17–22 May 2026
marinaforum REGENSBURG
Europe/Berlin timezone

3.047 The effect of surface-near helium on deuterium retention in tungsten and EUROFER

21 May 2026, 15:55
2h 10m
Poster C. Plasma Fueling, Particle Exhaust and Control, Tritium Retention Postersession 3

Speaker

Sabina Markelj (Jožef Stefan Institute)

Description

It was shown experimentally for tungsten, that He retained close to the surface influences transport and retention of hydrogen isotopes (HI). Namely, experiments using He seeded D plasmas, showed that the addition of He leads to reduced blistering accompanied by reduced D retention [1].
Recently, we have performed a systematic series of D exposures in tungsten where He was pre-implanted near the surface [2]. 20 MeV W irradiation was performed before or after He implantation to create defects within the first 3 µm. The defects created by W ions were used to trap D that was penetrating through the He surface layer. Using 3He nuclear reaction analysis (NRA) made it hence possible to quantify D transport beyond the He layer. D and He depth profiling showed increased D retention at the depth where He was implanted, but D retention in the bulk was reduced five times as compared to a He-free reference sample. Transmission electron microscopy showed nanometer-sized bubbles where He was implanted. From this we concluded that the observed D retention in He irradiated samples is due to D trapping at He bubbles and that the He containing microstructure enhances D re-emission. The same methodology was applied to EUROFER97 to clarify the effect of surface-near helium on deuterium transport into and retention in the bulk. To quantify the influence on D uptake at the surface, He was implanted into EUROFER97 samples close to the surface with 1 keV ions with different fluences and at different temperatures. Samples were then exposed to a low flux, low energy (100 eV/D) D ion beam at 370 K. One He-free W-irradiated EUROFER97 reference sample was also exposed only to low energy D ions for comparison. The defects created by W ions trap penetrating D and make it hence possible to quantify D transport below the He layer using NRA. Measured D depth profiles show reduced D uptake in the He-irradiated samples with major D retention near the surface where He is implanted. The D uptake is reduced by a factor of two compared to He-free sample. Surface analysis of the sample with the largest He fluence of 5.5×10^{21} He/m2 showed He bubbles near the surface. Results will be discussed and compared to tungsten.
[1] M. Baldwin et al. Nucl. Fusion 51 (2011) 103021; Nucl. Fusion 57 (2017) 076031
[2] Markelj et al. Nucl. Mater. Energy 45 (2025) 101981

Author

Sabina Markelj (Jožef Stefan Institute)

Co-authors

Dr Andreja Šestan Zavašnik (Jožef Stefan Institute) Dr Janez Zavašnik (Jožef Stefan Institute) Thomas Schwarz-Selinger (MPPL)

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