The microstructure of tungsten exposed to D plasma with different impurities

M Rasinski,A Kreter,Y Torikai,Ch Linsmeier

doi:10.1016/j.nme.2016.11.001

M Rasinski, A Kreter + Show 2 more

Open Access

https://doi.org/10.1016/j.nme.2016.11.001

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Abstract

In this study the effect of impurities in deuterium plasma on the tungsten microstructure is investigated. W samples were exposed in the linear plasma generator PSI-2 at a sample temperature of 500K with an incident ion flux of about 1022m−2s−1, an incident ion fluence of 5×1025m−2 and an incident ion energy of 70eV. Samples were exposed to pure D+ plasma and with additional impurities of He (3%), Ar (7%), Ne (10%) or N (5%). After the PSI-2 exposure a part of each sample was additionally loaded with tritium to measure the tritium uptake using the imaging plate technique.The surface morphology was investigated using scanning electron microscope (SEM) combined with a focused ion beam (FIB) utilized for cross-sectioning and thin lamella preparation for the transmission electron microscope (TEM) analysis.Blistering with grain orientation dependence was observed on all exposed samples. Most pronounced blistering is reported for grains with orientation close to (111). The addition of Ar or Ne results in surface erosion with different yields depending on grain orientation. Highest erosion yield is observed for grains with orientation close to (100). Large blisters are present but show signatures of erosion. Less pronounced erosion is visible when adding N. The highest uptake of tritium was reported for the sample exposed to D+He plasma which corresponds to the largest – 18nm, near surface damage zone revealed by TEM. Lowest tritium accumulation was observed for samples exposed to D+Ar and D+Ne plasmas, which corresponds to the shallowest near surface damage zone, as confirmed by TEM.

Highlights

The main candidates for plasma-facing materials in fusion devices are currently tungsten and beryllium [1]
The presence of different subsurface defects created by the mixed plasma exposure will influence the retention of hydrogen isotopes [7,8], which is of prime importance for the operation of a fusion device
Many studies has been undertaken to understand the retention of tungsten exposed to mixed plasma, the detailed surface morphology studies correlated with fuel trapping are insufficient

Summary

Introduction

The main candidates for plasma-facing materials in fusion devices are currently tungsten and beryllium [1]. Many studies show a positive effect of gas puffing on spreading the energy over a large divertor or first wall area [3,4,5,6]. The presence of He as a reaction product from the DT fusion reaction is unavoidable. All these impurities will have an effect on tungsten behavior under the plasma exposure. Many studies has been undertaken to understand the retention of tungsten exposed to mixed plasma, the detailed surface morphology studies correlated with fuel trapping are insufficient

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