Wall Recycling on the Superconducting Tokamak TRIAM-1M

Steady State Experiments on High Performance, Current Profile Control and Long Sustainment of LHCD Plasmas on the Superconducting Tokamak TRIAM-1M

TRIAM-1M (R0 =0.8 m, a×b=0.12 m×0.18 m and B = 8T) has the main mission to study the route toward a high field compact steady state fusion reactor. We have advanced steady state operation (SSO) programme in tokamaks, studied a heating mechanism for the high ion temperature (HIT) mode with an internal transport barrier, obtained an enhanced current drive (ECD) mode in an extended (higher power a...

Influence of wall thickness on the stability of the resistive wall mode in tokamak plasmas

Enhanced energy confinement and performance in a low-recycling tokamak.

Extensive lithium wall coatings and liquid lithium plasma-limiting surfaces reduce recycling, with dramatic improvements in Ohmic plasma discharges in the Current Drive Experiment-Upgrade. Global energy confinement times increase by up to 6 times. These results exceed confinement scalings such as ITER98P(y,1) by 2-3 times, and represent the largest increase in energy confinement ever observed f...

PFC / JA - 96 - 17 Screening of Recycling and Non - Recycling Impurities in the Alcator C - Mod Tokamak

The behavior of argon and nitrogen, injected into single null diverted ohmic discharges, has been compared. The screening of the divertor and scrape-off layer plasma is studied by comparing the number of impurity atoms in the core with the number injected by a calibrated gas puff. The effect of the poloidal position of injection on screening has been investigated. The core nitrogen density is d...

Influence of helium puff on divertor asymmetry in Experimental Advanced Superconducting Tokamak