Overview of comprehensive characterisation of erosion zones on plasma facing components

Rubel, M.; Fortuna, E.; Kreter, A.; Wessel, E.; Philipps, V.; Kurzydłowski, Krzysztof J.

doi:10.1016/j.fusengdes.2005.07.037

Cited by 30 publications

(11 citation statements)

References 34 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The erosion of carbon-based materials originated from the impact of energetic ion particles has long been a concern in fusion experiments [36][37][38][39][40][41]. The erosion by physical and chemical sputtering represented significant material loss contributing to not only reduction of the lifetime of carbon-based facing materials but also impurity buildup in the plasma and amorphous carbon film deposition at other vessel locations [42].…”

Section: Discussionmentioning

confidence: 99%

Influence of H+ ion irradiation on the surface and microstructural changes of a nuclear graphite

Yang

Choe

Jin

et al. 2012

Fusion Engineering and Design

View full text Add to dashboard Cite

Section: Discussionmentioning

confidence: 99%

Influence of H+ ion irradiation on the surface and microstructural changes of a nuclear graphite

Yang

Choe

Jin

et al. 2012

Fusion Engineering and Design

View full text Add to dashboard Cite

“…The ALT-II limiter surface features a pronounced distinction between the erosion and the deposition areas [13,14]. The deposition zone on that limiter is also the main 0031-8949/11/014006+05$33.00 (1) with a specimen of the ALT-II tile (2) and a pure graphite holder also serving the reference material (3).…”

Section: Methodsmentioning

confidence: 99%

Fuel re-absorption by thermally treated co-deposited carbon layers

Ivanova¹,

Rubel²,

Philipps³

et al. 2011

Phys. Scr.

View full text Add to dashboard Cite

Systematic studies have been conducted to address the fuel re-absorption by carbon deposits under repeated exposure to plasma after cleaning procedures. The investigation was done with graphite tiles from ALT-II (Advanced Limiter Test II), i.e. the main limiter at the TEXTOR tokamak. Pure graphite plates were used as the reference material. The experimental programme comprised the following: pre-characterization of specimens; D desorption by baking the tile at 1273 K; surface analyses of the fuel-depleted layers; exposure to deuterium in a laboratory plasma device and in TEXTOR; and quantitative assessment of deuterium re-absorption. The main result is that fuel retention in the re-exposed deposits is 30-40 times lower than that in the original co-deposit, showing that fuel re-absorption does not lead to an immediate re-saturation of deposits. Annealing at high temperatures enhances layer brittleness, leading eventually to detachment of co-deposits.

show abstract

“…As a consequence, more carbon impurity will be released into the plasma, which may induce the loss of plasma energy and limit operation for safety reason [2][3][4][5]. To enhance properties of carbon materials, processes associated with the erosion have been in focus of plasma-material interaction studies [6].…”

Section: Introductionmentioning

confidence: 99%

Microstructure changes and properties of TiC-coated carbon fiber-reinforced carbon composites

Wang

Guo

Zhang

et al. 2008

Fusion Engineering and Design

View full text Add to dashboard Cite

Overview of comprehensive characterisation of erosion zones on plasma facing components

Cited by 30 publications

References 34 publications

Influence of H+ ion irradiation on the surface and microstructural changes of a nuclear graphite

Influence of H+ ion irradiation on the surface and microstructural changes of a nuclear graphite

Fuel re-absorption by thermally treated co-deposited carbon layers

Microstructure changes and properties of TiC-coated carbon fiber-reinforced carbon composites

Contact Info

Product

Resources

About