Abstract

The level density models and level density parameters are two of important quantities for describing the properties of nuclei. Especially, the level density parameter has an important role as input in calculation of reaction cross sections. In this study, the cross sections on 235 U(g,f) reaction were calculated for different level density models using the TALYS 1.6 code up to 20 MeV gamma incident energies. First, it was determined the level density model that was the closest to the experimental data. Secondly, cross sections obtained for different level density parameters of this model were compared with experimental data from the EXFOR database. Thus it was determined the best level density parameter fit to experimental data.

Highlights

  • IntroductionThe level density and level density parameter are very important quantities in determination of the both structure and after reaction properties of nuclei

  • The cross sections on235U(g,f) reaction were calculated for different level density models, which are available in code, using the TALYS 1.6 nuclear reaction code [1]

  • The TALYS 1.6 code was used in theoretical calculations created by Koning and his colleagues at NRG Petten, Netherlands and CEA Bruyeres-le-Chatel, France to provide a complete and accurate simulation of nuclear reactions involving n, gamma, p, d, t, 3He, and α projectiles in the 1 keV–1 GeV energy range, through an optimal combination of nuclear models

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Summary

Introduction

The level density and level density parameter are very important quantities in determination of the both structure and after reaction properties of nuclei. The level density parameter has a significant role in the theoretical evaluation of reaction cross sections. There are a lot of studies, depend on different model approximation, on theoretically nuclear data evaluation for fission cross section and fission yield. TALYS’ calculation results depend on great input parameter tuning based on experimental data using best curve fitting. At this point, available experimental data play an important role in TALYS evaluation to achieve better agreement with it [3, 4]. The cross sections on235U(g,f) reaction were calculated for different level density models, which are available in code, using the TALYS 1.6 nuclear reaction code [1]. All the calculations were compared with the experimental data obtained from EXFOR library [5]

Level densities
The level density parameter
Methods
Results
Conclusion
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