Modelling of tritium permeation through beryllium as plasma facing material

被引:0
|
作者
Berardinucci, L. [1 ]
机构
[1] Inst fuer Neutronenphysik und, Reaktortechnik, Karlsruhe, Germany
来源
Journal of Nuclear Materials | 1998年 / 258-263卷 / pt A期
关键词
D O I
暂无
中图分类号
学科分类号
摘要
引用
收藏
页码:777 / 781
相关论文
共 50 条
  • [21] Surface effects on plasma-driven tritium permeation through metals
    Ogorodnikova, OV
    JOURNAL OF NUCLEAR MATERIALS, 2001, 290 (290-293) : 459 - 463
  • [22] Magras - Facility for modelling of plasma facing beryllium sputtering and re-deposition
    Zimin, AM
    Elistratov, NG
    Kolbasov, BN
    Kozlov, OS
    Kurochkin, YY
    Milyukov, DA
    Vasiliev, NN
    PLASMA DEVICES AND OPERATIONS, 1999, 8 (01): : 15 - 38
  • [23] Investigation of plasma-facing component material effects on tritium reprocessing systems
    Kuan, William
    Abdou, Mohamed A.
    Fusion Technology, 1995, 28 (3 pt 1): : 658 - 663
  • [24] AN INVESTIGATION OF PLASMA-FACING COMPONENT MATERIAL EFFECTS ON TRITIUM REPROCESSING SYSTEMS
    KUAN, W
    ABDOU, MA
    FUSION TECHNOLOGY, 1995, 28 (03): : 658 - 663
  • [25] A simulation study of tritium removal from molten salt at high temperature with tritium permeation through metallic material
    Zeng, You-shi
    Zhang, Qin
    Deng, Ke
    Chu, Xin-xin
    ANNALS OF NUCLEAR ENERGY, 2022, 170
  • [26] Plasma-driven accumulation of tritium in beryllium
    Pisarev, AA
    Grachova, ML
    JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 1137 - 1141
  • [27] Beryllium and liquid metals as plasma facing materials
    Doerner, RP
    NUCLEAR FUSION RESEARCH: UNDERSTANDING PLASMA-SURFACE INTERACTIONS, 2005, 78 : 335 - 357
  • [28] Tritium permeation modelling in DEMO WCLL cooling system
    Noschese, Leonardo
    Santucci, Alessia
    Tosti, Silvano
    Romanelli, Francesco
    FUSION ENGINEERING AND DESIGN, 2020, 161 (161)
  • [29] Beryllium application in ITER plasma facing components
    Raffray, AR
    Federici, G
    Barabash, V
    Pacher, HD
    Bartels, HW
    Cardella, A
    Jakeman, R
    Ioki, K
    Janeschitz, G
    Parker, R
    Tivey, R
    Wu, CH
    FUSION ENGINEERING AND DESIGN, 1997, 37 (02) : 261 - 286
  • [30] Tritium retention of plasma facing components in tokamaks
    Tanabe, T
    Bekris, N
    Coad, P
    Skinner, CH
    Glugla, M
    Miya, N
    JOURNAL OF NUCLEAR MATERIALS, 2003, 313 : 478 - 490