Publication Type
Journal
Journal Name
Progress in Nuclear Energy
Publication Date
Page Number
104551
Volume
157
Issue
March
Abstract
The evaluated 35Cl(n, p) cross sections in the ENDF/B-VIII.0 nuclear data library remain uncertain because of the lack of measured data in the neutron energy range between 100-600 keV. In this energy region, the R-matrix analysis relies heavily on estimated (n; p) partial widths and level density information. This resulted in significant differences of the evaluated cross sections and predicted reactivity in nuclear reactor applications with respect to previous nuclear data libraries. This paper presents a methodology to quantify the cross sections for the 35Cl(n, p) reaction channel from the combination of measured total cross sections and model calculations.
