Calculations of (γ,n) Reaction Cross Sections using Different Level Density Models for Some Lanthanide Nuclei

The discrete level information deficiency requires usage of level density models in cross section calculations. The total reaction cross sections for gamma-induced reactions through the six level density models with a consistent parameterization of some lanthanides (141Pr, 142Nd, 144Sm, 153Eu, 159Tb, 160Gd, 165Ho, 175Lu) were calculated using TALYS 1.6 in the incident energy range from 5 to 30 MeV. All calculations from the present study were compared with each other and with data available in the literature. DOI: 10.12693/APhysPolA.128.B-22