Publications of P. Wienhold
All genres
Journal Article (29)
2013
Journal Article
438, pp. S746 - S749 (2013)
Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR. Journal of Nuclear Materials
Journal Article
438, pp. S602 - S606 (2013)
Material deposition and migration processes with resonant magnetic perturbation fields at TEXTOR. Journal of Nuclear Materials
Journal Article
53, 073033 (7pp) (2013)
First studies of ITER-diagnostic mirrors in a tokamak with an all-metal interior: results of the first mirror test in ASDEX Upgrade. Nuclear Fusion 2011
Journal Article
415 (1), pp. S735 - S739 (2011)
Multi machine scaling of fuel retention in 4 carbon dominated tokamaks. Journal of Nuclear Materials 2009
Journal Article
386-388, pp. 809 - 812 (2009)
Castellated structures for ITER: Differences of impurity deposition and fuel accumulation in the toroidal and poloidal gaps. Journal of Nuclear Materials
Journal Article
390-391, pp. 556 - 559 (2009)
Investigations of castellated structures for ITER: The effect of castellation shaping and alignment on fuel retention and impurity deposition in gaps. Journal of Nuclear Materials
Journal Article
T138, 014031 (5pp) (2009)
Qualification of tungsten coatings on plasma-facing components for JET. Physica Scripta 2008
Journal Article
50 (9), 095008 (10pp) (2008)
Effect of surface roughness and substrate material on carbon deposition in tokamak TEXTOR. Plasma Physics and Controlled Fusion 2007
Journal Article
T128, pp. 35 - 39 (2007)
Long-term erosion and deposition studies of the main graphite limiter in TEXTOR. Physica Scripta
Journal Article
367-370, pp. 1481 - 1486 (2007)
Carbon transport, deposition and fuel accumulation in castellated structures exposed in TEXTOR. Journal of Nuclear Materials
Journal Article
T128, pp. 45 - 49 (2007)
Castellated structures for ITER: the influence of the shape of castellation on the impurity deposition and fuel accumulation in gaps. Physica Scripta
Journal Article
T128, pp. 29 - 34 (2007)
DiMES studies of temperature dependence of carbon erosion and re-deposition in DIII-D divertor. Physica Scripta
Journal Article
363-365, pp. 276 - 281 (2007)
Divertor and Midplane Materials Evaluation System in DIII-D. Journal of Nuclear Materials 2006
Journal Article
48, pp. 1401 - 1412 (2006)
Investigation of carbon transport by 13CH4 injection through graphite and tungsten test limiters in TEXTOR. Plasma Physics and Controlled Fusion
Journal Article
81, pp. 221 - 225 (2006)
Analyses of metallic first mirror samples after long term plasma exposure in Tore Supra. Fusion Engineering and Design 2005
Journal Article
337-339, pp. 1116 - 1120 (2005)
Exposure of metal mirrors in the scrape-off layer of TEXTOR. Journal of Nuclear Materials 2004
Journal Article
T111, pp. 55 - 61 (2004)
Carbon Erosion and Migration in Fusion Devices. Physica Scripta 2003
Journal Article
313-316, pp. 62 - 66 (2003)
Arcing at B4C-covered limiters exposed to a SOL-plasma. Journal of Nuclear Materials
Journal Article
313-316, pp. 377 - 382 (2003)
Erosion and deposition at the ALT-II limiter of TEXTOR. Journal of Nuclear Materials
Journal Article
70, pp. 423 - 428 (2003)
Ion beam analysis methods in the studies of plasma facing materials in controlled fusion devices. Vacuum