ELM-induced transient tungsten melting in the JET divertor

被引:92
作者
Coenen, J. W. [2 ]
Arnoux, G. [1 ]
Bazylev, B. [4 ]
Matthews, G. F. [1 ]
Autricque, A. [12 ]
Balboa, I. [1 ]
Clever, M. [2 ]
Dejarnac, R. [5 ]
Coffey, I. [6 ]
Corre, Y. [7 ]
Devaux, S. [8 ]
Frassinetti, L. [9 ]
Gauthier, E. [7 ]
Horacek, J. [5 ]
Jachmich, S. [3 ]
Komm, M. [5 ]
Knaup, M. [2 ]
Krieger, K. [8 ]
Marsen, S. [10 ]
Meigs, A. [1 ]
Mertens, Ph. [2 ]
Pitts, R. A. [11 ]
Puetterich, T. [8 ]
Rack, M. [2 ]
Stamp, M.
Sergienko, G. [2 ]
Tamain, P. [7 ]
Thompson, V. [1 ]
机构
[1] CCFE, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Forschungszentrum Julich, Partner Trilateral Euregio Cluster, IEK 4, D-52425 Julich, Germany
[3] Ecole Royale Mil, Plasma Phys Lab, B-1000 Brussels, Belgium
[4] Karlsruhe Inst Technol, D-76021 Karlsruhe, Germany
[5] Inst Plasma Phys AS CR, Prague 18221 8, Czech Republic
[6] Queens Univ Belfast, Sch Math & Phys, Astrophys Res Ctr, Belfast BT7 1NN, Antrim, North Ireland
[7] CEA, IRFM, F-13108 St Paul Les Durance, France
[8] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[9] KTH, Div Fus Plasma Phys, SE-10044 Stockholm, Sweden
[10] Max Planck Inst Plasma Phys, Teilinst Greifswald, D-17491 Greifswald, Germany
[11] ITER Org, F-613067 St Paul Les Durance, France
[12] Ecole Cent Lyon, Lyon, France
基金
英国工程与自然科学研究理事会;
关键词
fusion; melting; plasma wall interaction; power exhaust; RUNAWAY ELECTRONS; HEAT LOADS; EROSION; WALL; MACROBRUSH; SIMULATION; EVENTS; DAMAGE; ARMOR;
D O I
10.1088/0029-5515/55/2/023010
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The original goals of the JET ITER-like wall included the study of the impact of an all W divertor on plasma operation (Coenen et al 2013 Nucl. Fusion 53 073043) and fuel retention (Brezinsek et al 2013 Nucl. Fusion 53 083023). ITER has recently decided to install a full-tungsten (W) divertor from the start of operations. One of the key inputs required in support of this decision was the study of the possibility of W melting and melt splashing during transients. Damage of this type can lead to modifications of surface topology which could lead to higher disruption frequency or compromise subsequent plasma operation. Although every effort will be made to avoid leading edges, ITER plasma stored energies are sufficient that transients can drive shallow melting on the top surfaces of components. JET is able to produce ELMs large enough to allow access to transient melting in a regime of relevance to ITER. Transient W melt experiments were performed in JET using a dedicated divertor module and a sequence of I-P = 3.0 MA/B-T = 2.9 T H-mode pulses with an input power of P-IN = 23 MW, a stored energy of similar to 6 MJ and regular type I ELMs at Delta W-ELM = 0.3 MJ and f(ELM) similar to 30 Hz. By moving the outer strike point onto a dedicated leading edge in the W divertor the base temperature was raised within similar to 1 s to a level allowing transient, ELM-driven melting during the subsequent 0.5 s. Such ELMs (delta W similar to 300 kJ per ELM) are comparable to mitigated ELMs expected in ITER (Pitts et al 2011 J. Nucl. Mater. 415 (Suppl.) S957-64). Although significant material losses in terms of ejections into the plasma were not observed, there is indirect evidence that some small droplets (similar to 80 mu m) were released. Almost 1 mm (similar to 6 mm(3)) of W was moved by similar to 150 ELMs within 7 subsequent discharges. The impact on the main plasma parameters was minor and no disruptions occurred. The W-melt gradually moved along the leading edge towards the high-field side, driven by j x B forces. The evaporation rate determined from spectroscopy is 100 times less than expected from steady state melting and is thus consistent only with transient melting during the individual ELMs. Analysis of IR data and spectroscopy together with modelling using the MEMOS code Bazylev et al 2009 J. Nucl. Mater. 390-391 810-13 point to transient melting as the main process. 3D MEMOS simulations on the consequences of multiple ELMs on damage of tungsten castellated armour have been performed. These experiments provide the first experimental evidence for the absence of significant melt splashing at transient events resembling mitigated ELMs on ITER and establish a key experimental benchmark for the MEMOS code.
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