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Evaluated Cross Sections for Neutron Scattering from Natural Carbon Below 2 MeV Including R Matrix Fits to 13C Resonances

C. Y. Fu

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 494-500

Technical Note / dx.doi.org/10.13182/NSE90-A23774

The ENDF/B-V differential cross sections for neutron scattering from natural carbon below 2 MeV, recommended as standards for measurements and based on an R matrix analysis for 12C using natural carbon data, are revised to include 13C resonances for high-resolution applications. The recommended 13C cross sections are also based on an R matrix analysis of the available data. The 0.1529- and 1.736-MeV resonances rise above the natural carbon background by 7 and 1%, respectively. The angular distributions of the elastically scattered neutrons from 13C are generated by the R matrix theory. The final recommended cross sections and Legendre coefficients of angular distributions for natural carbon, adopted for ENDF/B-VI, are tabulated.