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This paper is concerned with investigation of an erosion of the ITER-like divertor plasma facing components under plasma heat loads expected during the Type I ELMs in ITER. These experiments were carried out on plasma accelerator QSPA at the SRC RF TRINITI under EU/RF collaboration. Targets were exposed by series repeated plasma pulses with heat loads in a range of 0.5-1.5 MJ/m(2) and pulse duration 0.5 ms. Erosion of CFC macrobrushes was determined mainly by sublimation of PAN-fibres that was less than 2.5 mu m per pulse. The CFC erosion was negligible at the energy density less than 0.5 MJ/m(2) and was increased to the average value 0.3 mu m per pulse at 1.5 MJ/m(2). The pure tungsten macrobrushes erosion was small in the energy range of 0.5-1.3 MJ/m(2). The sharp growth of tungsten erosion and the intense droplet ejection were observed at the energy density of 1.5 MJ/m(2).

Additional information

Authors: ZHITLUKHIN A, SRC RF TRINITI, Moscow Region (RU);KLIMOV N, SRC RF TRINITI, Moscow Region (RU);PODKOVYROV V, SRC RF TRINITI, Moscow Region (RU);SAFRONOV V, SRC RF TRINITI, Moscow Region (RU);MAYNASHEV V, SRC RF TRINITI, Moscow Region (RU);LEVASHOV V, SRC RF TRINITI, Moscow Region (RU);MUZICHENKO A, SRC RF TRINITI, Moscow Region (RU);LINKE J, Forschungszentrum Jülich GmbH, Jülich (DE);HIRAI T, Forschungszentrum Jülich GmbH, Jülich (DE);LANDMAN I, Forschungszentrum Karlsruhe, Karlsruhe (DE);BAZYLEV B, Forschungszentrum Karlsruhe, Karlsruhe (DE);PESTCHANYI S, Forschungszentrum Karlsruhe, Karlsruhe (DE);LOARTE A, EFDA Close Support Unit, Garching (DE);MEROLA M, EFDA Close Support Unit, Garching (DE);FEDERICI G, ITER JWS, Garching (DE)
Bibliographic Reference: An article published in: Journal of Nuclear Materials (2007), online edition
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Record Number: 200718988 / Last updated on: 2007-03-26
Original language: en
Available languages: en
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