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Akademický článek

Long-range correlation properties of quasi-coherent modes at TEXTOR

Autor: A Krämer-Flecken, S Soldatov, Y Xu, H Arnichand, S Hacquin, R Sabot, the TEXTOR team

Publikováno v: New Journal of Physics, Vol 17, Iss 7, p 073007 (2015)

The paper reports on the first measurements of long-range correlations along field lines in the center of ohmic plasmas at TEXTOR. The measurements are performed with correlation reflectometry. For the first time the poloidal, toroidal and radial ext

Externí odkaz: https://doaj.org/article/c986d21cce1e4c7cb6eb7f469ffd315e

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Tritium loading study of tungsten pre-exposed to TEXTOR plasmas

Autor: K. Sugiyama, A. Taguchi, R.-D. Penzhorn, Hiroaki Kurishita, Textor Team, Arkadi Kreter, Yoshio Ueda, M. Saito, Yuji Torikai, V. Philipps, M. Zlobinski

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, v.438, S1121-S1124 (2013)

The uptake of tritium at 573 K by polycrystalline tungsten limiter material pre-exposed to TEXTOR plasmas was investigated by the imaging plate technique (IP) and found to be mostly non-homogeneous on the plasma facing surface. Particularly high conc

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7a3f1f1e52ceb170bbc85d00ad8fe64d
https://doi.org/10.1016/j.jnucmat.2013.01.247

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Tritium Trapping on the Plasma Irradiated Tungsten Surface

Autor: Kanetsugu Isobe, V. Philipps, Arkadi Kreter, Yoshio Ueda, Textor Team, M. Zlobinski, V.Kh. Alimov, R.-D. Penzhorn, Hiroaki Kurishita, M. Oyaidzu, Toshihiko Yamanishi, Yuji Torikai

Publikováno v: Fusion Science and Technology. 67:619-622

Tungsten (W) specimens previously exposed to deuterium (D) plasmas both in the TEXTOR tokamak and high flux linear plasma generator (LPG) were subsequently loaded with tritium at 573 K for 3 h. Ret...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::49b7ce2a08758c24bd2d8d753b0ace04
https://doi.org/10.13182/fst14-t94

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Overview of material migration and mixing, fuel retention and cleaning of ITER-like castellated structures in TEXTOR

Publikováno v: Journal of Nuclear Materials, v.415, S289-S292 (2011)
JOURNAL OF NUCLEAR MATERIALS
Supplement
Journal of Nuclear Materials

Plasma-facing components (PFCs) in ITER will be castellated by splitting them into small-size blocks to maintain the thermo-mechanical stability. However, there are concerns in particular on retention of codeposited radioactive fuel in the gaps. An R

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b24faefd1e8ac74b85942a2bef898387
https://doi.org/10.1016/j.jnucmat.2010.12.018

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Runaway generation during disruptions in JET and TEXTOR

Autor: Lehnen, M., Abdullaev, S. S., Arnoux, G., Bozhenkov, S. A., Jakubowski, M. W., Jaspers, R., Plyusnin, V. V., Riccardo, V., Samm, U., JET EFDA Contributors, TEXTOR Team

Publikováno v: Journal of Nuclear Materials
STARTPAGE=740;ENDPAGE=746;TITLE=None
Journal of Nuclear Materials, v.390-391, 740-746 (2009)

Runaway electrons generated during ITER disruptions are of concern for the integrity of the plasma facing components. It is expected that a power of up to 8 GW is exposed to ITER PFCs. We present ill this article observations from JET and TEXTOR on t

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2e921cc4047acd7eea7c6a1cecc56451
https://doi.org/10.1016/j.jnucmat.2009.01.200

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Investigations of castellated structures for ITER: The effect of castellation shaping and alignment on fuel retention and impurity deposition in gaps

Autor: Oliver Schmitz, P. Wienhold, D. Borodin, Arkadi Kreter, Andrey Litnovsky, Uwe Breuer, S. Richter, K. Krieger, Gennady Sergienko, V. Philipps, U. Samm, A. Kirschner, Textor Team, Dmitry Matveev

Publikováno v: Journal of Nuclear Materials
JOURNAL OF NUCLEAR MATERIALS
Journal of Nuclear Materials, v.390-391, 556-559 (2009)

Castellation will be used in divertor and first wall components to provide thermo-mechanical stability of ITER. Radioactive fuel may be stored in the gaps of castellated structures representing a safety issue for ITER. Tungsten castellated structures

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0103f41a0210fe6f4ddbe04e15fd810e
https://doi.org/10.1016/j.jnucmat.2009.01.097

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Long-term erosion and deposition studies of the main graphite limiter in TEXTOR

Autor: U. Samm, Gennady Sergienko, V. Philipps, M. Mayer, P. Wienhold, Textor Team, Arkadi Kreter, A. Kirschner, J. Likonen

Publikováno v: Kreter, A, Kirschner, A, Wienhold, P, Likonen, J, Mayer, M, Philipps, V, Samm, U & Sergienko, G 2007, ' Long-term erosion and deposition studies of the main graphite limiter in TEXTOR ', Physica Scripta, vol. T128, pp. 35-39 . https://doi.org/10.1088/0031-8949/2007/T128/007
Physica Scripta, v.T128, 35-39 (2007)
Physica Scripta

Erosion and deposition behaviour of the TEXTOR main toroidal belt limiter ALT-II has been studied for two generations of limiter tiles with different surface shapes. Two specially prepared tiles with marker holes were subsequently exposed during expe

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::aa90535ae45befe90e0ee65e63941d17
https://doi.org/10.1088/0031-8949/2007/t128/007

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