An empirical scaling for deuterium retention in co-deposited beryllium layers

被引:66
作者
De Temmerman, G. [1 ]
Baldwin, M. J. [1 ]
Doerner, R. P. [1 ]
Nishijima, D. [1 ]
Schmid, K. [2 ]
机构
[1] Univ Calif San Diego, Energy Res Ctr, La Jolla, CA 92093 USA
[2] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany
关键词
D O I
10.1088/0029-5515/48/7/075008
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Different mechanisms contribute to tritium retention in ITER, amongst which co-deposition with materials from the plasma-facing components is one of the main contributors. A systematic study of the influence of the deposition conditions (substrate temperature, deposition rate, energy of the incident particles) on the deuterium retention in co-deposited beryllium layers has been carried out in PISCES-B. The mechanism by which deuterium co-deposits with beryllium appears to be a combination of co-deposition and implantation, with a decreased retention for increased deposition rate and an increased retention for increased incident deuterium particle energy. A scaling equation is developed, providing a method to predict the retention in Be co-deposits formed in PISCES-B as a function of the layer formation conditions. Using this equation, previously published data on retention in Be co-deposits are re-examined and relatively good agreement is found with the prediction of the scaling equation.
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页数:7
相关论文
共 34 条
[1]   Differential cross-section of the D(3He, p)4He nuclear reaction and depth profiling of deuterium up to large depths [J].
Alimov, VK ;
Mayer, M ;
Roth, J .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2005, 234 (03) :169-175
[2]   Hydrogen isotope retention in beryllium for tokamak plasma-facing applications [J].
Anderl, RA ;
Causey, RA ;
Davis, JW ;
Doerner, RP ;
Federici, G ;
Haasz, AA ;
Longhurst, GR ;
Wampler, WR ;
Wilson, KL .
JOURNAL OF NUCLEAR MATERIALS, 1999, 273 (01) :1-26
[3]  
BAKER RW, 1978, J ORGANOMET CHEM, V159, P3589
[4]   A time resolved study of the mitigation of graphite chemical erosion in deuterium plasmas containing beryllium [J].
Baldwin, M. J. ;
Doerner, R. P. .
NUCLEAR FUSION, 2006, 46 (04) :444-450
[5]   Composition and hydrogen isotope retention analysis of co-deposited C/Be layers [J].
Baldwin, MJ ;
Schmid, K ;
Doerner, RP ;
Wiltner, A ;
Seraydarian, R ;
Linsmeier, C .
JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :590-594
[6]   Hydrogen isotope retention and recycling in fusion reactor plasma-facing components [J].
Causey, RA .
JOURNAL OF NUCLEAR MATERIALS, 2002, 300 (2-3) :91-117
[7]   Codeposition of deuterium with beryllium [J].
Causey, RA ;
Walsh, DS .
JOURNAL OF NUCLEAR MATERIALS, 1998, 254 (01) :84-86
[8]  
CAUSEY RA, 1996, P INT WORKSH PRES ST
[9]   Overview of material re-deposition and fuel retention studies at JET with the Gas Box divertor [J].
Coad, JP ;
Likonen, J ;
Rubel, M ;
Vainonen-Ahlgren, E ;
Hole, DE ;
Sajavaara, T ;
Renvall, T ;
Matthews, GF .
NUCLEAR FUSION, 2006, 46 (02) :350-366
[10]   Tritium retention in next step devices and the requirements for mitigation and removal techniques [J].
Counsell, G. ;
Coad, P. ;
Grisola, C. ;
Hopf, C. ;
Jacob, W. ;
Kirschner, A. ;
Kreter, A. ;
Krieger, K. ;
Likonen, J. ;
Philipps, V. ;
Roth, J. ;
Rubel, M. ;
Salancon, E. ;
Semerok, A. ;
Tabares, F. L. ;
Widdowson, A. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2006, 48 (12B) :B189-B199