Abstract:I-mode is a high-performance tokamak regime characterized by the formation of a temperature pedestal and enhanced energy confinement, without an accompanying density pedestal or drop in particle and impurity transport. I-mode operation appears to have naturally-occurring suppression of large ELMs in addition to its highly favorable scalings of pedestal structure and overall performance. Extensive study of the ELMy H-mode has led to the development of the EPED model, which utilizes calculations of coupled peeli… Show more
“…The instability causing these fluctuations is unclear. Similar to the C-Mod results [3], the pedestal p in I-mode is low, more than a factor of 4 below the critical gradient for peelingballooning mode stability reached before the ELMs in the H-mode phase as computed with ELITE [24], and also roughly a factor of 2 below the ideal infinite-n ballooning mode limit.…”
Section: Diii-dsupporting
confidence: 65%
“…As can be seen, however, there is a wide range from 0.6<H 98,y2 <1.3, and the DIII-D discharges so far tend to be on the low end of the range, H 98,y2 up to 0.8. In both C-Mod and AUG, E in I-mode does not degrade significantly with power as in H-mode [9,3,6,11], thus the best normalized and absolute performance is achieved when maximum power can be applied and pedestal pressures achieved. This trend contrasts with the E~P -0.7 scaling of H 98,y2 .…”
Section: Diii-dmentioning
confidence: 99%
“…However, C-Mod has demonstrated that the density can be increased by fueling after the transition to I-mode [9]. With sufficient input power, T ped can be maintained [3]. The limits in density, as for pressure, are generally set by I-H transitions.…”
Section: C-modmentioning
confidence: 99%
“…Particle transport will also be needed to remove helium 'ash' produced by fusion reactions. Without a particle barrier, plasma densities can also be more readily controlled by fueling or pumping, important for burn control [3]. Another critical advantage over H-mode is that the regime is naturally ELM-free, giving stationary conditions for many energy confinement times E without the need for active means to suppress ELMs.…”
Abstract. This paper describes joint ITPA studies of the I-mode regime, which features an edge thermal barrier together with L-mode-like particle and impurity transport and no Edge Issues for extrapolation to ITER and other future fusion devices are discussed.
“…The instability causing these fluctuations is unclear. Similar to the C-Mod results [3], the pedestal p in I-mode is low, more than a factor of 4 below the critical gradient for peelingballooning mode stability reached before the ELMs in the H-mode phase as computed with ELITE [24], and also roughly a factor of 2 below the ideal infinite-n ballooning mode limit.…”
Section: Diii-dsupporting
confidence: 65%
“…As can be seen, however, there is a wide range from 0.6<H 98,y2 <1.3, and the DIII-D discharges so far tend to be on the low end of the range, H 98,y2 up to 0.8. In both C-Mod and AUG, E in I-mode does not degrade significantly with power as in H-mode [9,3,6,11], thus the best normalized and absolute performance is achieved when maximum power can be applied and pedestal pressures achieved. This trend contrasts with the E~P -0.7 scaling of H 98,y2 .…”
Section: Diii-dmentioning
confidence: 99%
“…However, C-Mod has demonstrated that the density can be increased by fueling after the transition to I-mode [9]. With sufficient input power, T ped can be maintained [3]. The limits in density, as for pressure, are generally set by I-H transitions.…”
Section: C-modmentioning
confidence: 99%
“…Particle transport will also be needed to remove helium 'ash' produced by fusion reactions. Without a particle barrier, plasma densities can also be more readily controlled by fueling or pumping, important for burn control [3]. Another critical advantage over H-mode is that the regime is naturally ELM-free, giving stationary conditions for many energy confinement times E without the need for active means to suppress ELMs.…”
Abstract. This paper describes joint ITPA studies of the I-mode regime, which features an edge thermal barrier together with L-mode-like particle and impurity transport and no Edge Issues for extrapolation to ITER and other future fusion devices are discussed.
“…Stability calculations with ELITE are consistent with operation near the high-n or ballooning side of the peeling-ballooning stability diagram. 151 This combination of conditions exist on C-Mod in a restricted window in shaping (d U < 0.3, d L > 0.7, and j < 1.6).…”
The object of this review is to summarize the achievements of research on the Alcator C-Mod tokamak [Hutchinson et al., Phys. Plasmas 1, 1511 and Marmar, Fusion Sci. Technol. 51, 261 (2007)] and to place that research in the context of the quest for practical fusion energy. C-Mod is a compact, high-field tokamak, whose unique design and operating parameters have produced a wealth of new and important results since it began operation in 1993, contributing data that extends tests of critical physical models into new parameter ranges and into new regimes. Using only highpower radio frequency (RF) waves for heating and current drive with innovative launching structures, C-Mod operates routinely at reactor level power densities and achieves plasma pressures higher than any other toroidal confinement device. C-Mod spearheaded the development of the vertical-target divertor and has always operated with high-Z metal plasma facing componentsapproaches subsequently adopted for ITER. C-Mod has made ground-breaking discoveries in divertor physics and plasma-material interactions at reactor-like power and particle fluxes and elucidated a) Paper AR1 1, Bull. Am. Phys. Soc. 58, 21 (2013). b) Invited speaker.
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