Influence of the base temperature on the performance of tungsten under thermal and particle exposure

被引:5
作者
Steudel, I. [1 ]
Huber, A. [1 ]
Kreter, A. [1 ]
Linke, J. [1 ]
Sergienko, G. [1 ]
Unterberg, B. [1 ]
Wirtz, M. [1 ]
机构
[1] Forschungszentrum Julich, Inst Energie & Klimaforsch, D-52425 Julich, Germany
关键词
DEUTERIUM RETENTION; PLASMA; DESORPTION; ITER;
D O I
10.1016/j.nme.2017.03.016
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
Tungsten, the plasma facing material (PFM) for the divertor in ITER, must sustain severe, distinct loading conditions. This broad array of exposure conditions necessitates comprehensive experiments that cover most of the expected loading parameters to predict qualitative statements about the performance and as a consequence thereof the intended operation time. However, comprehensive experiments are inherently difficult to realize due to the fact that there is no device that is capable of simulating all loading conditions simultaneously. Nevertheless, the linear plasma device PSI-2 enables experiments combining thermal and particle exposure at the same time. In this work, sequential and simultaneous loads on pure tungsten at different base temperatures were investigated to study not only the performance of the material, but also the influence of the experimental parameters. The detailed analysis and comparison of the obtained results showed different kinds of damage depending on the loading sequence, power density, microstructure of the samples, and base temperature. Finally, samples with transversal grain orientation (T) showed the weakest damage resistance and the increase of the base temperature could not compensate the detrimental impact of deuterium. (C) 2017 The Authors. Published by Elsevier Ltd.
引用
收藏
页码:1348 / 1351
页数:4
相关论文
共 17 条
  • [1] Plasma facing and high heat flux materials - needs for ITER and beyond
    Bolt, H
    Barabash, V
    Federici, G
    Linke, J
    Loarte, A
    Roth, J
    Sato, K
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 43 - 52
  • [2] VOID GROWTH AND THERMAL-DESORPTION OF DEUTERIUM FROM VOIDS IN TUNGSTEN
    ELEVELD, H
    VANVEEN, A
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 212 : 1421 - 1425
  • [3] Effects of ELMS and disruptions on ITER divertor armour materials
    Federici, G
    Zhitlukhin, A
    Arkhipov, N
    Giniyatulin, R
    Klimov, N
    Landman, I
    Podkovyrov, V
    Safronov, V
    Loarte, A
    Merola, M
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) : 684 - 690
  • [4] Re-emission and thermal desorption of deuterium from plasma sprayed tungsten coatings for application in ASDEX-upgrade
    GarciaRosales, C
    Franzen, P
    Plank, H
    Roth, J
    Gauthier, E
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 803 - 808
  • [5] Impact on the deuterium retention of simultaneous exposure of tungsten to a steady state plasma and transient heat cycling loads
    Huber, A.
    Sergienko, G.
    Wirtz, M.
    Steudel, I.
    Arakcheev, A.
    Brezinsek, S.
    Burdakov, A.
    Dittmar, T.
    Esser, H. G.
    Kreter, A.
    Linke, J.
    Linsmeier, Ch
    Mertens, Ph
    Moeller, S.
    Philipps, V.
    Pintsuk, G.
    Reinhart, M.
    Schweer, B.
    Shoshin, A.
    Terra, A.
    Unterberg, B.
    [J]. PHYSICA SCRIPTA, 2016, T167
  • [6] LINEAR PLASMA DEVICE PSI-2 FOR PLASMA-MATERIAL INTERACTION STUDIES
    Kreter, A.
    Brandt, C.
    Huber, A.
    Kraus, S.
    Moeller, S.
    Reinhart, M.
    Schweer, B.
    Sergienko, G.
    Unterberg, B.
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2015, 68 (01) : 8 - 14
  • [7] Influence of blistering on deuterium retention in tungsten irradiated by high flux deuterium 10-100 eV plasmas
    Luo, GN
    Shu, WM
    Nishi, M
    [J]. FUSION ENGINEERING AND DESIGN, 2006, 81 (8-14) : 957 - 962
  • [8] Ion-driven deuterium retention in tungsten
    Ogorodnikova, O. V.
    Roth, J.
    Mayer, M.
    [J]. JOURNAL OF APPLIED PHYSICS, 2008, 103 (03)
  • [9] Deuterium retention in tungsten in dependence of the surface conditions
    Ogorodnikova, OV
    Roth, J
    Mayer, M
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2003, 313 : 469 - 477
  • [10] Perkins FW, 1999, NUCL FUSION, V39, P2137, DOI 10.1088/0029-5515/39/12/301