The ENDF5MT Library is a multi-temperature ACE library developed from the EDNF/B-V data libraries. Neutron cross sections for several isotopes from ENDF/B-V have been Doppler broadened to reactor temperatures and processed into a format appropriate for the MCNP® Monte Carlo code. Cross sections for 1H, 10B, 16O, Zr, 135Xe, 235U, and 238U have been made available at 600 K, and cross sections for 16O, Zr, 135Xe, 235U, and 238U have been made at 900 K.
ENDF5MT can be downloaded either as a zip file or as a compressed tarball
If further information is required contact a member of the Data Team by e-mail at firstname.lastname@example.org