Investigation of cross sections of reactions used in neutron activation analysis
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E. Tel
Abstract
In this study, neutron incident reaction cross sections for some target nuclei such as 24Mg, 27Al, 28Si, 56Fe, and 63Cu used in neutron activation analysis have been investigated. The new calculations on the excitation functions of 24Mg(n, p)24Na, 27Al(n, p)27Mg, 27Al(n, α)24Na, 28Si(n, p)28Al, 56Fe(n, p)56Mn, and 63Cu(n, 2n)62Cu reactions have been carried out for incident neutron energies up to 20 MeV. In these calculations, the pre-equilibrium and equilibrium effects have been investigated. The pre-equilibrium calculations involve the new geometry dependent hybrid model and the full exciton model. Equilibrium effects are calculated according to the Weisskopf–Ewing model. In the present work, reaction cross-sections have been calculated by using empirical formulas developed for energies of 14–15 MeV. The calculated results are discussed and compared with the experimental data taken from the EXFOR database.
Kurzfassung
In der vorliegenden Studie werden Reaktionsquerschnitte einfallender Neutronen untersucht für eine Reihe von Targetkernen, wie z.B. 24Mg, 27Al, 28Si, 56Fe und 63Cu, die in der Neutronenaktivierungsanalyse verwendet werden. Die neuen Berechnungen der Anregungsfunktionen von 24Mg(n, p)24Na, 27Al(n, p)27Mg, 27Al(n, α)24Na, 28Si(n, p)28Al, 56Fe(n, p)56Mn, and 63Cu(n, 2n)62Cu Reaktionen wurden für Energien der einfallenden Neutronen von bis zu 20 MeV durchgeführt. In diesen Berechnungen wurden Vorgleichgewichts- und Gleichgewichtseffekte untersucht. Die Vorgleichgewichtsberechnungen wurden mit Hilfe des neuen geometrieabhängigen Hybridmodells und des Exzitonenmodells durchgeführt. Gleichgewichtseffekte wurden nach dem Weisskopf–Ewing-Model berechnet. In der vorliegenden Arbeit wurden diese Reaktionsquerschnitte berechnet mit Hilfe empirischer Formeln für Energien von 14–15 MeV. Die Ergebnisse der Berechnungen werden diskutiert und verglichen mit den experimentellen Ergebnissen aus der EXFOR Databank.
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Comparison between CAREB code calculations and LOCA test results in the FUMEX III project
- Calculation of moderator circulation in IPHWR using a porosity approach
- Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
- CFD analysis of passive autocatalytic recombiner interaction with atmosphere
- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
- Inverse problems using Artificial Neural Networks in long range atmospheric dispersion
- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
- Neutron multiplication in source driven subcritical nuclear systems
- Cyclotron production of 101Pd/101mRh radionuclide generator for radioimmunotherapy
- Investigation of cross sections of reactions used in neutron activation analysis
- Modified UN method for the reflected critical slab problem with forward and backward scattering
