Direct extrapolation of radial profile data to a self-ignited fusion reactor based on the gyro-Bohm model
- 30 July 2011
- journal article
- Published by Elsevier in Fusion Engineering and Design
- Vol. 86 (12) , 2879-2885
Abstract
No abstract availableKeywords
This publication has 29 references indexed in Scilit:
- Compact DEMO, SlimCS: design progress and issuesNuclear Fusion, 2009
- Optimization activities on design studies of LHD-type reactor FFHRFusion Engineering and Design, 2008
- The ARIES-CS Compact Stellarator Fusion Power PlantFusion Science and Technology, 2008
- Minimization of the external heating power by long fusion power rise-up time for self-ignition access in the helical reactor FFHR2mNuclear Fusion, 2007
- Chapter 1: Overview and summaryNuclear Fusion, 2007
- Comparison of turbulent transport models of L- and H-mode plasmasNuclear Fusion, 2006
- The Helias reactor HSR4/18Nuclear Fusion, 2001
- A comparative study of transport in stellarators and tokamaksPlasma Physics and Controlled Fusion, 1998
- A gyro-Landau-fluid transport modelPhysics of Plasmas, 1997
- Plasma transport simulation modelling for helical confinement systemsNuclear Fusion, 1992