In-situ detection and removal of carbon debris -: a challenge for the next-step fusion device

被引:43
作者
Counsell, GF [1 ]
Wu, CH
机构
[1] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] IPP Garching, EFDA Close Support Unit, D-85748 Garching, Germany
来源
PHYSICA SCRIPTA | 2001年 / T91卷
关键词
D O I
10.1238/Physica.Topical.091a00070
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
In response to continuing concerns over the use of carbon containing materials in the DT phase of a next-step fusion device. a range of techniques for removing accumulated dust, flakes and films from the vessel as well as diagnosing the total inventory without vessel intervention have been evaluated. These techniques are described and the results of initial proof-of-principal experiments are discussed.
引用
收藏
页码:70 / 75
页数:6
相关论文
共 7 条
[1]   CLEANUP OF GRAPHITE FIRST WALLS IN JT-60 [J].
ARAI, T ;
TAKATSU, H ;
NINOMIYA, H ;
YOSHINO, R ;
HOSOGANE, N ;
YAMAMOTO, M ;
KODAMA, K ;
KAMINAGA, A ;
SHIMIZU, M .
JOURNAL OF NUCLEAR MATERIALS, 1989, 162 :743-747
[2]  
BROWNE A, 1996, P 19 S FUS TECH, P893
[3]   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
[4]  
ROHDE V, IN PRESS J NUCL MAT
[5]   Flaking of co-deposited hydrogenated carbon layers on the TFTR limiter [J].
Skinner, CH ;
Gentile, CA ;
Menon, MM ;
Barry, RE .
NUCLEAR FUSION, 1999, 39 (09) :1081-1085
[6]  
WATKINS KG, 1997, LASERS CONSERVATION
[7]  
WYKES M, 2000, IN PRESS P 21 S FUS