Plasma edge and plasma-wall interaction modelling: Lessons learned from metallic devices

Wiesen, S.; Groth, M.; Wischmeier, M.; Brezinsek, S.; Jarvinen, A.; Reimold, F.; Aho-Mantila, L.

doi:10.1016/j.nme.2017.03.033

Title: Plasma edge and plasma-wall interaction modelling: Lessons learned from metallic devices

Journal Article · Tue Aug 01 00:00:00 EDT 2017 · Nuclear Materials and Energy

DOI:https://doi.org/10.1016/j.nme.2017.03.033· OSTI ID:1497271

Wiesen, S. ^[1]; Groth, M. ^[2]; Wischmeier, M. ^[3]; Brezinsek, S. ^[1]; Jarvinen, A. ^[4]; Reimold, F. ^[1]; Aho-Mantila, L. ^[5]

Forschungszentrum Julich (Germany). Inst. für Energie- und Klimaforschung
Aalto Univ., Espoo (Finland)
Max-Planck-Inst. für Plasmaphysik, Garching (Germany)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
VTT Technical Research Centre of Finland Ltd, Espoo (Finland)

Robust power exhaust schemes employing impurity seeding are needed for target operational scenarios in present day tokamak devices with metallic plasma-facing components (PFCs). For an electricity-producing fusion power plant at power density P_sep/R > 15 MW/m divertor detachment is a requirement for heat load mitigation. 2D plasma edge transport codes like the SOLPS code as well as plasma-wall interaction (PWI) codes are key to disentangle relevant physical processes in power and particle exhaust. With increased quantitative credibility in such codes more realistic and physically sound estimates of the life-time expectations and performance of metallic PFCs can be accomplished for divertor conditions relevant for ITER and DEMO. An overview is given on the recent progress of plasma edge and PWI modelling activities for (carbon-free) metallic devices, that include results from JET with the ITER-like wall, ASDEX Upgrade and Alcator C-mod. It is observed that metallic devices offer an opportunity to progress the understanding of underlying plasma physics processes in the edge. The validation of models can be substantially improved by eliminating carbon from the experiment as well as from the numerical system with reduced degrees of freedom as no chemical sputtering from amorphous carbon layers and no carbon or hydro-carbon transport are present. With the absence of carbon as the primary plasma impurity and given the fact that the physics of the PWI at metallic walls is less complex it is possible to isolate the crucial plasma physics processes relevant for particle and power exhaust. Finally, for a reliable 2D dissipative plasma exhaust model these are: cross-field drifts, complete kinetic neutral physics, geometry effects (including main-chamber, divertor and sub-divertor structures), SOL transport reflecting also the non-diffusive nature of anomalous transport, as well as transport within the pedestal region in case of significant edge impurity radiation affecting pedestal pressure and hence P_sep.

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Research Organization:: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA); European Commission (EC)

Grant/Contract Number:: AC52-07NA27344

OSTI ID:: 1497271

Report Number(s):: LLNL-JRNL-752164; 930345

Journal Information:: Nuclear Materials and Energy, Vol. 12, Issue C; ISSN 2352-1791

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 16 works

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