openmc.deplete.FissionYieldDistribution¶
- class openmc.deplete.FissionYieldDistribution(fission_yields)[source]¶
Energy-dependent fission product yields for a single nuclide
Can be used as a dictionary mapping energies and products to fission yields:
>>> fydist = FissionYieldDistribution( ... {0.0253: {"Xe135": 0.021}}) >>> fydist[0.0253]["Xe135"] 0.021
- Parameters
fission_yields (dict) – Dictionary of energies and fission product yields for that energy. Expected to be of the form
{float: {str: float}}
. The first float is the energy, typically in eV, that represents this distribution. The underlying dictionary maps fission products to their respective yields.- Variables
energies (tuple) – Energies for which fission yields exist. Sorted by increasing energy
products (tuple) – Fission products produced at all energies. Sorted by name.
yield_matrix (numpy.ndarray) – Array
(n_energy, n_products)
whereyield_matrix[g, j]
is the fission yield of productj
for energy groupg
.
See also
from_xml_element()
- Construction methodsFissionYield
- Class used for storing yields at a given energy
- classmethod from_xml_element(element)[source]¶
Construct a distribution from a depletion chain xml file
- Parameters
element (lxml.etree._Element) – XML element to pull fission yield data from
- Return type
- restrict_products(possible_products)[source]¶
Return a new distribution with select products
New in version 0.12.
- Parameters
possible_products (iterable of str) – Candidate pool of fission products. Existing products not contained here will not exist in the new instance
- Returns
A value of None indicates no values in
possible_products
exist inproducts
- Return type
FissionYieldDistribution or None