Erosion of a tungsten limiter under high heat flux in TEXTOR

被引:36
|
作者
Sergienko, G. [1 ]
Bazylev, B.
Huber, A.
Kreter, A.
Litnovsky, A.
Rubel, M.
Philipps, V.
Pospieswzyk, A.
Mertens, Ph.
Samm, U.
Schweer, B.
Schmitz, O.
Tokar, M.
机构
[1] EURATOM, Forschungszentrum Julich GmbH, Inst Plasmaphys, D-52425 Julich, Germany
[2] Forschungszentrum Karlsruhe GmbH, Inst Hochleistungsimpuls & Mikrowellentech, D-76021 Karlsruhe, Germany
[3] Assoc EURATOM VR, Royal Inst Technol, Alfven Lab, S-10044 Stockholm, Sweden
关键词
tungsten; limiter; spectroscopy; liquid metal; TEXTOR;
D O I
10.1016/j.jnucmat.2007.01.050
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Erosion characteristics of a tungsten plate heated up in TEXTOR by the plasma load have been investigated at temperatures extending to the melting point. No enhancement of atomic release exceeding physical sputtering and normal thermal sublimation for temperatures below 3700 K was observed. The liquid tungsten moved fast along the plate in the direction perpendicular to the magnetic field lines. The motion is caused by the Lorentz force due to the thermoelectron current emitted from the hot tungsten surface. The motion of liquid tungsten caused a material loss of 2.85 g during two discharges. The material redistribution due to the melt layer motion is compared with a MEMOS-1.5D simulation. (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:96 / 100
页数:5
相关论文
共 50 条
  • [1] Performance and erosion of a tungsten brush limiter exposed at the TEXTOR tokamak
    Hirai, T
    Philipps, V
    Huber, A
    Sergienko, G
    Linke, J
    Wakui, T
    Tanabe, T
    Rubel, M
    Wada, M
    Ohgo, T
    Pospieszczyk, A
    Ohya, K
    Barabash, V
    JOURNAL OF NUCLEAR MATERIALS, 2003, 313 : 67 - 71
  • [2] Tungsten erosion under combined hydrogen/helium high heat flux loading
    Maier, H.
    Greuner, H.
    Balden, M.
    Boeswirth, B.
    Elgeti , S.
    Toussaint, U. V.
    Linsmeier, Ch
    PHYSICA SCRIPTA, 2014, T159
  • [3] Erosion and deposition at the ALT-II limiter of TEXTOR
    Mayer, M
    Wienhold, P
    Hildebrandt, D
    Schneider, W
    JOURNAL OF NUCLEAR MATERIALS, 2003, 313 : 377 - 382
  • [4] Evaluation of tungsten coatings on CuCrZr and W/Cu FGM under high heat flux and HT-7 limiter plasma irradiation
    Chong, F. L.
    Chen, J. L.
    Li, J. G.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 363 (1-3) : 1201 - 1205
  • [5] Influence of recrystallization on tungsten divertor monoblock under high heat flux
    Yu-Zhong Jin
    Xiang Liu
    You-Yun Lian
    Jiu-Peng Song
    Tungsten, 2022, 4 : 194 - 202
  • [6] Influence of recrystallization on tungsten divertor monoblock under high heat flux
    Jin, Yu-Zhong
    Liu, Xiang
    Lian, You-Yun
    Song, Jiu-Peng
    TUNGSTEN, 2022, 4 (03) : 194 - 202
  • [7] Degradation of tungsten monoblock divertor under cyclic high heat flux loading
    Nogami, Shuhei
    Toyota, Michitoshi
    Guan, Wenhai
    Hasegawa, Akira
    Ueda, Yoshio
    FUSION ENGINEERING AND DESIGN, 2017, 120 : 49 - 60
  • [8] Thermal shock resistance of tungsten with various deformation degrees under transient high heat flux
    Zhang, Xiaoxin
    Gong, Zheng
    Huang, Jianjun
    Yu, Bin
    MATERIALS RESEARCH EXPRESS, 2020, 7 (06)
  • [9] Tungsten behavior under proton flux and high temperature
    Raunier, Sebastien
    Balat-Pichelin, Marianne
    Sans, Jean-Louis
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2009, 267 (10) : 1841 - 1848
  • [10] A route to standardised high heat flux testing: An example for tungsten
    Schoofs, Frank
    Gorley, Mike
    FUSION ENGINEERING AND DESIGN, 2019, 139 : 132 - 136