Affiliation:
1. Institut für Reaktorsicherheit, Forschungszentrum Karlsruhe GmbH, 76021, Karlsruhe, Germany
Abstract
Abstract
The uncertainty in calculations of proton induced reaction cross-sections using modern nuclear models and codes has been investigated. Cross-sections calculated with TALYS-0.72, ALICE/ASH, DISCA, and MCNPX codes have been compared with experimental data available in EXFOR for (p, x) reactions at proton incident energies up to 150 MeV for target nuclei from 24Mg to 209Bi. In addition, the comparison of evaluated data from ENDF/B-VII, JENDL-HE, and PADF calculations with measured cross-sections has been performed. Various statistical criteria were applied for the quantification of the difference between results of calculations, evaluated and experimental data.
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation
Reference37 articles.
1. Global Comparison of TALYS and ALICE Code Calculations and Evaluated Data from ENDF/B;JENDL, FENDL and JEFF Files with Measured Neutron Induced Reaction Cross-Sections at Energies above 0.1 MeV, Journal of Nuclear and Radiochemical Sciences,2006
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4 articles.
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