Published October 1998
INDC Report INDC(BLR)-13 INDC-2203 INDC-BLR-0013

Fission Level Density and Barrier Parameters for Actinide Neutron Induced-Neutron Cross Section Calculations

Creators

Description

No description available

Files

indc-blr-0013.pdf

Files (11.1 kB)

Name Size Download all
md5:50e1ec18cd922926b2568c4e42222f27
11.1 kB Preview Download