Boundary plasma and divertor phenomena in MAST

Counsell, G.; Kirk, A.; Ahn, J.-W.; Tabasso, A.; Yang, Yu

doi:10.1088/0741-3335/44/6/314

Cited by 46 publications

(51 citation statements)

References 9 publications

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“…The typical radial propagation velocity of the plasma ELM density perturbation in the SOL is of the order of vr ~ 1 km/s in all divertor experiments/ELM types [83,191,180,194]. This leads to an ELM radial propagation timescale of ~ 100 µs, which is similar to the timescale for parallel transport in the SOL during ELMs, as discussed in Sec.…”

Section: Interaction Of Type I Elms With the Main Chamber Plasma Facimentioning

confidence: 58%

“…Despite the large increase in radial transport associated with the ELM event, the poloidal footprint of the ELM power flux at the outer divertor does not show a significant broadening when compared to the inter-ELM power flux profile at the divertor [179,2,31,180]. A histogram summarising the results of a statistical analysis of the ELM power width (characterised by the full width at half maximum) at the outer divertor during the ELM is shown in Fig.…”

Section: Spatial Characteristics Of the Divertor Target Heat Flux Promentioning

confidence: 99%

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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: Interaction Of Type I Elms With the Main Chamber Plasma Facimentioning

confidence: 58%

Section: Spatial Characteristics Of the Divertor Target Heat Flux Promentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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“…86. 249 The shallow field line pitch for the inboard divertor in contrast to the strong outboard field line pitch can be seen in Fig. 85.…”

Section: Inboard/outboard Divertor Heat Load Asymmetrymentioning

confidence: 93%

Recent progress on spherical torus research

Ono

Kaita

2015

Physics of Plasmas

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The spherical torus or spherical tokamak (ST) is a member of the tokamak family with its aspect ratio (A = R0/a) reduced to A ∼ 1.5, well below the normal tokamak operating range of A ≥ 2.5. As the aspect ratio is reduced, the ideal tokamak beta β (radio of plasma to magnetic pressure) stability limit increases rapidly, approximately as β ∼ 1/A. The plasma current it can sustain for a given edge safety factor q-95 also increases rapidly. Because of the above, as well as the natural elongation κ, which makes its plasma shape appear spherical, the ST configuration can yield exceptionally high tokamak performance in a compact geometry. Due to its compactness and high performance, the ST configuration has various near term applications, including a compact fusion neutron source with low tritium consumption, in addition to its longer term goal of an attractive fusion energy power source. Since the start of the two mega-ampere class ST facilities in 2000, the National Spherical Torus Experiment in the United States and Mega Ampere Spherical Tokamak in UK, active ST research has been conducted worldwide. More than 16 ST research facilities operating during this period have achieved remarkable advances in all fusion science areas, involving fundamental fusion energy science as well as innovation. These results suggest exciting future prospects for ST research both near term and longer term. The present paper reviews the scientific progress made by the worldwide ST research community during this new mega-ampere-ST era.

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“…Recently pedestal structure has been examined through similarity studies between C-Mod/DIII-D [10] and between JET/JT-60U [11]. Studies of Type-I ELM evolution have also been reported from AUG [12][13][14], JET [15,16] and JT-60U [17,18] while studies of Type-III ELM evolution have been done at MAST [19,20] and TCV [21]. Studies have also been done on alternate small ELM regimes with good energy confinement such as the Type-II ELM regime in AUG [22], DIII-D [23] and JT60-U [24], the EDA regime in C-Mod [25], and the HRS regime in JFT-2M [26].…”

Section: Introductionmentioning

confidence: 99%

Structure, stability and ELM dynamics of the H-mode pedestal in DIII-D

Fenstermacher

Osborne²,

Leonard³

et al. 2005

Nucl. Fusion

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ABSTRACT. Experiments are described that have increased understanding of the transport and stability physics that set the H-mode edge pedestal width and height, determine the onset of Type-I edge localized modes (ELMs), and produce the nonlinear dynamics of the ELM perturbation in the pedestal and scrape-off layer (SOL). Models now exist for the n e pedestal profile and the p e height at the onset of Type-I ELMs, and progress has been made toward models of the T e pedestal width and nonlinear ELM evolution. Similarity experiments between DIII-D and JET suggested that neutral penetration physics plays an important role in the relationship between the width and height of the n e pedestal. Plasma physics appears to dominate in setting the T e pedestal width. Measured pedestal conditions including edge current at ELM onset agree with intermediate-n peeling-ballooning (P-B)

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Boundary plasma and divertor phenomena in MAST

Cited by 46 publications

References 9 publications

Chapter 4: Power and particle control

Chapter 4: Power and particle control

Recent progress on spherical torus research

Structure, stability and ELM dynamics of the H-mode pedestal in DIII-D

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