Interaction of Be4+ and Ground State Hydrogen Atom—Classical Treatment of the Collision

I Ziaeian,K Tőkési

doi:10.3390/atoms8020027

I Ziaeian, K Tőkési

Open Access

https://doi.org/10.3390/atoms8020027

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Journal: Atoms	Publication Date: Jun 3, 2020
Citations: 16	License type: CC BY 4.0

Affiliation: HUN-REN Institute for Nuclear Research

Abstract

The interaction between Be4+ and hydrogen atom is studied using the three-body classical trajectory Monte Carlo method (CTMC) and the quasiclassical trajectory Monte Carlo method of Kirschbaum and Wilets (QTMC-KW). We present total cross sections for target ionization, target excitation, and charge exchange to the projectile bound states. Calculations are carried out in the projectile energy range between 10 and 1000 keV/au, relevant to the interest of fusion research when the target hydrogen atom is in the ground state. Our results are compared with previous theoretical results. We found that the classical treatment describes reasonably well the cross sections for various final channels. Moreover, we show that the calculations by the QTMC-KW model significantly improve the obtained cross sections.

Highlights

The currently used energy production methods will not be able to satisfy the energy needs of humanity in the long run
Beryllium is typically considered as the armor material for plasma facing components (PFCs) of fusion devices and it is the first wall of the international thermonuclear experimental reactor (ITER) [1]
Chemical and physical erosion of the first wall releases beryllium atoms and several molecular species, which eventually lead to the presence of fully-stripped beryllium ions in the plasma core

Summary

Introduction

The currently used energy production methods will not be able to satisfy the energy needs of humanity in the long run. One of the best solutions in the future would be the implementation of fusion power plants. Beryllium is typically considered as the armor material for plasma facing components (PFCs) of fusion devices and it is the first wall of the international thermonuclear experimental reactor (ITER) [1]. Chemical and physical erosion of the first wall releases beryllium atoms and several molecular species, which eventually lead to the presence of fully-stripped beryllium ions in the plasma core. Beryllium is attractive as a plasma facing reactor material because of its low atomic number (i.e., low potential for radiative plasma power losses), excellent gettering properties concerning oxygen (unavoidably present in any fusion plasma), and adequate thermo-mechanical and erosion properties when exposed to plasma energy and particle fluxes.

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