Testing of tungsten and tantalum limiters at the TEXTOR tokamak: Material performance and deuterium retention

被引:25
作者
Hirai, T [1 ]
Rubel, M
Philipps, V
Huber, A
Tanabe, T
Wada, M
Ohgo, T
Pospieszczyk, A
Sergienko, G
Wienhold, P
机构
[1] Forschungszentrum Julich, Inst Plasma Phys, EURATOM Assoc, TEC, D-52425 Julich, Germany
[2] Royal Inst Technol KTH, Alfven Lab, EURATOM Assoc, S-10044 Stockholm, Sweden
[3] Nagoya Univ, CIRSE, Chikusa Ku, Nagoya, Aichi 464, Japan
[4] Doshisha Univ, Dept Elect, Kyoto 610039, Japan
[5] Fukuoka Univ Educ, Dept Phys, Fukuoka 8114192, Japan
[6] Russian Acad Sci, Inst High Temp Phys, Assoc IVTAN, Moscow 127412, Russia
关键词
D O I
10.1238/Physica.Topical.103a00059
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
Tungsten and tantaium were examined in the TEXTOR tokamak as test limiters in order to compare their performance under plasma operation and to recognise fuel recycling on endothermic (W) and exothermic (Ta) hydrogen absorbers. Differences have been noticed in the distribution and microstructure of co-deposits. in the fuel inventory in the bulk of metals and, in the deuterium release mechanism (ratio of molecules to atoms). As a result of poor thermal conductivity. the surface temperature of Ta during the power deposition was higher than that of W and it increased shot-by-shot because of the degradation of thermal properties due to surface modification. Results on thermal response, fuel recycling and inventory show that. as a candidate material for plasma facing components. tungsten is superior to tantalum.
引用
收藏
页码:59 / 62
页数:4
相关论文
共 27 条
[1]  
ALEFELD G, 1978, TOPICS APPL PHYSICS, V28
[2]  
Brandes E.A., 1983, SMITHELLS METALS REF
[3]  
Campbell IE, 1967, HIGH TEMPERATURE MAT
[4]   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
[5]   SOLUTION AND DIFFUSION OF HYDROGEN IN TUNGSTEN [J].
FRAUENFELDER, R .
JOURNAL OF VACUUM SCIENCE & TECHNOLOGY, 1969, 6 (03) :388-+
[6]   Deuterium release and microstructure of tantalum-tungsten twin limiter exposed in TEXTOR-94 [J].
Hirai, T ;
Philipps, V ;
Tanabe, T ;
Wada, M ;
Huber, A ;
Brezinsek, S ;
von Seggern, J ;
Linke, J ;
Ohgo, T ;
Ohya, K ;
Wienhold, P ;
Pospieszczyk, A ;
Sergienko, G .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) :79-83
[7]   Conclusions about the use of tungsten in the divertor of ASDEX Upgrade [J].
Krieger, K ;
Maier, H ;
Neu, R .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :207-216
[8]   Performance of beryllium, carbon, and tungsten under intense thermal fluxes [J].
Linke, J ;
Akiba, M ;
Bolt, H ;
Breitbach, G ;
Duwe, R ;
Makhankov, A ;
Ovchinnikov, I ;
Rodig, M ;
Wallura, E .
JOURNAL OF NUCLEAR MATERIALS, 1997, 241 :1210-1216
[9]   Performance of tungsten coatings as plasma facing components used in ASDEX Upgrade [J].
Maier, H ;
Kötterl, S ;
Krieger, K ;
Neu, R ;
Balden, M .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :921-926
[10]   Erosion and deposition in the ASDEX Upgrade tungsten divertor experiment [J].
Maier, H ;
Krieger, K ;
Balden, M ;
Roth, J .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :1003-1008