Overview of steady state tokamak plasma experiments in TRIAM-1M

Abstract

An overview of steady state tokamak studies in TRIAM-1M (R0 = 0.8 m, a × b = 0.12 m × 0.18 m and B = 8 T) is presented. The current ramp-up scenario without using centre solenoid coils is reinvestigated with respect to controllability of the current ramp-up rate at the medium density region of (1–2) × 1019 m−3. The plasma is initiated by ECH (fundamental o-mode at 170 GHz with 200 kW) at B = 6.7 T, and the ramp-up rate below the technical limit of 150 kA s−1 for ITER can be achieved by keeping the LH power less than 100 kW during the current ramp-up phase. The physics understanding of the enhanced current drive (ECD) mode around the threshold power level has progressed from a viewpoint of transition probability. A transition frequency, ftrans, for the ECD transition is determined as a function of PCD. At ∼70 kW no transition occurs for an ftrans value of ∼0.017 Hz, meaning almost zero transition probability. With increasing PCD > Pth, ftrans increases up to 10 Hz, and the transition tends to occur with high probability. The record value of the discharge duration is updated to 3 h 10 min in a low and low power (<10 kW) discharge. The global particle balance in long duration discharges is investigated, and the temporal change in wall pumping rate is determined. Although the density was low, the gas supply had to be stopped at 30 min after the plasma initiation to maintain the density constant. After that the density was sustained by the recycling flux alone until the end of the discharges. In addition to the recycling problem, in the high power and high density experiments, the localized PWI affects the SSO of the tokamak plasma. The effects of enhanced influx of metal impurities (Fe, Cr, Ni, Mo) on sustainment of the high performance ECD plasma are investigated. In order to evaluate the helium bombarding effects on the plasma facing component and hydrogen recycling in the future burning plasma, microscopic damage of metals exposed to long duration helium discharges was studied. The total exposure time was 128 s. From thermal desorption experiments for the specimens the amount of retained helium was evaluated as 3.9 × 1020 He m−2 and the scale length to be ∼1 mm in the SOL.

High field side launch of RF waves: A new approach to reactor actuators

“…Previous and nearterm long-pulse experiments (e.g. TRIAM-1M [3], Tore Supra [4], WEST [5], EAST [6], and ITER [7]) operate in regimes much less severe than reactor. Neutron issues are virtually nonexistent in these long-pulse experiments (except in ITER), and the scrape off layer (SOL) conditions are less likely to produce PMI damage.…”

Modeling of dust-particle behavior for different materials in plasmas

“…Table I lists the materials used for plasma facing components ͑PFC͒ in different fusion devices around the world and in ITER. [20][21][22][23][24][25][26][27][28][29][30][31][32][33][34][35][36][37][38][39] As seen, the commonly used materials are Be, C, Fe, Mo, and W. The choice of material in current devices is typically governed by specific thermochemical characteristics in hydrogen plasma environment, cost, and suitable construction properties as well as by plasma performance considerations. Note that boron was widely used in recent fusion plasma experiments as the restorable coating of PFCs.…”

A Scoping Study for High-Field-Side Launch of Lower Hybrid Waves on ADX MIT

“…Radio-frequency (RF) actuators also face challenges extrapolating to a reactor environment. Experiments conducted to date operate in a much less extreme environment compared with what is foreseen in a reactor [3], [4]. There are concerns about the survivability of the RF antennas located near the plasma on the low field side (LFS), and fundamental physics limits on the use of RF actuators in a high-temperature, high-density reactor.…”