The ITER research plan has been recently re-elaborated to lay out a robust path to achieve the Project’s fusion production goals and technical objectives. This includes changes to device and ancillaries configuration to minimize previously identified risks such as: changing plasma facing material of the first wall from beryllium (Be) to tungsten (W), modifying the heating and current drive...
Significant progress has been achieved on EAST in the development of long-pulse steady-state advanced plasmas in support of future fusion reactors (e.g ITER and CFETR) since last IAEA technical meeting (TM) on long-pulse operation (LPO). A new record of reproducible 403s H-mode plasmas has been achieved with full metal wall with EAST improved flexibilities and capabilities. EAST scientific...
Long pulse operation in a W environment : feedback from WEST
P. Manas1, P. Maget1, R. Dumont, J. Dominski2, T. Fonghetti1, J. Morales1, A. Ekedahl1, N. Fedorczak1, J. Gaspar3, E. Tsitrone1, and the WEST Team*
1 CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
2 Princeton Plasma Physics Laboratory, 100 Stellarator rd, Princeton 08540 New Jersey,USA
3 Aix-Marseille Université, CNRS, IUSTI,...
The mission of the KSTAR device is to sustain high-performance plasma for 300 seconds[1]. In the 2023 experimental campaign, KSTAR maintained H-mode plasma for 102 seconds. The operating conditions of this discharge were $I_P$=400 kA, $B_T$=1.95 T, $P_{NBI}$=3.9 MW, and $P_{EC}$=1.1 MW. The plasma characteristics of this plasma were $V_{loop}$~70 mV, $β_P$~2.5, $β_N$~2.1, $T_{e,core}$>6.0 keV,...
Stellarators offer a relatively straightforward route to steady state fusion power operation. Future reactors, such as DEMO, are expected to operate quasi-continuously with divertor heat fluxes as low as 5 MW/m$^2$ [1]. This requires that most of the power leaving the plasma has to be radiated away by the plasma impurities in the so-called detached regime, in which the divertor target plates...
This study shows the experimental results on the density limit and ultra-high neutral pressure in the sub-divertor volume at LHD for high density steady state operation, and good particle exhaust.
A new density scaling for tokamaks was reported in [1] based on edge turbulent transport. It shows a strong dependence on heating power and is similar to the Sudo density limit in the helical...
Recent high poloidal beta ($\beta_P$) scenario experiments on EAST and DIII-D have made coordinated breakthroughs for high confinement quality at high density near the Greenwald limit. Experiments on DIII-D have achieved $f_{Gr}$ ($=$line-averaged density$/$Greenwald density) above 1 simultaneously with $H_{98y2}$ around 1.5, as required in compact steady-state fusion pilot plant designs but...
In the last experimental campaign of the JET tokamak in December 2023, long discharge operation (>30s) in deuterium plasmas was developed to assess the sustainment of the plasma performance over many resistive time scales and to address plasma-wall interaction physics in a full metallic environment with the ITER-like wall (ILW), with a W divertor and a Be first wall [1]. Two types of long...
