Overview of coating and compatibility research for Fusion Energy in the US

被引：11
作者：
Pint, B. A. [1 ]
机构：
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
来源：
HIGH TEMPERATURE CORROSION AND PROTECTION OF MATERIALS 7, PTS 1 AND 2 | 2008年 / 595-598卷
关键词：
fusion energy; liquid metals; refractory metals; lithium; SiC composites;
D O I：
10.4028/www.scientific.net/MSF.595-598.549
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Planning for a U.S. test blanket module to operate in the internationally-sponsored ITER reactor has focused attention on the many coating and compatibility issues that will need to be solved before fusion energy moves from concept to commercial reality. Examples are given for (1) a dual-layer, electrically-resistant coating as a potential solution to reduce the magnetohydrodynamic pressure drop with liquid Li and (2) materials compatibility issues with eutectic Pb-Li for conventional alloys and SiC/SiC composites. Because of the reduced activity of Li in Pb-Li, a wider range of functional materials can be considered in this system. Nevertheless, an Al(2)O(3) scale on FeCrAl was transformed to LiAlO(2) after exposure to Pb-Li at 800 degrees C.
引用
收藏
页码：549 / 558
页数：10
相关论文
共 29 条
  • [1] US plans and strategy for ITER blanket testing
    Abdou, M
    Sze, D
    Wong, C
    Sawan, M
    Ying, A
    Morley, NB
    Malang, S
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2005, 47 (03) : 475 - 487
  • [2] Hydrogen permeation through tritium permeation barrier in Pb-17Li
    Aiello, A
    Benamati, G
    Chini, M
    Fazio, C
    Serra, E
    Yao, Z
    [J]. FUSION ENGINEERING AND DESIGN, 2001, 58-59 : 737 - 742
  • [3] Status of reduced activation ferritic/martensitic steel development
    Baluc, N.
    Gelles, D. S.
    Jitsukawa, S.
    Kimura, A.
    Klueh, R. L.
    Odette, G. R.
    van der Schaaf, B.
    Yu, Jinnan
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 33 - 41
  • [4] Materials challenges for ITER - Current status and future activities
    Barabash, V.
    Peacock, A.
    Fabritsiev, S.
    Kalinin, G.
    Zinkle, S.
    Rowcliffe, A.
    Rensman, J.-W.
    Tavassoli, A. A.
    Marmy, P.
    Karditsas, P. J.
    Gillemot, F.
    Akiba, M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 21 - 32
  • [5] MHD FLOW IN LIQUID-METAL-COOLED BLANKETS
    BARLEON, L
    CASAL, V
    LENHART, L
    [J]. FUSION ENGINEERING AND DESIGN, 1991, 14 (3-4) : 401 - 412
  • [6] BATTLES JE, 1989, INT MATER REV, V34, P1
  • [7] LIQUID-METAL CORROSION
    CHOPRA, OK
    SMITH, DL
    TORTORELLI, PF
    DEVAN, JH
    SZE, DK
    [J]. FUSION TECHNOLOGY, 1985, 8 (02): : 1956 - 1969
  • [8] Test blanket modules in ITER:: An overview on proposed designs and required DEMO-relevant materials
    Giancarli, L.
    Chuyanov, V.
    Abdou, M.
    Akiba, M.
    Hong, B. G.
    Laesser, R.
    Pan, C.
    Strebkov, Y.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 1271 - 1280
  • [9] Corrosion behaviour of Al based tritium permeation barriers in flowing Pb-17Li
    Glasbrenner, H
    Konys, J
    Voss, Z
    Wedemeyer, O
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 1360 - 1363
  • [10] Pb-17Li and lithium: A thermodynamic rationalisation of their radically different chemistry
    Hubberstey, P
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1997, 247 : 208 - 214
123