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[en] A complete set neutron data for 233U, including cross sections, angular distributions and secondary neutron spectra, from 10-5 eV to 20 MeV were evaluated based on evaluated experimental data and theoretical calculated results in Endf/B-6 format
Source
China Nuclear Information Centre, Beijing (China); 179 p; ISBN 7-5022-2120-4; 
; Dec 1999; p. 83-95; 19 refs., 1 tab., 12 figs.
; Dec 1999; p. 83-95; 19 refs., 1 tab., 12 figs.