openmc.data.Reaction

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.

classmethod from_endf(ev, mt)[source]

Generate a reaction from an ENDF evaluation

Parameters
Returns

rx – Reaction data

Return type

openmc.data.Reaction

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

openmc.data.Reaction

to_hdf5(group)[source]

Write reaction to an HDF5 group

Parameters

group (h5py.Group) – HDF5 group to write to