openmc.data.Reaction¶
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class
openmc.data.Reaction(mt)[source]¶ A nuclear reaction
A Reaction object represents a single reaction channel for a nuclide with an associated cross section and, if present, a secondary angle and energy distribution.
Parameters: mt (int) – The ENDF MT number for this reaction.
Variables: - center_of_mass (bool) – Indicates whether scattering kinematics should be performed in the center-of-mass or laboratory reference frame. grid above the threshold value in barns.
- redundant (bool) – Indicates whether or not this is a redundant reaction
- mt (int) – The ENDF MT number for this reaction.
- q_value (float) – The Q-value of this reaction in eV.
- xs (dict of str to openmc.data.Function1D) – Microscopic cross section for this reaction as a function of incident energy; these cross sections are provided in a dictionary where the key is the temperature of the cross section set.
- products (Iterable of openmc.data.Product) – Reaction products
- derived_products (Iterable of openmc.data.Product) – Derived reaction products. Used for ‘total’ fission neutron data when prompt/delayed data also exists.
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classmethod
from_endf(ev, mt)[source]¶ Generate a reaction from an ENDF evaluation
Parameters: - ev (openmc.data.endf.Evaluation) – ENDF evaluation
- mt (int) – The MT value of the reaction to get data for
Returns: rx – Reaction data
Return type:
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classmethod
from_hdf5(group, energy)[source]¶ Generate reaction from an HDF5 group
Parameters: - group (h5py.Group) – HDF5 group to read from
- energy (dict) – Dictionary whose keys are temperatures (e.g., ‘300K’) and values are arrays of energies at which cross sections are tabulated at.
Returns: Reaction data
Return type: