Publikationen von P. Wienhold
Alle Typen
Zeitschriftenartikel (29)
1.
Zeitschriftenartikel
438, S. S746 - S749 (2013)
Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR. Journal of Nuclear Materials 2.
Zeitschriftenartikel
: Material deposition and migration processes with resonant magnetic perturbation fields at TEXTOR. Journal of Nuclear Materials 438, S. S602 - S606 (2013)
3.
Zeitschriftenartikel
: 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 53, 073033 (7pp) (2013)
4.
Zeitschriftenartikel
: Multi machine scaling of fuel retention in 4 carbon dominated tokamaks. Journal of Nuclear Materials 415 (1), S. S735 - S739 (2011)
5.
Zeitschriftenartikel
: Castellated structures for ITER: Differences of impurity deposition and fuel accumulation in the toroidal and poloidal gaps. Journal of Nuclear Materials 386-388, S. 809 - 812 (2009)
6.
Zeitschriftenartikel
: 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 390-391, S. 556 - 559 (2009)
7.
Zeitschriftenartikel
T138, 014031 (5pp) (2009)
Qualification of tungsten coatings on plasma-facing components for JET. Physica Scripta 8.
Zeitschriftenartikel
: Effect of surface roughness and substrate material on carbon deposition in tokamak TEXTOR. Plasma Physics and Controlled Fusion 50 (9), 095008 (10pp) (2008)
9.
Zeitschriftenartikel
T128, S. 35 - 39 (2007)
Long-term erosion and deposition studies of the main graphite limiter in TEXTOR. Physica Scripta 10.
Zeitschriftenartikel
: Carbon transport, deposition and fuel accumulation in castellated structures exposed in TEXTOR. Journal of Nuclear Materials 367-370, S. 1481 - 1486 (2007)
11.
Zeitschriftenartikel
: Castellated structures for ITER: the influence of the shape of castellation on the impurity deposition and fuel accumulation in gaps. Physica Scripta T128, S. 45 - 49 (2007)
12.
Zeitschriftenartikel
: DiMES studies of temperature dependence of carbon erosion and re-deposition in DIII-D divertor. Physica Scripta T128, S. 29 - 34 (2007)
13.
Zeitschriftenartikel
: Divertor and Midplane Materials Evaluation System in DIII-D. Journal of Nuclear Materials 363-365, S. 276 - 281 (2007)
14.
Zeitschriftenartikel
: Investigation of carbon transport by 13CH4 injection through graphite and tungsten test limiters in TEXTOR. Plasma Physics and Controlled Fusion 48, S. 1401 - 1412 (2006)
15.
Zeitschriftenartikel
: Analyses of metallic first mirror samples after long term plasma exposure in Tore Supra. Fusion Engineering and Design 81, S. 221 - 225 (2006)
16.
Zeitschriftenartikel
: Exposure of metal mirrors in the scrape-off layer of TEXTOR. Journal of Nuclear Materials 337-339, S. 1116 - 1120 (2005)
17.
Zeitschriftenartikel
T111, S. 55 - 61 (2004)
Carbon Erosion and Migration in Fusion Devices. Physica Scripta 18.
Zeitschriftenartikel
: Arcing at B4C-covered limiters exposed to a SOL-plasma. Journal of Nuclear Materials 313-316, S. 62 - 66 (2003)
19.
Zeitschriftenartikel
313-316, S. 377 - 382 (2003)
Erosion and deposition at the ALT-II limiter of TEXTOR. Journal of Nuclear Materials 20.
Zeitschriftenartikel
70, S. 423 - 428 (2003)
Ion beam analysis methods in the studies of plasma facing materials in controlled fusion devices. Vacuum