Experimental demonstration of tokamak fuelling by compact toroid injection

Raman, R.; Martín, F.; Haddad, E.; St-Onge, M.; Abel, G.; Côté, C.; Richard, Nicolas; Blanchard, N.; Mai, H.; Quirion, B.; Lachambre, J. L.; Gauvreau, J. L.; Pacher, G.W.; Decoste, R.; Gierszewski, P.; Hwang, D. Q.; Hirose, Akira; Savoie, S.; Leblanc, B; McLean, H. S.; Xiao, Chunsheng; Stansfield, B.L.; Cote, A.; Michaud, Daniel; Chartré, M.

doi:10.1088/0029-5515/37/7/i05

Cited by 47 publications

(32 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…CT injection into tokamak plasmas was pioneered in TdeV [500] and was investigated in JFT-2M [501]. CT injection has not matured into a continuous standard fuelling technique so far.…”

Section: Compact Toroid Fuellingmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

View full text Add to dashboard Cite

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...

show abstract

“…CT injection into tokamak plasmas was pioneered in TdeV [500] and was investigated in JFT-2M [501]. CT injection has not matured into a continuous standard fuelling technique so far.…”

Section: Compact Toroid Fuellingmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

View full text Add to dashboard Cite

show abstract

“…In recent years, compact toroid ͑CT͒ plasmoid injection has been considered as one of the advanced fueling methods for a fusion reactor, [1][2][3][4][5][6][7][8][9][10][11][12][13][14] since the injection velocity of fuel by this method is much faster than that by any of the other methods. Since 1997, in the Japan Atomic Energy Research Institute ͑JAERI͒, the CT injection experiment into JAERI Fusion Torus-2M ͑JFT-2M͒ has been carried out in cooperation with the Himeji Institute of Technology.…”

Section: Introductionmentioning

confidence: 99%

Deceleration mechanism of spheromak-like compact toroid penetrating into magnetized plasmas

Suzuki¹,

Hayashi

Kishimoto³

2000

Physics of Plasmas

View full text Add to dashboard Cite

To understand the fueling process in a fusion device by a spheromak-like compact toroid (SCT) injection method, magnetohydrodynamic numerical simulations, where a SCT is injected into magnetized target plasmas, have been carried out so far. As a result, it has been found that the SCT penetration into magnetized target plasmas is accompanied by complex physical dynamics, which is not adequately described by the conventional simple theoretical model. In this study, based on the previous simulation results, a new theoretical model to determine the penetration depth of the SCT is represented. Here, the SCT is considered to be decelerated not only by the magnetic pressure force but also by the magnetic tension force, which is generated by the bending of the target magnetic field as a result of the SCT penetration. Furthermore, by comparing the penetration depth of the SCT estimated from the theoretical model with that in the simulation, the accuracy of the model is examined. Finally, the effect of magnetic reconnection on the SCT penetration is discussed.

show abstract

“…The first successful demonstration of tokamak fueling through CT injection was performed on TdeV [18,28] and showed that the tokamaks' particle inventory was increased without changes in the tokamak loop voltage or plasma current. As well, and possibly most important, it was shown that the tokamak was fueled with little to no increase in magnetohydrodynamic instabilities as well as an increased confinement time.…”

Section: Nuclear Fusion and The Tokamak Reactormentioning

confidence: 99%

Repetitive operation of the University of Saskatchewan Compact Torus Injector

Pant

Hirose

Xiao

2010

Radiation Effects and Defects in Solids

View full text Add to dashboard Cite

Development of fueling technologies for modern and future tokamak reactors is essential for their implementation in a commercial energy production setting. Compared to the presently available fueling technologies, gas or cryogenic pellet injection, compact torus injection presents an effective and efficient method for directly fueling the central core of tokamak plasmas. Fueling of the central core of a tokamak plasma is pivotal for providing efficient energy production. The central core plasma of a reactor contains the greatest density of fusion processes. For consistent and continuous fueling of tokamak fusion reactors, compact torus injectors must be operated in a repetitive mode.The goal of this thesis was to study the feasibility of firing the University of Saskatchewan Compact Torus Injector (USCTI) in a repetitive mode. In order to enable USCTI to fire repetitively, modifications were made to its electrical system, control system and data acquisition system. These consisted primarily of the addition of new power supplies, to enable fast charging of the many capacitor banks used to form and accelerate the plasma. The maximum firing rate achieved on USCTI was 0.33 Hz, an increase from the previous maximum firing rate of 0.2 Hz achieved at UC Davis.Firing USCTI in repetitive modes has been successful. It has been shown that the CTs produced in any given repetitive series are properly formed and repeatable. This is made evident through analysis of data collected from the CTs' magnetic fields and densities as they traveled along the injector barrel. The shots from each experiment were compared to the series' mean data and were shown to be consistent over time.Calculations of their correlations show that there are only minimal deviations from shot to shot in any given series.ii

show abstract

Experimental demonstration of tokamak fuelling by compact toroid injection

Cited by 47 publications

References 8 publications

Chapter 4: Power and particle control

Chapter 4: Power and particle control

Deceleration mechanism of spheromak-like compact toroid penetrating into magnetized plasmas

Repetitive operation of the University of Saskatchewan Compact Torus Injector

Contact Info

Product

Resources

About