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Klimov, N.; Podkovyrov, V.; Zhitlukhin, A.; Kovalenko, D.; Linke, J.; Pintsuk, G.; Landman, I.; Pestchanyi, S.; Bazylev, B.; Janeschitz, G.; Loarte, A.; Merola, M.; Hirai, T.; Federici, G.; Riccardi, B.; Mazul, I.; Giniyatulin, R.; Khimchenko, L.; Koidan, V.
Journal of nuclear materials, 08/2011, Letnik: 415, Številka: 1Journal Article, Conference Proceeding
The paper concerns experimental investigations of plasma facing components erosion under the plasma heat loads expected in ITER divertor during transient events such as the Type I Edge-Localized Modes and the disruptions. The experiments were carried out at the TRINITI plasma gun QSPA-T. The carbon fiber composite and tungsten macrobrush targets designed for ITER were exposed to multiple plasma pulses of duration 0.5ms and deposited energy in the range of 0.2–2.5MJ/m2. Between some of the pulses the eroded surface was analyzed with profilometric measurements and electron microscopy. The CFC erosion is determined mainly by damages to the PAN-fibers. While the energy increases from 0.2 to 2.4MJ/m2 the removed layer of PAN-fibers area increases from 0.01 to 10μm per pulse. The erosion of tungsten (pure and lanthanum oxide-doped tungsten) is shown to be determined mainly by crack formation, melt layer movement and droplets ejection.
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JCR | SNIP | JCR | SNIP | JCR | SNIP | JCR | SNIP |
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in: SICRIS
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