Released: 1994-07-22
A new MCNP® data library has been created, appending ENDF/B-VI delayed neutron data to the existing ENDF60 data tables. The library seeks to more accurately represent the secondary neutrons produced from a fission event by incorporating the capability of calculating the probability of delayed neutrons and, if sampled, their energy and time of creation after the occurrence of a fission event. A new library, ENDF6DN, has now been constructed consisting of the 20 isotopes listed in Table 2 of LA-UR-00-1549 and are designated with the ZAID extension .61c.
ENDF6DN 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 nucldata@lanl.gov