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

被引:11
作者
Ding, R. [1 ,2 ]
Kirschner, A. [2 ]
Borodin, D. [2 ]
Brezinsek, S. [2 ]
Kreter, A. [2 ]
Tokar, M. Z. [2 ]
Chen, J. [1 ]
Schmitz, O. [2 ]
Philipps, V. [2 ]
Samm, U. [2 ]
Li, J. [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
[2] Forschungszentrum Julich, Inst Energieforsch Plasmaphys, EURATOM Assoc, D-52425 Julich, Germany
关键词
SCRAPE-OFF LAYER; CHEMICAL EROSION; HYDROCARBON RADICALS; IMPURITY TRANSPORT; DIVERTOR PLASMAS; FUSION DEVICES; SIMULATION; JET; REDEPOSITION; TOKAMAK;
D O I
10.1088/0741-3335/52/4/045005
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The 3D Monte Carlo code ERO has been used to simulate dedicated TEXTOR experiments in which methane (CH4)-C-13 and ethene (C2H4)-C-13 were injected into the plasma through graphite and tungsten spherical limiters to investigate local carbon transport and deposition. Spectroscopy was used to follow the observable hydrocarbon break-up products, and the local C-13 deposition efficiency was measured by post-mortem surface analysis. The experimental observations showing the dependence of the C-13 deposition on substrate and gas have been modelled. The main uncertain input parameters for the modelling, as C-12 concentration in the background plasma, effective sticking coefficient for hydrocarbons and enhanced erosion of redeposited carbon, have been defined by benchmarking between modelling and experiment. With the same set of parameters, the modelled C-13 deposition efficiencies are in good agreement with the experimental ones (0.8-2.1%). Also, the observed distribution of C-13 deposition on the limiter surfaces is well reproduced by modelling. The higher amount of C-13 deposition on graphite compared with tungsten limiter is mainly due to the higher reflection of carbon on tungsten and the higher physical sputtering of carbon film on top of the tungsten compared with graphite. The larger amount of C-13 deposition for (C2H4)-C-13 instead of (CH4)-C-13 injection can be explained by more C-13 returning to the limiter surface from (C2H4)-C-13 injection than (CH4)-C-13 injection, which is mainly determined by the different masses and reaction rate coefficients.
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页数:14
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共 45 条
[1]   13C transport studies in L-mode divertor plasmas on DIII-D [J].
Allen, SL ;
Wampler, WR ;
McLean, AG ;
Whyte, DG ;
West, WP ;
Stangeby, PC ;
Brooks, NH ;
Rudakov, DL ;
Phillips, V ;
Rubel, M ;
Matthews, GF ;
Nagy, A ;
Ellis, R ;
Bozek, AS .
JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :30-34
[2]   Molecular dynamics calculation of carbon/hydrocarbon reflection coefficients on a hydrogenated graphite surface [J].
Alman, DA ;
Ruzic, DN .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :182-186
[3]   VELOCITY DISTRIBUTION OF CARBON-ATOMS RELEASED FROM A TOKAMAK LIMITER BY CHEMICAL AND PHYSICAL SPUTTERING [J].
BOGEN, P ;
RUSBULDT, D .
NUCLEAR FUSION, 1992, 32 (06) :1057-1061
[4]   Hydrocarbon injection for quantification of chemical erosion yields in tokamaks [J].
Brezinsek, S. ;
Pospieszczyk, A. ;
Borodin, D. ;
Stamp, M. F. ;
Pugno, R. ;
McLean, A. G. ;
Fantz, U. ;
Manhard, A. ;
Kallenbach, A. ;
Brooks, N. H. ;
Groth, M. ;
Mertens, Ph. ;
Philipps, V. ;
Samm, U. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 363 :1119-1128
[5]   Characterization of the deuterium recycling flux in front of a graphite surface in the TEXTOR tokamak [J].
Brezinsek, S ;
Sergienko, G ;
Pospieszczyk, A ;
Mertens, P ;
Samm, U ;
Greenland, PT .
PLASMA PHYSICS AND CONTROLLED FUSION, 2005, 47 (04) :615-634
[6]   Comparison of 13C2H4 and 13CH4 injection through graphite and tungsten limiters in TEXTOR [J].
Brezinsek, S. ;
Kreter, A. ;
Ding, R. ;
Hirai, T. ;
Kirschner, A. ;
Philipps, V. ;
Pospieszczyk, A. ;
Samm, U. ;
Schweer, B. ;
Schmitz, O. ;
Sugiyama, K. ;
Tanabe, T. ;
Ueda, Y. .
PHYSICA SCRIPTA, 2009, T138
[7]   Overview of material re-deposition and fuel retention studies at JET with the Gas Box divertor [J].
Coad, JP ;
Likonen, J ;
Rubel, M ;
Vainonen-Ahlgren, E ;
Hole, DE ;
Sajavaara, T ;
Renvall, T ;
Matthews, GF .
NUCLEAR FUSION, 2006, 46 (02) :350-366
[8]   Internal magnetic field structure and parallel electric field profile evolution during the sawtooth cycle in MST [J].
Deng, B. H. ;
Ding, W. X. ;
Brower, D. L. ;
Almagri, A. F. ;
McCollam, K. J. ;
Ren, Y. ;
Prager, S. C. ;
Sarff, J. S. ;
Reusch, J. ;
Anderson, J. K. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2008, 50 (11)
[9]   Impurity transport modelling in edge plasmas of fusion devices with the Monte Carlo code ERO [J].
Droste, S. ;
Borodin, D. ;
Virschner, A. ;
Kreter, A. ;
Philipps, V. ;
Samm, U. .
CONTRIBUTIONS TO PLASMA PHYSICS, 2006, 46 (7-9) :628-634
[10]   Modelling of 13CH4 injection experiments with graphite and tungsten test limiters in TEXTOR using the coupled code ERO-SDTrimSP [J].
Droste, S. ;
Kirschner, A. ;
Borodin, D. ;
Kreter, A. ;
Brezinsek, S. ;
Philipps, V. ;
Samm, U. ;
Schmitz, O. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2008, 50 (01)