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Polevoi, A. R.*; Loarte, A.*; 林 伸彦; Kim, H. S.*; Kim, S. H.*; Koechl, F.*; Kukushkin, A. S.*; Leonov, V. M.*; Medvedev, S. Yu.*; 村上 匡且*; et al.
Nuclear Fusion, 55(6), p.063019_1 - 063019_8, 2015/05
被引用回数：33 パーセンタイル：84.89(Physics, Fluids & Plasmas)The operational space (
-
) for long pulse scenarios of ITER was assessed by 1.5D core transport modelling with pedestal parameters predicted by the EPED1 code. The analyses include the majority of transport models presently used for interpretation of experiments and ITER predictions. The EPED1 code was modified to take into account boundary conditions predicted by SOLPS for ITER. In contrast with standard EPED1 assumptions, EPED1 with the SOLPS boundary conditions predicts no degradation of the pedestal pressure as density is reduced. Lowering the plasma density to 
5-6 
10
m
leads to an increased plasma temperature (similar pedestal pressure), which reduces the loop voltage and increases the duration of the burn phase to 
1000 s with Q 
5 for 
13 MA at moderate normalised pressure (
2). These ITER plasmas require the same level of additional heating power as the reference Q = 10 inductive scenario at 15 MA. However, unlike the "hybrid" scenarios considered previously, these H-mode plasmas do not require specially shaped q profiles nor improved confinement in the core for the transport models considered in this study. Thus, these medium density H-mode plasma scenarios with 13 MA present an attractive alternative to hybrid scenarios to achieve ITER's long pulse Q 5 and deserve further analysis and experimental demonstration in present tokamaks.
Polevoi, A. R.*; 林 伸彦; Kim, H. S.*; Kim, S. H.*; Koechl, F.*; Kukushkin, A. S.*; Leonov, V. M.*; Loarte, A.*; Medvedev, S. Yu.*; 村上 匡且*; et al.
Europhysics Conference Abstracts (Internet), 37D, p.P2.135_1 - P2.135_4, 2013/07
Long-pulse operation 
1000 s with 
5 is foreseen in ITER to demonstrate high neutron fluence scenarios which can be of use for the nuclear technology and for the TBM. In this study we address the viability of achieving ITER's long-pulse scenario in plasma regimes with H-mode confinement level by characterizing the current-density operational space and the achievable Q with long pulse burning phases. The EPED1 model with boundary conditions from SOLPS predicts no degradation of pedestal pressure with decreasing density in ITER. Modelling of core transport with 1.5D transport models carried out with pedestal parameters predicted by EPED1+SOLPS indicate that there is a large operational space for long pulse plasma operation with high fusion gain 5. Reducing the plasma density to 5-6 10m leads to an increased plasma temperature (similar pedestal pressure) which reduces the loop voltage and increases the duration of the burn phase to 1000 s with 5 for 13 MA at moderate normalised pressure, 2. Unlike the "hybrid" scenarios, these H-mode plasmas do not require specially shaped q profiles nor improved confinement in the core for the majority of the transport models considered in this study. Thus, these medium density H-mode plasma scenarios present an attractive alternative to hybrid scenarios to achieve ITER's long pulse.
Labit, B.*; Pochelon, A.*; Rancic, M.*; Piras, F.*; Bencze, A.*; Bottino, A.*; Brunner, S.*; Camenen, Y.*; Chattopadhyay, P. K.*; Coda, S.*; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03
We present recent results on turbulence measurements in TCV L-mode plasmas. The transport reduction at negative triangularity (compared to positive triangularity) is reflected in the reduction of the temperature fluctuation level, in the low frequency part of the spectrum (30-150 kHz), measured by correlation ECE in the outer equatorial plane. The TEM induced transport computed from nonlinear gyrokinetic simulations is shown to decrease with decreasing triangularity and increasing collisionality. First results of an experimental scenario to reach the H-mode regime at negative triangularity in TCV are presented. Then, we report on an innovative divertor magnetic configuration: the snowflake (SF) divertor as opposed to the classical single-null (SN) divertor. For ELMy SF plasmas, the strike-point properties (density, temperature, fluctuation level,...) are studied with Langmuir probes (LPs) and compared with those of a SN configuration obtained within the same discharge.
