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
doi 10.14494/jnrs2000.7.n1
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The Japan Society of Nuclear and Radiochemical Sciences