Erosion of plasma-facing components in ITER

被引:48
作者
Federici, G
Wuerz, H
Janeschitz, G
Tivey, R
机构
[1] ITER Garching JWS, D-85748 Garching, Germany
[2] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
关键词
ITER; erosion; component lifetime; plasma-material interactions; B2-EIRENE;
D O I
10.1016/S0920-3796(02)00298-3
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Erosion of ITER plasma-facing components (PFCs) is analysed with a strike-point carbon divertor target and,, plasma metallic walls (Be in the main chamber, and W divertor baffles), for a 'semi-detached' edge plasma regime, with Type I ELMs and off-normal events (e.g. disruptions). This paper builds on earlier studies [J. Nucl. Mater. 290-293 (2001) 260], refines the assessment of erosion during full DT operation with long cumulative burn time, and discusses erosion effects is expected during early phases of operation with H and DD plasmas. The present analysis should be viewed as more reliable for indicating trends, rather than providing firm quantitative predictions. Outstanding issues are identified and recommendations are made for further urgent RD. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:81 / 94
页数:14
相关论文
共 53 条
[11]   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
[12]   MODELING AND ANALYSIS OF EROSION AND REDEPOSITION FOR LIMITER AND DIVERTOR IMPURITY CONTROL-SYSTEMS [J].
BROOKS, JN .
NUCLEAR TECHNOLOGY-FUSION, 1983, 4 (01) :33-45
[13]  
Doerner R, COMMUNICATION
[14]   Plasma-material interactions in current tokamaks and their implications for next step fusion reactors [J].
Federici, G ;
Skinner, CH ;
Brooks, JN ;
Coad, JP ;
Grisolia, C ;
Haasz, AA ;
Hassanein, A ;
Philipps, V ;
Pitcher, CS ;
Roth, J ;
Wampler, WR ;
Whyte, DG .
NUCLEAR FUSION, 2001, 41 (12R) :1967-2137
[15]   Selection of plasma-facing materials in next-step fusion devices [J].
Federici, G ;
Barabash, V ;
Janeschitz, G ;
Tivey, R ;
Loarte, A ;
Roth, J ;
Skinner, CH ;
Wampler, WR .
19TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, PROCEEDINGS, 2002, :311-320
[16]   RACLETTE: A model for evaluating the thermal response of plasma facing components to slow high power plasma transients .2. Analysis of ITER plasma facing components [J].
Federici, G ;
Raffray, AR .
JOURNAL OF NUCLEAR MATERIALS, 1997, 244 (02) :101-130
[17]   Assessment of erosion and tritium codeposition in ITER-FEAT [J].
Federici, G ;
Brooks, JN ;
Coster, DP ;
Janeschitz, G ;
Kukuskhin, A ;
Loarte, A ;
Pacher, HD ;
Stober, J ;
Wu, CH .
JOURNAL OF NUCLEAR MATERIALS, 2001, 290 :260-265
[18]   In-vessel tritium retention and removal in ITER-FEAT [J].
Federici, G ;
Brooks, JN ;
Iseli, M ;
Wu, CH .
PHYSICA SCRIPTA, 2001, T91 :76-83
[19]   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
[20]  
FEDERICI G, IN PRESS J NUCL MAT