A new pellet injector for steady state fuelling in Tore Supra

Géraud, A.; Viniar, I.; Skoblikov, S. V.; Lukin, A. Ya.; Umov, A. P.; Krasilnikov, I.A.; Reznichenko, P. V.; Gros, G.; Saille, A.; Gauthier, A.; Manzagol, J.; Perin, J.P.

doi:10.1016/s0920-3796(03)00224-2

Cited by 20 publications

(11 citation statements)

References 5 publications

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“…Currently, the fastest pellet accelerators, based on the multi-stage gas gun principle can launch pellets at up to 4500 m/s [493]; whereas, highest pellet speed achieved in a centrifuge, which is more suitable for steady state operation, is 1200 m/s [494]. A repetitive injector, able to operate at a frequency higher than 10 Hz, has also been developed for continuous fuelling [495] and successfully tested on long discharges in Tore Supra [496]. The planned ITER fuelling system is based on a centrifuge injector launching pellets at the high field side via a transfer system suitable for speeds up to 500 m/s [497].…”

Section: Pellet Fuellingmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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Abstract.Progress, since the ITER Physics Basis publication, in understanding the processes that will determine the properties of the plasma edge and its interaction with material elements in ITER is described. Experimental areas where significant progress has taken place are : energy transport in the SOL in particular of the anomalous transport scaling, particle transport in the SOL that plays a major role in the interaction of diverted plasmas with the main chamber material elements, ELM energy deposition on material elements and the transport mechanism for the ELM energy from the main plasma to the plasma facing components, the physics of plasma detachment and neutral dynamics including the edge density profile structure and the control of plasma particle content and He removal, the erosion of low and high Z materials in fusion devices, their transport to the core plasma and their migration at the plasma edge including the formation of mixed materials, the processes determining the size and location of the retention of tritium in fusion devices and methods to remove it and the processes determining the efficiency of the various fuelling methods as well as their development towards the ITER requirements. This experimental progress has been accompanied by the development of modelling tools for the physical processes at the edge plasma and plasma-materials interaction and the further validation of these models by comparing their predictions with the new experimental results. Progress in the modelling development and validation has been mostly concentrated in the following areas : refinement of the predictions for ITER with plasma edge modelling codes by inclusion of detailed geometrical features of the divertor and the introduction of physical effects, which can play a 2 major role in determining the divertor parameters at the divertor for ITER conditions such as hydrogen radiation transport and neutral-neutral collisions, modelling of the ion orbits at the plasma edge, which can play a role in determining power deposition at the divertor target, models for plasma-materials and plasma dynamics interaction during ELMs and disruptions, models for the transport of impurities at the plasma edge to describe the core contamination by impurities and the migration of eroded materials at the edge plasma and its associated tritium retention and models for the turbulent processes that determine the anomalous transport of energy and particles across the SOL. The implications for the expected performance of the reference regimes in ITER, the operation of the ITER device and the lifetime of the plasma facing materials are discussed. Introduction.This chapter outlines the significant progress achieved since the ITER Physics Basis in understanding basic scrape-off layer (SOL) and divertor processes in a tokamak. The interaction of plasma with first-wall surfaces will have considerable impact on the performance of fusion plasmas, the lifetime of plasma facing components, and the retention of tritium in next step Burning Plasma E...

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Section: Pellet Fuellingmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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“…The HFPI was designed and built on the basis of the screw extruder technology and pneumatic acceleration using the blower gun concept. It forms an upgrade of a steady state launcher type developed for Tore Supra [9]. The launcher shown schematically in figure 1 was designed to meet both requirements for fuelling and ELM pacing.…”

Section: Performance Of the Hfpimentioning

confidence: 99%

ELM pacing investigations at JET with the new pellet launcher

Lang

Alonso²,

Alper

et al. 2011

Nucl. Fusion

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Abstract.A new pellet injection system was installed at JET designed for both fuelling and ELM pacing. The purpose of the pacing section was to validate pellet ELM pacing as a suitable tool for ELM mitigation in ITER. Pellet pacing was confirmed at the large size scale of JET. The dynamics of triggered ELMs was investigated with respect to their spontaneous counterparts. Triggered ELMs show features also typical for spontaneous ELMs in several operational regimes. Since none of these regimes was unsettled by the pellets this is a strong hint for compatibility with other plasma control tools. Observations and modelling results indicate the ELM triggering occurs by the pellet ablation plasmoid evolving into the first ELM filament followed by a poloidal spread of the instability. An ELM obviously can be forced by a pellet due to the strong local perturbation imposed already under unusual onset conditions but then evolves like any ELM typical for the according plasma regime. For tool optimization the pellet mass and hence the convective confinement losses imposed have to be minimized. In our experiments, a lower mass threshold was observed for the first time. It has been found that to reliably trigger an ELM the pellet needs to be sufficiently large (and fast) to penetrate close to the pedestal top. Recent investigations are clear steps forward to validate the pellet pacing approach for ITER.

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“…The new pellet injector installed on Tore Supra in 2003 [6] was built by PELIN Laboratory in St Petersburg (Russia). It is based on a screw extruder, cooled by liquid helium, producing a continuous hydrogen or deuterium rod of ice of rectangular cross section.…”

Section: Pellet Injector and Diagnosticsmentioning

confidence: 99%