Diferenças entre bibliotecas de seções de choque para dosimetria de nêutrons

摘要: Absorbed dose calculations depend on a consistent set of nuclear data used in simulations computer codes. Nuclear are stored libraries, however, the information available about differences caused by different libraries rare. The processed system to be able radiation transport code. One systems capable processing is NJOY system. objective this study evaluate for neutrons literature, and quantify absorbed obtained using JENDL 4.0, JEFF 3.3.1 ENDF/B.VII. calculation was performed simple geometric model, as spheres, anthropomorphic model human body based ICRP-110 neutron simulation MCNP5 results were compared with literature data. cross sections from ENDF/B.VII have shown identical most cases, except one case where difference has exceeded 10%. library considerably cases comparing other two libraries. Some over 200%. showed between which justified sections. It been observed that values certain nuclides assume quite These turn cause considerable calculations.