Published August 2017 | Version v1
Journal article

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

  • 1. Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, 52425 Jülich (Germany)
  • 2. Aalto University, Espoo (Finland)
  • 3. Max-Planck-Institut für Plasmaphysik, 85748 Garching bei München (Germany)
  • 4. Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States)
  • 5. VTT Technical Research Centre of Finland Ltd, P.O. Box 1000, FI-02044 VTT (Finland)

Description

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 Psep/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. 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 Psep.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nme.2017.03.033

Additional details

Identifiers

DOI
10.1016/j.nme.2017.03.033;
PII
S2352179116300370;

Publishing Information

Journal Title
Nuclear Materials and Energy
Journal Volume
12
Journal Page Range
p. 3-17
ISSN
2352-1791

Conference

Title
22. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices
Acronym
PSI-22
Dates
30 May - 3 Jun 2016
Place
Rome (Italy)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50079837
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALCATOR DEVICE; ASDEX TOKAMAK; CARBON; DIVERTORS; EQUIPMENT; FIRST WALL; HEATING LOAD; ITER TOKAMAK; PLASMA IMPURITIES; POWER DENSITY; SIMULATION; THERMONUCLEAR POWER PLANTS; WALL EFFECTS
Descriptors DEC
CLOSED PLASMA DEVICES; ELEMENTS; IMPURITIES; NONMETALS; POWER PLANTS; THERMAL POWER PLANTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
© 2017 The Authors. Published by Elsevier Ltd.
Collaborations
JET contributors