Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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NEUTRON CROSS SECTION DATA LIBRARY FOR PD-105, AG-109, XE-131 AND CS-133

  • LEE Y. D. (Korea Atomic Energy Research Institute) ;
  • CHANG J. H. (Korea Atomic Energy Research Institute)
  • Published : 2005.02.01
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Abstract

The neutron induced nuclear cross-section data for Pd-105, Ag-109, Xe-131, and Cs-133 were calculated and evaluated from an unresolved energy to 20 MeV. The energy dependent optical model potential parameters were extracted based on recent experimental data and applied up to 20 MeV. A spherical optical model and a statistical model for the equilibrium energy, and a multistep direct and a multistep compound model for the pre-equilibrium energy were used in the calculation. The direct capture model was recently introduced for fast neutron capture. The theoretically calculated cross-sections were compared with the experimental data and the evaluated files. The total and capture cross-sections calculated using the model were in good agreement with the reference experimental data. The evaluated cross-section results were compiled in ENDF-6 format and merged with the resonance component, already adopted in the ENDF/B-VI release 8. New data library files covering from thermal to 20 MeV were created. They are at the preliminary stage of an ENDF/B- VII release.

Keywords

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