Theoretical model code was used to evaluate neutron-induced radiative capture cross section on isotope of 237Np, 241Am, 243Am, 244Cm, and 245Cm with an effort to improve the contribution to the nuclear reaction data from 1 MeV which are important ingredients in studying the heating effect in the reactor core. The phenomenology level density model was implemented by varying different parameters to fit unknown experimental nuclear cross sections using nuclear reaction calculation modular code (EMPIRE 3.2.3 code). The evaluated neutron-induced capture cross section on
237Np, 241Am, 243Am, 244Cm and 245Cm were compared with experimental data retrieved from EXFOR and recent Evaluated Nuclear Data Library. A discrepancy of 2.82% was observed between model calculation on the excited nucleus and Evaluated Nuclear Data File ENDF at about ??≥1 MeV, suspected to be effect from target spin and level coupling respectively. However, the good agreement between the model prediction of neutron-induced capture cross section and experimental data confirms the quality of the model calculation. The calculated results are relevant for the incineration of the minor actinides capable of reactors design.
Key words: EMPIRE 3.2.3 code, Level Density, Nuclear Cross-Section, Minor Actinides
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