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LIBRIS Formathandbok  (Information om MARC21)
FältnamnIndikatorerMetadata
00006492naa a2200625 4500
001oai:DiVA.org:kth-340270
003SwePub
008231201s2023 | |||||||||||000 ||eng|
024a https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-3402702 URI
024a https://doi.org/10.1016/j.nme.2023.1015462 DOI
040 a (SwePub)kth
041 a engb eng
042 9 SwePub
072 7a ref2 swepub-contenttype
072 7a art2 swepub-publicationtype
100a Corre, Y.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
2451 0a Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms
264 1b Elsevier BV,c 2023
338 a print2 rdacarrier
500 a QC 20231201
520 a 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.
650 7a NATURVETENSKAPx Fysikx Fusion, plasma och rymdfysik0 (SwePub)103032 hsv//swe
650 7a NATURAL SCIENCESx Physical Sciencesx Fusion, Plasma and Space Physics0 (SwePub)103032 hsv//eng
653 a Heat flux calculation
653 a IR thermography
653 a Melting
653 a Plasma Facing Unit
653 a Tungsten cracking
700a Aumeunier, M. H.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Durif, A.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Gaspar, J.u Aix Marseille Univ, CNRS, IUSTI, Marseille, France4 aut
700a Krieger, K.u Max-Planck-Institut für Plasmaphysik, 85748 Garching b. München, Germany4 aut
700a Loewenhoff, T.u Forschungszentrum Jülich GmbH, Institut für Energie und Klimaforschung, 52425 Jülich, Germany4 aut
700a Richou, M.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Ratynskaia, Svetlana V.u KTH,Rymd- och plasmafysik4 aut0 (Swepub:kth)u1p4172h
700a Tichit, Q.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Anquetin, Y.u Aix Marseille Univ, CNRS, IUSTI, Marseille, France4 aut
700a Dejarnac, R.u Institute of Plasma Physics, Czech Academy of Sciences, 182 00 Prague, Czech Republic4 aut
700a Diez, M.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Dubus, L.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Firdaouss, M.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Gerardin, J.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Grosjean, A.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Gunn, J. P.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Loarer, T.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Maget, P.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Martin, C.u Aix Marseille Univ, PIIM UMR 7345, F-13397 Marseille, France4 aut
700a Paschalidis, Konstantinosu KTH,Rymd- och plasmafysik4 aut0 (Swepub:kth)u1052qm5
700a Tsitrone, E.u CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, France4 aut
700a Wirtz, M.u Forschungszentrum Jülich GmbH, Institut für Energie und Klimaforschung, 52425 Jülich, Germany4 aut
710a CEA, Institute for Research on Fusion by Magnetic confinement, 13108 St-Paul-Lez-Durance, Franceb Aix Marseille Univ, CNRS, IUSTI, Marseille, France4 org
773t Nuclear Materials and Energyd : Elsevier BVg 37q 37x 2352-1791
856u https://doi.org/10.1016/j.nme.2023.101546y Fulltext
8564 8u https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-340270
8564 8u https://doi.org/10.1016/j.nme.2023.101546

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