Recycling and wall pumping in long duration discharges on TRIAM-1M

被引:43
作者
Sakamoto, M [1 ]
Itoh, S [1 ]
Nakamura, K [1 ]
Zushi, H [1 ]
Hanada, K [1 ]
Jotaki, E [1 ]
Pan, YD [1 ]
Kawasaki, S [1 ]
Nakashima, H [1 ]
机构
[1] Kyushu Univ, Res Inst Appl Mech, Adv Fus Res Ctr, Kasuga, Fukuoka, Japan
关键词
Charge exchange neutral flux - Wall pumping properties - Wall recycling properties - Wall saturation phenomena;
D O I
10.1088/0029-5515/42/2/307
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Recycling and wall pumping have been studied comparing low (approximate to10(18) m(-3)) and high (approximate to10(19) m(-3)) density long duration plasmas in TRIAM-1M. The recycling coefficient of each plasma increases with time. There exist two time constants in the temporal evolution of the recycling coefficient. One is a few seconds and the other is about 30 s. The wall pumping rates of low and high density plasmas are evaluated to be approximate to1.5 x 10(16) atoms m(-2) s(-1) and approximate to4 x 10(17) atoms m(-2) s(-1), respectively. The difference may be caused by the total number of diffused ions and the charge exchange neutral flux with an energy of less than 0.7 keV. In an ultra-long discharge (approximate to70 min), the recycling coefficient becomes 1 or more before again decreasing below 1, i.e. the wall repeats the process of being saturated and refreshed. In high power and high density experiments, wall saturation phenomena have been observed. The discharge duration limited by wall saturation decreases with an increase in density.
引用
收藏
页码:165 / 168
页数:4
相关论文
共 9 条
[1]   Composition of the plasma facing material Tokamakium [J].
Behrisch, R ;
Mayer, M ;
GarciaRosales, C .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :673-680
[2]  
BRUSATI M, 1992, INT C PLASM PHYS C 1, V16, P307
[3]  
CHATELIER M, 1998, COMMUNICATION
[4]   Structure of materials deposited aln the plasma facing surface in TRIAM-1M tokamak and the effect on hydrogen recycling [J].
Hirai, T ;
Fujiwara, T ;
Tokunaga, K ;
Yoshida, N ;
Komori, A ;
Motojima, O ;
Itoh, S .
JOURNAL OF NUCLEAR MATERIALS, 2000, 283 :1177-1181
[5]   Investigation on modification of plasma facing surface under long duration discharges by means of a collector probe in TRIAM-1M [J].
Hirai, T ;
Tokunaga, K ;
Fujiwara, T ;
Yoshida, N ;
Itoh, S .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1060-1065
[6]  
HIRAI T, 2000, J PLASMA FUSION RES, V3, P284
[7]  
ITOH S, 1997, FUSION ENERGY 1996, V3, P351
[8]   Steady state operation and control experiments on Tore Supra [J].
Saint-Laurent, F .
NUCLEAR FUSION, 2000, 40 (06) :1047-1055
[9]  
SAKAMOTO M, 1997, CONTROLLED FUSIO A 2, V21, P721