endf.IncidentNeutron#

class endf.IncidentNeutron(atomic_number, mass_number, metastable=0)[source]#

Continuous-energy neutron interaction data.

This class stores data derived from an ENDF-6 format neutron interaction sublibrary.

Parameters:

  • atomic_number (int) – Number of protons in the target nucleus

  • mass_number (int) – Number of nucleons in the target nucleus

  • metastable (int) – Metastable state of the target nucleus. A value of zero indicates the ground state.

atomic_number#

Number of protons in the target nucleus

Type:

int

atomic_symbol#

Atomic symbol of the nuclide, e.g., ‘Zr’

Type:

str

mass_number#

Number of nucleons in the target nucleus

Type:

int

metastable#

Metastable state of the target nucleus. A value of zero indicates the ground state.

Type:

int

name#

Name of the nuclide using the GNDS naming convention

Type:

str

reactions#

Contains the cross sections, secondary angle and energy distributions, and other associated data for each reaction. The keys are the MT values and the values are Reaction objects.

Type:

dict

Methods

from_ace(filename_or_table[, metastable_scheme])

Generate incident neutron continuous-energy data from an ACE table

from_endf(filename_or_mat)

Generate incident neutron data from an ENDF file