Performance of the Ti doped graphite RG-Ti-91 at the divertor of the Tokamak ASDEX Upgrade

被引:10
作者
Burtseva, T
Barabash, V
Mazul, I
GarciaRosales, C
Deschka, S
Behrisch, R
Herrmann, A
机构
[1] EURATOM,MAX PLANCK INST PLASMAPHYS,D-85748 GARCHING,GERMANY
[2] EURATOM,MAX PLANCK INST PLASMAPHYS,D-10117 BERLIN,GERMANY
关键词
ASDEX Upgrade; poloidal divertor; low Z wall material; wall particle retention; energy balance;
D O I
10.1016/S0022-3115(97)80128-6
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
During the 1994/1995 discharge period two graphite tiles at the outer and the inner lower divertor plates of the tokamak ASDEX-Upgrade have been replaced by tiles of RG-Ti-91 which is a graphite, doped with about 2 at% of Ti and subsequently treated at high temperatures and pressures to achieve a high thermal conductivity perpendicular to one direction. The RG-Ti-91 tiles have been installed with the directions of high thermal conductivity normal to the plasma exposed surface. The plates have been exposed to about 670 tokamak discharges each lasting about 2 to 3 s. The performance of the discharges has not been influenced by the presence of the RG-Ti-91 tiles, i.e., no additional impurities, such as Ti. have been observed in the plasma. The temperature increase of the RG-Ti-91 tiles during high power loads was about a factor 2 lower than the temperature increase of fine grain graphite plates. The surfaces of the tiles showed preferential erosion of the carbon. and TiC crystallites staying out on the surfaces. This is similar to the surface structure which develops at D-ion bombarded surfaces of this RG-Ti-91 material in the laboratory.
引用
收藏
页码:716 / 721
页数:6
相关论文
共 23 条
[1]   HYDROGEN AND DEUTERIUM RETENTION IN WALL SAMPLES OF JET [J].
BEHRISCH, R ;
EHRENBERG, J ;
WIELUNSKI, M ;
MARTINELLI, AP ;
BERGSAKER, H ;
EMMOTH, B ;
DEKOCK, L ;
COAD, JP .
JOURNAL OF NUCLEAR MATERIALS, 1987, 145 :723-726
[3]   HEAT REMOVAL BY THE DIVERTOR PLATE AND LIMITER MATERIALS IN FUSION-REACTORS [J].
BEHRISCH, R ;
VENUS, G .
JOURNAL OF NUCLEAR MATERIALS, 1993, 202 (1-2) :1-9
[4]  
BEHRISCH R, 1987, J NUCL MATER, V155, P95
[5]  
BURTSEVA TA, 1992, J NUCL MATER, V191, P309
[6]  
BURTSEVA TA, 1994, FUSION TECHNOLOGY 19, P235
[7]  
CHAPPIUS P, 1989, FUS TECHN 1988 P 15
[8]   THE RETAINED DEUTERIUM INVENTORY IN JET AND IMPLICATIONS FOR TRITIUM OPERATION [J].
COAD, JP ;
BEHRISCH, R ;
BERGSAKER, H ;
EHRENBERG, J ;
EMMOTH, B ;
PARTRIDGE, J ;
SAIBENE, G ;
SARTORI, R ;
SIMPSON, JCB ;
WANG, WM .
JOURNAL OF NUCLEAR MATERIALS, 1989, 162 :533-541
[9]   EXPERIENCE WITH LIMITER AND WALL MATERIALS IN JET [J].
DIETZ, KJ .
JOURNAL OF NUCLEAR MATERIALS, 1988, 155 :8-14
[10]   PLASMA MATERIAL INTERACTIONS IN TFTR [J].
DYLLA, HF .
JOURNAL OF NUCLEAR MATERIALS, 1987, 145 :48-60