Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms

0584102 - ÚFP 2024 RIV NL eng J - Článek v odborném periodiku
Corre, Y. - Aumeunier, M.-H. - Durif, A. - Gaspar, J. - Krieger, K. - Loewenhoff, Th. - Richou, M. - Ratynskaia, S. - Tichit, Q. - Anquetin, Y. - Dejarnac, Renaud - Diez, M. - Dubus, L. - Firdaouss, M. - Gerardin, J. - Grosjean, A. - Gunn, J. P. - Loarer, T. - Maget, P. - Martin, C. - Paschalidis, K. - Tsitrone, E. - Wirtz, M.
Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms.
Nuclear Materials and Energy. Roč. 37, December (2023), č. článku 101546. E-ISSN 2352-1791
GRANT EU: European Commission(BE) 101052200
Institucionální podpora: RVO:61389021
Klíčová slova: Heat flux calculation * IR thermography * Melting * Plasma Facing Unit * Tungsten cracking
Obor OECD: Fluids and plasma physics (including surface physics)
Impakt faktor: 2.6, rok: 2022
Způsob publikování: Open access
https://www.sciencedirect.com/science/article/pii/S2352179123001850?via%3Dihub

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.
Trvalý link: https://hdl.handle.net/11104/0352087