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Recent analysis of key plasma wall interactions issues for ITER
Abstract Plasma wall interaction (PWI) is important for the material choice in ITER and for the plasma scenarios compatible with material constraints. In this paper, different aspects of the PWI areExpand
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Chapter 4: Power and particle control
Progress, since the ITER Physics Basis publication (ITER Physics Basis Editors et al 1999 Nucl. Fusion 39 2137–2664), in understanding the processes that will determine the properties of the plasmaExpand
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A full tungsten divertor for ITER: Physics issues and design status
Abstract Budget restrictions have forced the ITER Organization to reconsider the baseline divertor strategy, in which operations would begin with carbon (C) in the high heat flux regions, changingExpand
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Status and physics basis of the ITER divertor
The ITER divertor design is the culmination of years of physics and engineering effort, building confidence that this critical component will satisfy the requirements and meet the challenge ofExpand
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Characteristics of type I ELM energy and particle losses in existing devices and their extrapolation to ITER
Analysis of Type I ELMs from ongoing experiments shows that ELM energy losses are correlated with the density and temperature of the pedestal plasma before the ELM crash. The Type I ELM plasma energyExpand
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Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation
Progress in the definition of the requirements for edge localized mode (ELM) control and the application of ELM control methods both for high fusion performance DT operation and non-activeExpand
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ELM control strategies and tools: status and potential for ITER
Operating ITER in the reference inductive scenario at the design values of Ip = 15 MA and QDT = 10 requires the achievement of good H-mode confinement that relies on the presence of an edge transportExpand
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A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak
A high-confinement plasma that is potentially useful for controlled fusion has now been sustained for over 30 s. The Experimental Advanced Superconducting Tokamak in Hefei, China, achieved thisExpand
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Assessment of erosion of the ITER divertor targets during type I ELMs
This paper presents the results of a preliminary assessment conducted to estimate the thermal response and erosion lifetime of the ITER divertor targets clad either with carbon-fibre composite orExpand
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