Pellet fuelling in Tore Supra long discharges

Géraud, A.; Bucalossi, J.; Loarer, T.; Pégouriè, B.; Grisolia, C.; Gros, G.; Gunn, J.

doi:10.1016/j.jnucmat.2004.10.048

Cited by 17 publications

(12 citation statements)

References 5 publications

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“…The latter is shown in Fig. 5 [5]. The same fuelling frequency (particle flow rate divided by the plasma particle content) is found with the three different fuelling methods, indicating that the fuelling is largely dominated by the recycling.…”

Section: Particle Controlsupporting

confidence: 54%

Performance Issues for Actuators and Internal Components During Long Pulse Operation on Tore Supra

Bucalossi

2010

IEEE Trans. Plasma Sci.

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In a fusion device, long pulse operation adds a set of specific constraints on actuators and internal components. Some of these issues are analyzed through the 20-year experience of Tore Supra which is, to date, the largest Tokamak that is able to run long-duration discharges (hundreds of seconds). Superconducting magnet operation, RF heating and current drive, and particle fuelling issues are discussed. The impact on operation of the actively cooled environment is also assessed. Material erosion and fuel retention results showed the limits of the carbon as armor material for a fusion reactor. Real-time survey of the surface temperature of critical components integrated into the plasma control systems allows for safe operation at ITER relevant heat fluxes and accurate scenario control close to the limits.

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Section: Particle Controlsupporting

confidence: 54%

Performance Issues for Actuators and Internal Components During Long Pulse Operation on Tore Supra

Bucalossi

2010

IEEE Trans. Plasma Sci.

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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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“…But in present day mid-scale devices, the core fueling is yet dominated by the recycling flux. For this reason, in Tore Supra, two macroscopically similar L-mode discharges, the former fueled by gas puff, the latter by pellet injection, demonstrated identical particle balance despite very different fueling efficiencies: [35].…”

Section: Recent Results In Fuelingmentioning

confidence: 99%

Pellet Core Fueling in Tokamaks, Stellarators and Reversed Field Pinches

GEULIN¹,

Pégouriè²

2022

Plasma and Fusion Research

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In a reactor grade device, the role of core fueling is to replace the D and T consumed in the fusion reactions (almost negligible) and to compensate the plasma losses through the separatrix -including the material expelled out by the ELMs. For this purpose, deep material deposition is an advantage and pellet injection the best candidate for fueling the future machines. Fueling by pellet injection consists in two phases: First, the pellet ablation itself, then the ablated material homogenization and drift in the discharge. The former is a self-regulated process, which depends only of the local plasma characteristics. The second is a global phenomenon, which depends on the whole magnetic configuration. In this paper, we discuss first the basics of the ablation physics, emphasizing the role of the fast particles -ions and electrons -resulting from NBI or wave heating; then we describe the homogenization process and associated ∇B-induced drift. The drift acceleration and damping processes are described as well as the influence of the magnetic configuration (tokamak, stellarator and reversed field pinch) on the predominance of a given damping process and its consequence on the resulting deposition profile. We finally review the last results relative to pellet fueling in these different kind of devices and present the ongoing projects for future large-scale machines.

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Pellet fuelling in Tore Supra long discharges

Cited by 17 publications

References 5 publications

Performance Issues for Actuators and Internal Components During Long Pulse Operation on Tore Supra

Performance Issues for Actuators and Internal Components During Long Pulse Operation on Tore Supra

Chapter 4: Power and particle control

Pellet Core Fueling in Tokamaks, Stellarators and Reversed Field Pinches

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