ENDF/B-VII.1 Incident-Neutron Data |
This page provides access to the incident-neutron evaluations for
ENDF/B-VII.1. Each entry has links to the raw ENDF evaluation, to an
interative browser that makes it easier to read ENDF format for
non experts, and to PDF plots of the data that were generated during
processing for an MCNP library. In addition, each entry has supplemental information, including the ENDF MAT number and an "Info Tag" which provides some summary information about the contents of the evaluation using the following abbreviations:
B = Single-level Breit-Wigner resolved resonance parameters
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Custom 2D and 3D plots of the incident-neutron data can be made using the Nuclear Data Viewer. Select the types ENDFB-VII.1-neutron for raw ENDF/B-VII.1 evaluations or ENDF-VII.1-neutron-pointwise for files with reconstructed resonance cross sections and other information added by NJOY processing. |
Individual room-temperature pointwise files for ENDF/B-VII.1 neutron data
can be downloaded by requesting links like data/data/ENDFB-VII.1-neutron-pointwise/Al/27 Caution: these files are large! The isotopes available can be determined from the index above. |