Abstract

Nuclear data on Uranium isotopes are of crucial interest for new generation of nuclear reactors. Processes of interest are the nuclear reactions induced by neutrons and in this work mainly the capture and the fission process on 238 U will be analyzed in a wide energy interval. For slow and resonant neutrons the many levels Breit – Wigner formalism is necessary. In the case of fast and very fast neutrons up to 200 MeV the nuclear reaction mechanism implemented in Talys will be used. The present evaluations are necessary in order to obtain the field of neutrons in the design of nuclear reactors and they are compared with experimental data from literature obtained from capture and (n,xn) processes.

Highlights

  • In the middle of XX century the scientists had already demonstrated that the classical fossil hydrocarbon fuel will be finished in approximately one century taking into account the predicted temps of world economic development

  • In many countries national programs of research and development of subcritical systems and new generation nuclear reactors based on the fission of 238U induced by fast neutrons are already started or in progress

  • In the future the calculations should to be extended higher than 200 MeV up to some GeV as it is requested in the researches dedicated to the fast neutrons reactors of new generation

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Summary

Introduction

In the middle of XX century the scientists had already demonstrated that the classical fossil hydrocarbon fuel (gas, coal, oil) will be finished in approximately one century taking into account the predicted temps of world economic development. In the present work the cross sections of fission and capture processes induced by fast neutrons on 238U and of the (n,xn) reactions on 89Y nucleus, the mass distributions and neutron multiplicity are evaluated. The neutron induced fission and (n,xn) cross sections, the mass distribution and neutron multiplicity obtained in the present work were calculated with Talys codes [7].

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