2017
DOI: 10.4236/ijmpcero.2017.63031
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Calculation of Reactions Cross Section for Neutron-Induced Reactions on <sup>127</sup>I Isotope

Abstract: In this work, the reaction cross-section for neutron-induced reactions on 127 I isotope was calculated using EXIFON code in the energy range of incident particle from 0 MeV to 30 MeV. The code is based on an analytical model for statistical multistep direct and multistep compound reactions (SMD/SMC model). In order to see the effect of nuclear structure on cross sections, the calculation was done using nuclear shell structure effect and without considering shell structure effect. Obtained results and statistic… Show more

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Cited by 3 publications
(2 citation statements)
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“…However, this research is for nuclear research reactor application. As such, we shall focus on nuclear reactor fuels [1]. It is pertinent to search for alternative fuel means in some isotopes that are radioactive aside the uranium-235 and plutonium-239.…”
Section: Flow Injection System(fia): 11 Introduction Fiamentioning
confidence: 99%
“…However, this research is for nuclear research reactor application. As such, we shall focus on nuclear reactor fuels [1]. It is pertinent to search for alternative fuel means in some isotopes that are radioactive aside the uranium-235 and plutonium-239.…”
Section: Flow Injection System(fia): 11 Introduction Fiamentioning
confidence: 99%
“…Nuclear fission is almost ten (10) times much effective at energy of production compare to normal fossil (fuels) [1]. Nuclear reactions generate and produce massive quantities of carbon-free electricity and aside from this volume of energy produced, it protects the environment and the air we breathe [2].…”
Section: Introductionmentioning
confidence: 99%