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Testing of ITER-gra...
Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms
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- Corre, Y. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Aumeunier, M. H. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Durif, A. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Gaspar, J. (författare)
- Aix Marseille Univ, CNRS, IUSTI, Marseille, France
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- Krieger, K. (författare)
- Max-Planck-Institut für Plasmaphysik, 85748 Garching b. München, Germany
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- Loewenhoff, T. (författare)
- Forschungszentrum Jülich GmbH, Institut für Energie und Klimaforschung, 52425 Jülich, Germany
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- Richou, M. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Ratynskaia, Svetlana V. (författare)
- KTH,Rymd- och plasmafysik
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- Tichit, Q. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Anquetin, Y. (författare)
- Aix Marseille Univ, CNRS, IUSTI, Marseille, France
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- Dejarnac, R. (författare)
- Institute of Plasma Physics, Czech Academy of Sciences, 182 00 Prague, Czech Republic
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- Diez, M. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Dubus, L. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Firdaouss, M. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Gerardin, J. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Grosjean, A. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Gunn, J. P. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Loarer, T. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Maget, P. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Martin, C. (författare)
- Aix Marseille Univ, PIIM UMR 7345, F-13397 Marseille, France
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- Paschalidis, Konstantinos (författare)
- KTH,Rymd- och plasmafysik
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- Tsitrone, E. (författare)
- CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France
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- Wirtz, M. (författare)
- Forschungszentrum Jülich GmbH, Institut für Energie und Klimaforschung, 52425 Jülich, Germany
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(creator_code:org_t)
- Elsevier BV, 2023
- 2023
- Engelska.
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Ingår i: Nuclear Materials and Energy. - : Elsevier BV. - 2352-1791. ; 37
- Relaterad länk:
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https://doi.org/10.1...
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https://urn.kb.se/re...
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https://doi.org/10.1...
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Abstract
Ämnesord
Stäng
- Assessing the performance of the ITER design for the tungsten (W) divertor Plasma Facing Units (PFUs) in a tokamak environment is a high priority issue to ensure efficient plasma operation. This paper reviews the most recent results derived from experiments and post-mortem analysis of the ITER-grade PFUs exposed in the WEST tokamak and the associated modelling, with a focus on understanding heat loading and damage evolution. Several shaping options, sharp or chamfered leading edge (LE), unshaped or shaped blocks with a toroidal bevel as foreseen in ITER, were investigated, under steady state heat fluxes of up to 120 MW⋅m−2 and 6 MW⋅m−2 on the sharp LE and top surface of the block, respectively. A very high spatial resolution (VHR) infrared (IR) camera (0.1 mm/pixel) was used to derive the temporal and surface distribution of the temperature and heat load on the castellated tungsten blocks for different geometric alignment and plasma conditions. Photonic modelling was required to reproduce the IR measurements in particular in the toroidal and poloidal gaps of the mono-block (MB) stacks where high apparent temperatures are observed. Specular reflection is found to be the dominant emitter in these parts of the blocks. W-cracking was observed on the leading edge of the blocks already within the first phase of plasma operation, during which the divertor was equipped with unshaped PFUs, including some intentionally misaligned blocks. Numerical analysis taking into account softening processes and mechanical stresses, revealed brittle failure due to transients as the dominant failure mechanisms. Ductile failure was observed in one particular block used for the melting experiment, therefore under extremely high steady state heat load conditions. W-melting achieved on actively cooled PFU exhibits specific features: shallow melting and slow melt displacement. Plasma exposure of pre-damaged PFUs at various damage levels (crack network and melted droplets) was carried out under high heat load conditions with several hours of cumulated plasma duration. IR data and preliminary surface analyses show no evidence of significant degradation damage progression under these conditions.
Ämnesord
- NATURVETENSKAP -- Fysik -- Fusion, plasma och rymdfysik (hsv//swe)
- NATURAL SCIENCES -- Physical Sciences -- Fusion, Plasma and Space Physics (hsv//eng)
Nyckelord
- Heat flux calculation
- IR thermography
- Melting
- Plasma Facing Unit
- Tungsten cracking
Publikations- och innehållstyp
- ref (ämneskategori)
- art (ämneskategori)
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Till lärosätets databas
- Av författaren/redakt...
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Corre, Y.
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Aumeunier, M. H.
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Durif, A.
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Gaspar, J.
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Krieger, K.
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Loewenhoff, T.
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visa fler...
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Richou, M.
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Ratynskaia, Svet ...
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Tichit, Q.
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Anquetin, Y.
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Dejarnac, R.
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Diez, M.
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Dubus, L.
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Firdaouss, M.
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Gerardin, J.
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Grosjean, A.
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Gunn, J. P.
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Loarer, T.
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Maget, P.
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Martin, C.
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Paschalidis, Kon ...
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Tsitrone, E.
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Wirtz, M.
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