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- Publications
- Influence
Chapter 4: Power and particle control
- A. Loarte, B. Lipschultz, +33 authors E. Tsitrone
- Materials Science
- 1 June 2007
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 plasma… Expand
A full tungsten divertor for ITER: Physics issues and design status
- R. Pitts, S. Carpentier, +11 authors P. Stangeby
- Physics
- 1 July 2013
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, changing… Expand
Status and physics basis of the ITER divertor
- R. Pitts, A. Kukushkin, +5 authors M. Shimada
- 1 December 2009
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 of… Expand
Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation
- A. Loarte, Gta Guido Huijsmans, +19 authors A. Wingen
- Materials Science
- 1 March 2014
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-active… Expand
Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER
- T. Eich, A. Leonard, +16 authors J. Contributors
- Physics
- 29 August 2013
A multi-machine database for the H-mode scrape-off layer power fall-off length, λq in JET, DIII-D, ASDEX Upgrade, C-Mod, NSTX and MAST has been assembled under the auspices of the International… Expand
Physics basis and design of the ITER plasma-facing components
- R. Pitts, S. Carpentier, +10 authors P. Stangeby
- 1 August 2011
Abstract In ITER, as in any tokamak, the first wall and divertor plasma-facing components (PFC) must provide adequate protection of in-vessel structures, sufficient heat exhaust capability and be… Expand
Retarding field energy analyzer for the JET plasma boundary
Retarding field analyzers (RFAs) are essentially the only practical tool with which to measure the distribution of ion energies in the boundary plasma of magnetic fusion devices. The technique has… Expand
The new SOLPS-ITER code package
- S. Wiesen, D. Reiter, +9 authors S. Voskoboynikov
- Computer Science
- 1 August 2015
TLDR
Disruptions in ITER and strategies for their control and mitigation
- M. Lehnen, K. Aleynikova, +28 authors Efda Jet Workprogramme Contributors
- 1 August 2015
Abstract The thermal and electromagnetic loads related to disruptions in ITER are substantial and require careful design of tokamak components to ensure they reach the projected lifetime and to… Expand
Fluctuations and transport in the TCV scrape-off layer
- O. E. Garcia, J. Horacek, +4 authors J. Rasmussen
- Physics
- 27 June 2007
Fluctuations and particle transport in the scrape-off layer of TCV plasmas have been investigated by probe measurements and direct comparison with two-dimensional interchange turbulence simulations… Expand
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