Critical plasma-wall interaction issues for plasma-facing materials and components in near-term fusion devices

被引:28
作者
Federici, G
Coad, JP
Haasz, AA
Janeschitz, G
Noda, N
Philipps, V
Roth, J
Skinner, CH
Tivey, R
Wu, CH
机构
[1] JWS Garching Coctr, ITER, D-85748 Garching, Germany
[2] Jet Joint Undertaking, Abingdon OX14 3EA, Oxon, England
[3] Univ Toronto, Inst Aerosp Studies, Toronto, ON M3H 5T6, Canada
[4] Natl Inst Fus Sci, Toki 5095292, Japan
[5] Forschungszentrum Julich, Inst Plasma Phys, D-52425 Julich, Germany
[6] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[7] Princeton Univ, Plasma Phys Lab, Princeton, NJ 08543 USA
[8] EFDA, D-85748 Garching, Germany
关键词
D O I
10.1016/S0022-3115(00)00158-6
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The increase in pulse duration and cumulative run-time, together with the increase of the plasma energy content, will represent the largest changes in operation conditions in future fusion devices such as the International Thermonuclear Experimental Reactor (ITER) compared to today's experimental facilities. These will give rise to important plasma-physics effects and plasma-material interactions (PMIs) which are only partially observed and accessible in present-day experiments and will open new design, operation and safety issues. For the first time in fusion research, erosion and its consequences over many pulses (e.g., co-deposition and dust) may determine the operational schedule of a fusion device, This paper identifies the most critical issues arising from PMIs which represent key elements in the selection of materials, the design, and the optimisation of plasma-facing components (PFCs) for the first-wall and divertor. Significant advances in the knowledge base have been made recently, as part of the R&D supporting the engineering design activities (EDA) of ITER, and some of the most relevant data are reviewed here together with areas where further R&D work is urgently needed. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:110 / 119
页数:10
相关论文
共 31 条
[1]   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
[2]   Tritium recycling and retention in JET [J].
Andrew, P ;
Brennan, D ;
Coad, JP ;
Ehrenberg, J ;
Gadeberg, M ;
Gibson, A ;
Groth, M ;
How, J ;
Jarvis, ON ;
Jensen, H ;
Lässer, R ;
Marcus, F ;
Monk, R ;
Morgan, P ;
Orchard, J ;
Peacock, A ;
Pearce, R ;
Pick, M ;
Rossi, A ;
Schunke, B ;
Stamp, M ;
von Hellermann, M ;
Hillis, DL ;
Hogan, J .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 (266) :153-159
[3]   Erosion/redeposition analysis: status of modeling and code validation for semi-detached tokamak edge plasmas [J].
Brooks, JN ;
Alman, D ;
Federici, G ;
Ruzic, DN ;
Whyte, DG .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :58-66
[4]   The amount and distribution of deuterium retained in the jet divertor after the C and Be phases in 1994-1995 [J].
Coad, JP ;
Rubel, M ;
Wu, CH .
JOURNAL OF NUCLEAR MATERIALS, 1997, 241 :408-413
[5]  
COAD JP, 1999, IN PRESS P 26 EPS C
[6]   Impurity release from low-Z materials under light particle bombardment [J].
Davis, JW ;
Haasz, AA .
JOURNAL OF NUCLEAR MATERIALS, 1997, 241 :37-51
[7]   Oxygen removal of codeposited a-C:D layers from tokamak tiles [J].
Davis, JW ;
Haasz, AA .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :478-484
[8]   In-vessel tritium retention and removal in ITER [J].
Federici, G ;
Anderl, RA ;
Andrew, P ;
Brooks, JN ;
Causey, RA ;
Coad, JP ;
Cowgill, D ;
Doerner, RP ;
Haasz, AA ;
Janeschitz, G ;
Jacob, W ;
Longhurst, GR ;
Nygren, R ;
Peacock, A ;
Pick, MA ;
Philipps, V ;
Roth, J ;
Skinner, CH ;
Wampler, WR .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :14-29
[9]  
FEDERICI G, UNPUB NUCL FUS
[10]  
*IAEA, 1998, FDR ITER EDA DOC SER, V16