Fission cross-sections of important actinides produced in the TH-U fuel cycle
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Date
2017-07
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G.B. Pant University of Agriculture and Technology, Pantnagar - 263145 (Uttarakhand)
Abstract
Accurate measurement of neutron induced fission cross-section data are essential in designing the future fission reactors. In the present work, neutron induced fission cross-sections are calculated for different isotopes of Thorium, Protactinium and Uranium (232Th, 231,232,233Pa, 232,233,234,235,236U) which produces in the Th – U fuel cycle. The calculations were done with EMPIRE 3.1 Nuclear code, which is based on various theoretical model and number of FORTRAN codes, reference input parameter libraries (RIPL) and experimental data library (EXFOR). The comparison of (n, f) reaction cross-sections calculated using the barrier parameters obtained by the analytical barrier formula are more reliable and supported by the experimental and evaluated results. The fission barrier height values of various radionuclides, taken from RIPL-1, RIPL-2 and RIPL-3 produces the experimental and evaluated data poorly for the studied actinides. Thus, it is concluded from the results of the present work that the precise measurement of the barrier heights is very important to predict the fission cross-section data accurately.
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