Počet záznamů: 1
Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms
- 1.
SYSNO ASEP 0584102 Druh ASEP J - Článek v odborném periodiku Zařazení RIV J - Článek v odborném periodiku Poddruh J Článek ve WOS Název Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms Tvůrce(i) Corre, Y. (FR)
Aumeunier, M.-H. (FR)
Durif, A. (FR)
Gaspar, J. (FR)
Krieger, K. (DE)
Loewenhoff, Th. (DE)
Richou, M. (FR)
Ratynskaia, S. (SE)
Tichit, Q. (FR)
Anquetin, Y. (FR)
Dejarnac, Renaud (UFP-V) RID, ORCID
Diez, M. (FR)
Dubus, L. (FR)
Firdaouss, M. (FR)
Gerardin, J. (FR)
Grosjean, A. (FR)
Gunn, J. P. (FR)
Loarer, T. (FR)
Maget, P. (FR)
Martin, C. (FR)
Paschalidis, K. (SE)
Tsitrone, E. (FR)
Wirtz, M. (DE)Celkový počet autorů 23 Číslo článku 101546 Zdroj.dok. Nuclear Materials and Energy. - : Elsevier
Roč. 37, December (2023)Poč.str. 13 s. Jazyk dok. eng - angličtina Země vyd. NL - Nizozemsko Klíč. slova Heat flux calculation ; IR thermography ; Melting ; Plasma Facing Unit ; Tungsten cracking Vědní obor RIV BL - Fyzika plazmatu a výboje v plynech Obor OECD Fluids and plasma physics (including surface physics) Způsob publikování Open access Institucionální podpora UFP-V - RVO:61389021 UT WOS 001119119300001 EID SCOPUS 85177591538 DOI 10.1016/j.nme.2023.101546 Anotace 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. Pracoviště Ústav fyziky plazmatu Kontakt Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Rok sběru 2024 Elektronická adresa https://www.sciencedirect.com/science/article/pii/S2352179123001850?via%3Dihub
Počet záznamů: 1