The Calculated Neutron Capture Cross-Section of the 238U and 232Th in the Range of 5-20 MeV

The transmutation of the long-lived fission products have great importance in solving the problem of radioactive waste. Therefore one needs to know reaction cross sections for 238U(n,2n)237U and 232Th(n,2n)231Th from point of view of accelerator-driven sub-critical systems and nuclear reactors. The 238U(n,2n)237U and 232Th(n,2n)231Th reaction cross sections were calculated by using TALYS 1.6 code in the energy range of 5-20 MeV. The calculated results are in good agreement with the measured results obtained from EXFOR

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