Trapping of deuterium implanted in carbon and silicon: A calibration for particle-energy measurements in the plasma boundary of tokamaks

Deuterium retention in carbon fibre composites NB31 and N11 irradiated with low-energy D ions

“…1). No saturation was reached as had been previously observed in pyrolytic graphite [2]. An increase of the irradiation temperature leads to the decrease of the D concentration both in the near-surface layers and in the bulk of the CFC NB31 (Fig.…”

“…In dense pyrolytic graphite the retention of implanted hydrogen isotopes saturates when the concentration in the implantation range reaches about 30 at% [ 2 ]. In fine grain graphites with a typical density around 1,85 g/cm 3 a slow increase in retention with ion fluence was found [ 3 , 4 ].In doped CFC materials, a steeper increase in retention and diffusion far beyond the ion range was observed [ 5 ].…”

Hydrogen isotope retention in plasma-facing materials: review of recent experimental results

“…In the case of 200 eV D ion irradiation at room temperature, the retention increase proceeds proportional to Φ 0.5 at high ion fluences. No saturation was reached as observed in pyrolytic graphite [20]. The relatively low D retention in the CFC N11 exposed to the PISCES-A plasma at 473 K, as compared to the CFC NB31 irradiated with D ions, can only partly be explained by the lower ion energies.…”

Deuterium retention in rhenium-doped tungsten

“…A fraction of the incident ions can be neutralized at the entrance apertures, resulting in 1.5-3% fraction of high-energy neutrals in the decelerated beam [6,7]. This leads to a 10% uncertainty of the low-energy particles fluence [8]. Ion implantations were always performed at normal incidence and room temperature.…”