The capability to inject deuterium pellets from the magnetic high field side ͑HFS͒ has been added to the DIII-D tokamak ͓J. L. Luxon and L. G. Davis, Fusion Technol. 8, 441 ͑1985͔͒. It is observed that pellets injected from the HFS lead to deeper mass deposition than identical pellets injected from the outside midplane, in spite of a factor of 4 lower pellet speed. HFS injected pellets have been used to generate peaked density profile plasmas ͓peaking factor (n e (0)/͗n e ͘) in excess of 3͔ that develop internal transport barriers when centrally heated with neutral beam injection. The transport barriers are formed in conditions where T e ϳT i and q(0) is above unity. The peaked density profiles, characteristic of the internal transport barrier, persist for several energy confinement times. The pellets are also used to investigate transport barrier physics and modify plasma edge conditions. Transitions from L-to H-mode have been triggered by pellets, effectively lowering the H-mode threshold power by 2.4 MW. Pellets injected into H-mode plasmas are found to trigger edge localized modes ͑ELMs͒. ELMs triggered from the low field side ͑LFS͒ outside midplane injected pellets are of significantly longer duration than from HFS injected pellets.

High repetition rate injection of deuterium pellets from the low-field side (LFS) of the DIII-D tokamak is shown to trigger high-frequency edge-localized modes (ELMs) at up to 12× the low natural ELM frequency in H-mode deuterium plasmas designed to match the ITER baseline configuration in shape, normalized beta, and input power just above the H-mode threshold. The pellet size, velocity, and injection location were chosen to limit penetration to the outer 10% of the plasma. The resulting perturbations to the plasma density and energy confinement time are thus minimal (<10%). The triggered ELMs occur at much lower normalized pedestal pressure than the natural ELMs, suggesting that the pellet injection excites a localized high-n instability. Triggered ELMs produce up to 12× lower energy and particle fluxes to the divertor, and result in a strong decrease in plasma core impurity density. These results show for the first time that shallow, LFS pellet injection can dramatically accelerate the ELM cycle and reduce ELM energy fluxes on plasma facing components, and is a viable technique for real-time control of ELMs in ITER.

Pellet injection from the inner wall is planned for use in ITER as the primary core fuelling system since gas fuelling is expected to be highly inefficient in burning plasmas. Tests of the inner wall guide tube have shown that 5 mm pellets with up to 300 m s−1 speeds can survive intact and provide the necessary core fuelling rate. Modelling and extrapolation of the inner wall pellet injection experiments from present day's smaller tokamaks leads to the prediction that this method will provide efficient core fuelling beyond the pedestal region. Using pellets for triggering of frequent small edge localized modes is an attractive additional benefit that the pellet injection system can provide. A description of the ITER pellet injection system's capabilities for fuelling and ELM triggering is presented and performance expectations and fusion power control aspects are discussed.

Deuterium pellets have been injected into plasmas in the DIII-D tokamak from the inner wall, top, and outer midplane port locations to investigate fuelling efficiency, mass deposition and interaction with edge localized modes (ELMs). Pellets injected from the outer midplane port (low field side (LFS)) show a large discrepancy in the mass deposition profile and fuelling efficiency from conventional pellet ablation theory, while the penetration depth compares favourably with theory. The mass deposition from pellets injected from inner wall and top locations is deeper than expected from ablation theory. The profile measurements indicate that pellet mass is deposited inside the measured penetration radius, thus verifying that a drift of the pellet ablatant is occurring in the major radius direction during the toroidal symmetrization process. The scaling of the measured drift magnitude in DIII-D is found to depend strongly on the pellet size and plasma pedestal temperature. Extrapolation to a burning plasma configuration on ITER is favourable for inner wall pellet fuel deposition depth well beyond the separatrix. Pellets injected into H-mode plasmas from all locations trigger ELMs with much larger ELM events induced by the outside midplane injected pellets. This suggests that the LFS is more sensitive to ELM triggering and may be the preferred location to inject very small pellets to trigger frequent small ELMs and thus minimize ELM induced damage to the divertor material surfaces.

High-pressure gas-jet injection of neon and argon is shown to be a simple and robust method to mitigate the deleterious effects of disruptions on the DIII-D tokamak. The gas jet penetrates to the central plasma at its sonic velocity. The deposited species dissipates >95% of the plasma by radiation and substantially reduces mechanical stresses on the vessel caused by poloidal halo currents. The gas-jet species-charge distribution can include >50% fraction neutral species which inhibits runaway electrons. The favorable scaling of this technique to burning fusion plasmas is discussed.