JuLib | Articles & more

1

Modelling of carbon deposition from methane and ethene injection through graphite and tungsten test limiters in TEXTOR

Ding, R.
2010

Plasma physics and controlled fusion, 52 (2010) S. 045005

2

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

Litnovsky, A.
2009

Journal of nuclear materials, 390-391 (2009)

3

Journal Article

Modelling of Be transport in PSI experiment at PISCES-B

Borodin, D.
2009

Journal of nuclear materials, 390-391 (2009)

4

Journal Article

Simulation of light emission from hydrocarbon injection in TEXTOR using the ERO code

Ding, R.
2009

Plasma physics and controlled fusion, 51 (2009) S. 055019

5

Journal Article

Castellated structures for ITER: Differences of impurity deposition and fuel accumulation in the toroidal and poloidal gaps

Litnovsky, A.
2009

Journal of nuclear materials, 386-388 (2009) S. 809 - 812

6

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

7

Journal Article

Simulation of light emission of hydrocarbon injection experiments at TEXTOR using the ERO code

Ding, R.
2008

Verhandlungen der Deutschen Physikalischen Gesellschaft, 43 (2008) S. PIV.3

8

Journal Article

Modelling of chemical erosion mitigation experiments at PISCES-B using the 3D Monte-Carlo code ERO

Borodin, D.
2007

Physica scripta, T128 (2007) S. 127 - 132

9

Journal Article

Hydrocarbon injection for quantification of chemical erosion yields in tokamaks

Brezinsek, S.
2007

Journal of nuclear materials, 363-365 (2007) S. 1119 - 1128

10

Journal Article

Study of Local Carbon Transport on Graphite, Tungsten und Molybdenum test limiters in TEXTOR by 12Ch4 Tracer Injection

Kreter, A.
2007

Journal of nuclear materials, 363-365 (2007) S. 179 - 183

11

Journal Article

Modelling of tritium retention and target lifetime of the ITER divertor using the ERO code

Kirschner, A.
2007

Journal of nuclear materials, 363-365 (2007) S. 91 - 95

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