Deuterium retention and release in tungsten co-deposited layers

被引:60
作者
De Temmerman, G. [1 ]
Doerner, R. P. [2 ]
机构
[1] EURATOM, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Univ Calif San Diego, Energy Res Ctr, La Jolla, CA 92093 USA
基金
英国工程与自然科学研究理事会;
关键词
HYDROGEN ISOTOPE RETENTION; BLISTER FORMATION; FUEL RETENTION; RE-DEPOSITION; PLASMA; BERYLLIUM; DIVERTOR; ITER;
D O I
10.1016/j.jnucmat.2009.03.028
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
A systematic study of the influence of the deposition conditions on the deuterium retention in co-deposited tungsten layers formed both by magnetron sputtering and in the PISCES-B linear device has been carried out. Experimental parameters such as the tungsten deposition rate, the incident particle energy and the substrate temperature are shown to affect the level of deuterium retention in the layers. A decreased retention for increased substrate temperature and deposition rates, and an increased retention for increasing incident deuterium particle energy are observed. A scaling equation is proposed to describe the influence of the conditions during the co-deposition process (surface temperature, incident particle energy and deposition flux) on the deuterium retention. In addition, the desorption kinetics of deuterium has been studied by TDS. Two desorption stages at 473-573 K and at 1073 K have been observed. (C) 2009 Elsevier B.V. All rights reserved
引用
收藏
页码:479 / 483
页数:5
相关论文
共 21 条
  • [1] Composition and hydrogen isotope retention analysis of co-deposited C/Be layers
    Baldwin, MJ
    Schmid, K
    Doerner, RP
    Wiltner, A
    Seraydarian, R
    Linsmeier, C
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) : 590 - 594
  • [2] Tritium retention in tungsten exposed to intense fluxes of 100 eV tritons
    Causey, R
    Wilson, K
    Venhaus, T
    Wampler, WR
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1999, 266 : 467 - 471
  • [3] Hydrogen isotope retention and recycling in fusion reactor plasma-facing components
    Causey, RA
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 300 (2-3) : 91 - 117
  • [4] The use of tungsten in fusion reactors: A review of the hydrogen retention and migration properties
    Causey, RA
    Venhaus, TJ
    [J]. PHYSICA SCRIPTA, 2001, T94 : 9 - 15
  • [5] Overview of material re-deposition and fuel retention studies at JET with the Gas Box divertor
    Coad, JP
    Likonen, J
    Rubel, M
    Vainonen-Ahlgren, E
    Hole, DE
    Sajavaara, T
    Renvall, T
    Matthews, GF
    [J]. NUCLEAR FUSION, 2006, 46 (02) : 350 - 366
  • [6] An empirical scaling for deuterium retention in co-deposited beryllium layers
    De Temmerman, G.
    Baldwin, M. J.
    Doerner, R. P.
    Nishijima, D.
    Schmid, K.
    [J]. NUCLEAR FUSION, 2008, 48 (07)
  • [7] The implications of mixed-material plasma-facing surfaces in ITER
    Doerner, R. P.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 363 (1-3) : 32 - 40
  • [8] Eckstein Wolfgang., 2002, Calculated sputtering, reflection and range values
  • [9] Haasz AA, 1997, J NUCL MATER, V241, P1076, DOI 10.1016/S0022-3115(97)80197-3
  • [10] Helium and hydrogen trapping in tungsten deposition layers formed by helium plasma sputtering
    Katayama, K.
    Imaoka, K.
    Okamura, T.
    Nishikawa, M.
    [J]. FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 1645 - 1650