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

被引：14

作者：

Corre, Y. ^{[1
,8
]}

Aumeunier, M-h. ^{[1
]}

Durif, A. ^{[1
]}

Gaspar, J. ^{[2
]}

Krieger, K. ^{[3
]}

Loewenhoff, T. ^{[4
]}

Richou, M. ^{[1
]}

Ratynskaia, S. ^{[5
]}

Tichit, Q. ^{[1
]}

Anquetin, Y. ^{[2
]}

Dejarnac, R. ^{[6
]}

Diez, M. ^{[1
]}

Dubus, L. ^{[1
]}

Firdaouss, M. ^{[1
]}

Gerardin, J. ^{[1
]}

Grosjean, A. . ^{[1
]}

Gunn, J. P. ^{[1
]}

Loarer, T. ^{[1
]}

Maget, P. ^{[1
]}

Martin, C. ^{[7
]}

Paschalidis, K. ^{[5
]}

Tsitrone, E. ^{[1
]}

Wirtz, M. ^{[4
]}

机构：

[1] Inst Res Fus Magnet Confinement, CEA, F-13108 St Paul Les Durance, France

[2] Aix Marseille Univ, CNRS, IUSTI, Marseille, France

[3] Max Planck Inst Plasma Phys, D-85748 Garching, Germany

[4] Forschungszentrum Julich, Inst Energie & Klimaforsch, D-52425 Julich, Germany

[5] KTH Royal Inst Technol, Space & Plasma Phys, SE-10044 Stockholm, Sweden

[6] Czech Acad Sci, Inst Plasma Phys, Prague 18200, Czech Republic

[7] Aix Marseille Univ, PIIM UMR 7345, F-13397 Marseille, France

[8] CEA, IRFM, F-13108 St Paul Les Durance, France

来源：

NUCLEAR MATERIALS AND ENERGY | 2023年 / 37卷

关键词：

Tungsten cracking; Melting; Plasma Facing Unit; Heat flux calculation; IR thermography; INFRARED THERMOGRAPHY; TUNGSTEN DIVERTOR;

D O I：

10.1016/j.nme.2023.101546

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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.

引用

页数：13

共 4 条

[1] Plasma heat load in the toroidal gaps of the ITER-like plasma facing units in WEST tokamak
Tichit, Q.
Aumeunier, M. H.
Corre, Y.
Dejarnac, R.
Dubus, L.
Gaspar, J.
Gerardin, J.
Grosjean, A.
Gunn, J. P.
Juven, A.
Krieger, K.
Tsitrone, E.
NUCLEAR MATERIALS AND ENERGY, 2025, 42
[2] Protection of the plasma facing components in the WEST tokamak, progress and development in view of ITER
Houry, M.
Aumeunier, M-h.
Corre, Y.
Courtois, X.
Mitteau, R.
Loarer, TH.
Dubus, L.
Gauthier, E.
Gerardin, J.
Gorse, V.
Grelier, E.
Juven, A.
Malard, PH.
Moncada, V.
Tichit, Q.
Vives, S.
Gaspar, J.
WEST Team
NUCLEAR FUSION, 2025, 65 (01)
[3] ITER-grade tungsten limiters damage under high turbulent heat flux in the T-10 tokamak
Grashin, S. A.
Arkhipov, I. I.
Budaev, V. P.
Karpov, A., V
Klyuchnikov, L. A.
Khimchenko, L. N.
Melnikov, A., V
Sarychev, D., V
Sergeev, N. S.
Zemtsov, I. A.
FUSION ENGINEERING AND DESIGN, 2019, 146 : 2100 - 2104
[4] First evidence of optical hot spots on ITER-like plasma facing units in the WEST tokamak
Diez, M.
Gunn, J. P.
Firdaouss, M.
Grosjean, A.
Corre, Y.
Delmas, E.
Gargiulo, L.
Tsitrone, E.
NUCLEAR FUSION, 2020, 60 (05)

← 1 →