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121

Choice of Divertor Tungsten Coating Thickness fro the JET ITER-like Wall Project

Matthews, G. F.
2008

122

Talk (non-conference)

R&D on diagnostic mirrors at Forschungszentrum Jülich

Litnovsky, A.
2008

123

Talk (non-conference)

Investigations of castellated structures for ITER

Litnovsky, A.
2008

124

Journal Article

First tests of diagnostic mirrors in a tokamak divertor: An overview of experiments in DIII-D

Litnovsky, A.
2008

Fusion engineering and design, 83 (2008) S. 79 - 89

125

Conference Presentation

ERO modelling of hydrocarbon transport and spectroscopy for injection experiments at TEXTOR

Ding, R.
2008

126

Conference Presentation

Implementation of metastable states into ERO code: modelling of Be experiments at PISCES-B

Borodin, D.
2008

127

Conference Presentation

Hydrogen level in JET

Brezinsek, S.
2008

128

Conference Presentation

Fuel retention experiments in JET recent results in L- and H-mode

Brezinsek, S.
2008

129

Modelling of erosion and deposition of ITER limiters during ramp phases

Kirschner, A.
2008

130

Comparison of 13C2H4 and 13CH4 injection through C and W limiters in TEXTOR

Brezinsek, S.
2008

131

Conference Presentation

Fuel retention in carbon based materials including ITER-grade CFC NB41 exposed in TEXTOR and PISCES-A

Kreter, A.
2008

132

Journal Article

Modelling of 13CH4 injection experiments with graphite and tungsten test limiters in TEXTOR using the coupled code ERO-SDTrimSP

Droste, S.
2008

Plasma physics and controlled fusion, 50 (2008) S. 015006

133

Journal Article

Modelling of carbon migration during JET 13C injection experiments

Strachan, J. D.
2008

Nuclear fusion, 48 (2008) S. 105002

134

Conference Presentation

Development of wall conditioning and tritium removal techniques for ITER and future fusion devices in TEXTOR

Philipps, V.
2008

135

Industrial scale 10 um W coating of CFC tiles for the ITER-like Wall project at JET

Ruset, C.
2008

136

Journal Article

Effect of surface roughness and substrate material on carbon deposition in tokamak TEXTOR

Kreter, A.
2008

Plasma physics and controlled fusion, 50 (2008) S. 095008

137

Journal Article

Tritium inventory in ITER plasma-facing materials and tritium removal procedures

Roth, J.
2008

Plasma physics and controlled fusion, 50 (2008) S. 103001

138

Conference Presentation

Laser induced spectroscopy diagnostics for insitu characterization of rist walls in plasma devices

Schweer, B.
2008

139

Dust studies in DIII-D and TEXTOR

Rudakov, D. L.
2008

140

A new look at the specification of ITER plasmas wall interaction and tritium retention

Roth, J.
2008

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