[en] The neutron cross sections of Cm-247 are evaluated in the resonance (resolved and unresolved) region up to 10 keV. Average resonance parameters (i.e. spacing D, fission and radiative widths, neutron strength functions) are determined for unresolved region calculations. Moreover for a better comparison with the experimental data, fission cross section is calculated up to 10 MeV. In addition, the average number of neutrons emitted per fission as a function of energy is estimated
Source
Hage, W. (ed.); Commission of the European Communities, Ispra (Italy). Joint Research Centre; 540 p; ISBN 92-825-2058-7; 
; 1980; p. 171-190; 2. Technical meeting on the nuclear transmutation of actinides; Ispra, Italy; 21 - 24 Apr 1980
; 1980; p. 171-190; 2. Technical meeting on the nuclear transmutation of actinides; Ispra, Italy; 21 - 24 Apr 1980