuclide in mutual_nuclides: abundances[nuclide] = NATURAL_ABUNDANCE[nuclide] # Adjust the abundances for the absent nuclides for nuclide in absent_nuclides: if nuclide in ['O17', 'O18'] and 'O16' in mutual_nuclides: abundances['O16'] += NATURAL_ABUNDANCE[nuclide] elif nuclide == 'Ta180' and 'Ta181' in mutual_nuclides: abundances['Ta181'] += NATURAL_ABUNDANCE[nuclide] elif nuclide == 'W180' and 'W182' in mutual_nuclides: abundances['W182'] += NATURAL_ABUNDANCE[nuclide] else: msg = 'Unsure how to partition natural abundance of ' \ 'isotope {0} into other natural isotopes of ' \ 'this element that are present in the cross ' \ 'section library provided. Consider adding ' \ 'the isotopes of this element individually.' raise ValueError(msg) # If a cross_section library is not present, expand the element into # its natural nuclides else: for nuclide in natural_nuclides: abundances[nuclide] = NATURAL_ABUNDANCE[nuclide] # Modify mole fractions if enrichment provided # Old treatment for Uranium if enrichment is not None and enrichment_target is None: # Check that the element is Uranium if self.name != 'U': msg = ('Enrichment procedure for Uranium was requested, ' 'but the isotope is {} not U'.format(self)) raise ValueError(msg) # Check that enrichment_type is not 'ao' if enrichment_type == 'ao': msg = ('Enrichment procedure for Uranium requires that ' 'enrichment value is provided as wo%.') raise ValueError(msg) # Calculate the mass fractions of isotopes abundances['U234'] = 0.0089 * enrichment abundances['U235'] = enrichment abundances['U236'] = 0.0046 * enrichment abundances['U238'] = 100.0 - 1.0135 * enrichment # Convert the mass fractions to mole fractions for nuclide in abundances.keys(): abundances[nuclide] /= atomic_mass(nuclide) # Normalize the mole fractions to one sum_abundances = sum(abundances.values()) for nuclide in abundances.keys(): abundances[nuclide] /= sum_abundances # Modify mole fractions if enrichment provided # New treatment for arbitrary element elif enrichment is not None and enrichment_target is not None: # Provide more informative error message for U235 if enrichment_target == 'U235': msg = ("There is a special procedure for enrichment of U235 " "in U. To invoke it, the arguments 'enrichment_target'" "and 'enrichment_type' should be omitted. Provide " "a value only for 'enrichment' in weight percent.") raise ValueError(msg) # Check if it is two-isotope mixture if len(abundances) != 2: msg = ('Element {} does not consist of two naturally-occurring ' 'isotopes. Please enter isotopic abundances manually.' .format(self)) raise ValueError(msg) # Check if the target nuclide is present in the mixture if enrichment_target not in abundances: msg = ('The target nuclide {} is not one of the naturally-occurring ' 'isotopes ({})'.format(enrichment_target, list(abundances))) raise ValueError(msg) # If weight percent enrichment is requested convert to mass fractions if enrichment_type == 'wo': # Convert the atomic abundances to weight fractions # Compute the element atomic mass element_am = sum(atomic_mass(nuc)*abundances[nuc] for nuc in abundances) # Convert Molar Fractions to mass fractions for nuclide in abundances: abundances[nuclide] *= atomic_mass(nuclide) / element_am # Normalize to one sum_abundances = sum(abundances.values()) for nuclide in abundances: abundances[nuclide] /= sum_abundances # Enrich the mixture # The procedure is more generic that it needs to be. It allows # to enrich mixtures of more then 2 isotopes, keeping the ratios # of non-enriched nuclides the same as in natural composition # Get fraction of non-enriched isotopes in nat. composition non_enriched = 1.0 - abundances[enrichment_target] tail_fraction = 1.0 - enrichment / 100.0 # Enrich all nuclides # Do bogus operation for enrichment target but overwrite immediatly # to avoid if statement in the loop for nuclide, fraction in abundances.items(): abundances[nuclide] = tail_fraction * fraction / non_enriched abundances[enrichment_target] = enrichment / 100.0 # Convert back to atomic fractions if requested if enrichment_type == 'wo': # Convert the mass fractions to mole fractions for nuclide in abundances: abundances[nuclide] /= atomic_mass(nuclide) # Normalize the mole fractions to one sum_abundances = sum(abundances.values()) for nuclide in abundances: abundances[nuclide] /= sum_abundances # Compute the ratio of the nuclide atomic masses to the element # atomic mass if percent_type == 'wo': # Compute the element atomic mass element_am = 0. for nuclide in abundances.keys(): element_am += atomic_mass(nuclide) * abundances[nuclide] # Convert the molar fractions to mass fractions for nuclide in abundances.keys(): abundances[nuclide] *= atomic_mass(nuclide) / element_am # Normalize the mass fractions to one sum_abundances = sum(abundances.values()) for nuclide in abundances.keys(): abundances[nuclide] /= sum_abundances # Create a list of the isotopes in this element isotopes = [] for nuclide, abundance in abundances.items(): isotopes.append((nuclide, percent * abundance, percent_type)) return isotopes