Fission cross-sections of important actinides produced in the TH-U fuel cycle

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dc.contributor.advisorAgarwal, H.M.
dc.contributor.authorPandey, Hem Chandra
dc.date.accessioned2018-07-30T06:24:30Z
dc.date.available2018-07-30T06:24:30Z
dc.date.issued2017-07
dc.description.abstractAccurate 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.en_US
dc.identifier.urihttp://krishikosh.egranth.ac.in/handle/1/5810062494
dc.keywordsfission, actinides, fuels, nuclear energyen_US
dc.language.isoenen_US
dc.pages59en_US
dc.publisherG.B. Pant University of Agriculture and Technology, Pantnagar - 263145 (Uttarakhand)en_US
dc.research.problemActinidesen_US
dc.subPhysicsen_US
dc.subjectnullen_US
dc.themeFissionen_US
dc.these.typeM.Scen_US
dc.titleFission cross-sections of important actinides produced in the TH-U fuel cycleen_US
dc.typeThesisen_US
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