Progress of the European R&amp;D on plasma–wall interactions, neutron effects and tritium removal in ITER plasma facing materials

Wu, C.H.; Alessandrini, C.; Bonal, J.P.; Davis, James W.; Haasz, A.A.; Jacob, W.; Kallenbach, A.; Keinonen, J.; Kornejew, P.; Moormann, R.; Philipps, V.; Roth, J.; Scaffidi-Argentina, F.; Würz, H.

doi:10.1016/s0920-3796(01)00255-1

Cited by 20 publications

(14 citation statements)

References 22 publications

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“…During the normal operation, in the ITER divertor zone steady state plasma parameters are expected to be $5-20 MW m À2 heat, $10 24 H + m À2 s À1 (1-10 eV) protons, and $10 22 -10 24 He 2+ m À2 s À1 (<500 eV) helium ions [1][2][3]. In contrast, a 10 m radius IFE chamber, such as the high average power laser (HAPL) reactor [4] is expected to be exposed to helium and deuterium ions ranging in energy from 1 keV to 10 MeV, with a low energy helium flux of about $10 15 m À2 in the range of 100-200 keV and a high energy helium flux of $10 16 m À2 between 200 keV and 10 MeV (per shot from a 365 MJ target).…”

Section: Introductionmentioning

confidence: 99%

A description of stress driven bubble growth of helium implanted tungsten

Sharafat

Takahashi

Nagasawa

et al. 2009

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

A description of stress driven bubble growth of helium implanted tungsten

Sharafat

Takahashi

Nagasawa

et al. 2009

Journal of Nuclear Materials

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“…The problems of plasma-wall interaction were two kinds: the contamination of the plasma preventing suitable conditions for fusion to take place, and damage to the components of the containment vessel leading to possible component failure [5]. Therefore controlling plasma-wall interactions is critical to achieving high performance in present day Tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors [6].…”

Section: Introductionmentioning

confidence: 99%

The Study of Surface Properties of Tokamak First Wall Using TiN Coated on Stainless Steel

2015

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Structural properties of the synthesized TiN thin film on 316L stainless steel (S.S.316L) were studied to determine its potential application as a protective layer for first wall of Tokamaks. For this purpose we deposited TiN on stainless steel 316L (TiN/S.S.316L) via DC magnetron sputtering method and annealing at 700°C. Before and after exposure, samples were analyzed by using scanning electron microscopy (SEM), X-ray diffraction (XRD) and a spectrophotometer. The XRD analysis for studying crystalline structure of samples shows the position and intensity of XRD peaks has changed after exposing to 500 shots of Tokamak. It was found that the S.S.316L sample was severely damaged, its reflection dropped significantly but the SEM images show that plasma exposure has not created any cracks and lines on the surface of the TiN/S.S.316L sample and mass of dust particle has been assembled in some area of the sample.

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“…In nuclear fusion power research, the plasma-facing material is any material used to construct the plasma-facing components, those components exposed to the plasma within which nuclear fusion occurs, and particularly the material used for the lining or first wall of the reactor vessel [5][6][7][8][9]. Selection of the plasma facing mirrors material and research on the behavior of these mirrors under plasma irradiation are currently underway all over the world [10,11].…”

Section: Introductionmentioning

confidence: 99%

“…Currently there is a great interest in designing and engineering thin films with morphologies tailored to specific requirements for various application fields. The connection between the surface morphology of the films and functionality is especially important for optical applications, as surface microstructure generates scattering and stray light in optical components [6][7][8]. Physical vapor deposition (PVD) techniques such as direct-current (DC) magnetron sputtering, ion plating, and plasma-based ion implantation are employed to deposit TiN thin films [16][17][18].…”

Section: Introductionmentioning

confidence: 99%

Effects of Annealing on TiN Thin Film Growth by DC Magnetron Sputtering

Jafari

Ghoranneviss

Elahi

et al. 2014

Advances in Mechanical Engineering

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We have reviewed the deposition of titanium nitride (TiN) thin films on stainless steel substrates by a DC magnetron sputtering method and annealing at different annealing temperatures of 500, 600, and 700 ∘ C for 120 min in nitrogen/argon atmospheres. Effects of annealing temperatures on the structural and the optical properties of TiN films were investigated using X-ray diffraction (XRD), atomic force microscope (AFM), field emission scanning electron microscopy (FESEM), and UV-VIS spectrophotometer. Our experimental studies reveal that the annealing temperature appreciably affected the structures, crystallite sizes, and reflection of the films. By increasing the annealing temperature to 700 ∘ C crystallinity and reflection of the film increase. These results suggest that annealed TiN films can be good candidate for tokamak first wall due to their structural and optical properties.

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Progress of the European R&D on plasma–wall interactions, neutron effects and tritium removal in ITER plasma facing materials

Cited by 20 publications

References 22 publications

A description of stress driven bubble growth of helium implanted tungsten

A description of stress driven bubble growth of helium implanted tungsten

The Study of Surface Properties of Tokamak First Wall Using TiN Coated on Stainless Steel

Effects of Annealing on TiN Thin Film Growth by DC Magnetron Sputtering

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