Analysis of structural changes and high-heat-flux tests on pre-damaged tungsten from tokamak melt experiments

被引:17
作者
Coenen, J. W. [1 ]
Philipps, V. [1 ]
Brezinsek, S. [1 ]
Pintsuk, G. [2 ]
Tanabe, T. [3 ]
Ueda, Y. [4 ]
Samm, U. [1 ]
机构
[1] Assoc EURATOM FZJ, Partner Trilateral Euregio Cluster, Forschungszentrum Julich GmbH, Inst Energy & Climate Res Plasma Phys, Julich, Germany
[2] Assoc EURATOM FZJ, Partner Trilateral Euregio Cluster, Forschungszentrum Julich GmbH, Inst Energy & Climate Res Microstruct & Propertie, Julich, Germany
[3] Kyushu Univ, Interdisciplinary Grad Sch Engn Sci, Higashiku, Fukuoka 8128581, Japan
[4] Osaka Univ, Grad Sch Engn, Suita, Osaka 5650871, Japan
关键词
D O I
10.1088/0031-8949/2011/T145/014066
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
The characteristics of W plasma-facing components under high heat fluxes were investigated in view of the material choice for the divertor in future fusion devices. Thin W sheets were exposed in the TEXTOR tokamak to multiple steady-state loads (20 MW at 36 degrees), resulting in substantial W melting. One sample was subjected to post-exposure edge localized mode (ELM) simulation in the electron beam facility JUDITH 1 to determine the modified behavior of the pre-damaged components. The material structure after exposure and the cracking thresholds and patterns under repetitive transient thermal loads were investigated. Grain sizes from the original mu m up to the mm range were observed. Void-like structures from the low mu m up to the mm range were found at different regions of the resolidified sample. Exposure of the molten and recrystallized specimens to ELM-like thermal loads revealed a shift of the cracking threshold towards 300 degrees C, indicating an unfavorable increase in the ductile-to-brittle transition temperature.
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页数:6
相关论文
共 15 条
[1]   Analysis of tungsten melt-layer motion and splashing under tokamak conditions at TEXTOR [J].
Coenen, J. W. ;
Philipps, V. ;
Brezinsek, S. ;
Bazylev, B. ;
Kreter, A. ;
Hirai, T. ;
Laengner, M. ;
Tanabe, T. ;
Ueda, Y. ;
Samm, U. .
NUCLEAR FUSION, 2011, 51 (08)
[2]   Tungsten melt layer motion and splashing on castellated tungsten surfaces at the tokamak TEXTOR [J].
Coenen, J. W. ;
Bazylev, B. ;
Brezinsek, S. ;
Philipps, V. ;
Hirai, T. ;
Kreter, A. ;
Linke, J. ;
Sergienko, G. ;
Pospieszczyk, A. ;
Tanabe, T. ;
Ueda, Y. ;
Samm, U. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) :S78-S82
[3]  
COENEN JW, 2010, P 23 INT C FUS EN 20, P10
[4]  
ESPE W, 1959, WERKSTOFFKUNDE HOCHV
[5]   Overview on stationary and transient divertor heat loads [J].
Herrmann, A .
PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 (06) :883-903
[6]   Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures [J].
Hirai, T. ;
Pintsuk, G. ;
Linke, J. ;
Batilliot, M. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 390-91 :751-754
[7]   Performance of different tungsten grades under transient thermal loads [J].
Linke, J. ;
Loewenhoff, T. ;
Massaut, V. ;
Pintsuk, G. ;
Ritz, G. ;
Roedig, M. ;
Schmidt, A. ;
Thomser, C. ;
Uytdenhouwen, I. ;
Vasechko, V. ;
Wirtz, M. .
NUCLEAR FUSION, 2011, 51 (07)
[8]  
LINKE J, 2010, P 23 INT C FUS EN DA, P10
[9]   Power handling of a segmented bulk W tile for JET under realistic plasma scenarios [J].
Mertens, Ph. ;
Coenen, J. W. ;
Eich, T. ;
Huber, A. ;
Jachmich, S. ;
Nicolai, D. ;
Riccardo, V. ;
Senik, K. ;
Samm, U. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) :S943-S947
[10]  
NACHTIGALL E., 2004, CHEM-ING-TECH, V27, P794