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28 changes: 1 addition & 27 deletions openmc/data/endf.py
Original file line number Diff line number Diff line change
Expand Up @@ -12,6 +12,7 @@

from .data import gnds_name
from .function import Tabulated1D
from endf.material import _LIBRARY, _SUBLIBRARY
from endf.incident_neutron import SUM_RULES
from endf.records import (
float_endf,
Expand All @@ -38,33 +39,6 @@ def get_tab1_record(file_obj):
return params, Tabulated1D(tab.x, tab.y, tab.breakpoints, tab.interpolation)


_LIBRARY = {0: 'ENDF/B', 1: 'ENDF/A', 2: 'JEFF', 3: 'EFF',
4: 'ENDF/B High Energy', 5: 'CENDL', 6: 'JENDL',
17: 'TENDL', 18: 'ROSFOND', 21: 'SG-21', 31: 'INDL/V',
32: 'INDL/A', 33: 'FENDL', 34: 'IRDF', 35: 'BROND',
36: 'INGDB-90', 37: 'FENDL/A', 41: 'BROND'}

_SUBLIBRARY = {
0: 'Photo-nuclear data',
1: 'Photo-induced fission product yields',
3: 'Photo-atomic data',
4: 'Radioactive decay data',
5: 'Spontaneous fission product yields',
6: 'Atomic relaxation data',
10: 'Incident-neutron data',
11: 'Neutron-induced fission product yields',
12: 'Thermal neutron scattering data',
19: 'Neutron standards',
113: 'Electro-atomic data',
10010: 'Incident-proton data',
10011: 'Proton-induced fission product yields',
10020: 'Incident-deuteron data',
10030: 'Incident-triton data',
20030: 'Incident-helion (3He) data',
20040: 'Incident-alpha data'
}


def get_evaluations(filename):
"""Return a list of all evaluations within an ENDF file.

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