Wayne Arter Member Ieee Elizabeth Surrey Damian.B. King
There is an increasing need to model plasma inter- action with complex engineered surfaces, notably to verify that power deposition rates are acceptable. The SMARDDA algorithm has been developed to meet this requirement, with particular reference to the neutral beam ducts that feed into the vacuum vessels of tokamaks. Application to limiters and di…
PublishedE. Surrey M. Porton A. Caballero T. Davenne D. Findlay A. Letchford J. Thomason J. Marrow S. Roberts Andrei Seryi B. Connolly P. Mummery H. Owen
The erosion and high neutron flux in a fusion power plant results in the need for frequent remote replacement of the plasma facing components. This is a complex and time consuming remote handling operation and its duration directly affects the availability and therefore the commercial viability of the power plant. A tool is needed to allow the main…
PublishedD. Taylor S. Lilley A. Turner A. Davis
A significant functional upgrade is planned for the Mega Ampere Spherical Tokamak (MAST) device, located at Culham in the UK, including the implementation of a notably greater neutral beam injection power. This upgrade will cause the emission of a substantially increased intensity of neutron radiation for a substantially increased amount of time up…
PublishedL.W.G. Morgan L.W. Packer
The generation of tritium in sufficient quantities is an absolute requirement for a next step fusion device such as DEMO due to the scarcity of tritium sources. A number of methods have been proposed in order to meet this requirement, however a lithium-based tritium breeding blanket that surrounds the fusion plasma is widely considered to be the mo…
PublishedAnthony J. Webster JET EFDA Contributors
The generic question is considered: How can we determine the probability of an otherwise quasirandom event, having been triggered by an external influence? A specific problem is the quantification of the success of techniques to trigger, and hence control, plasma instabilities in magnetically confined fusion (MCF) experiments. The successful develo…
PublishedM. Kovari R. Kemp H. Lux P. Knight J. Morris D.J. Ward
PROCESS is a reactor systems code – it assesses the engineering and economic viability of a hypothetical fusion power station using simple models of all parts of a reactor system, from the basic plasma physics to the generation of electricity. It has has been used for many years, but details of its operation have not been previously published. Th…
PublishedM-L. Mayoral V. Bobkov A. Czarnecka I. Day A. Ekedahl P. Jacquet M. Goniche R. King K. Kirov E. Lerche J. Mailloux D. Van Eester O. Asunta C. Challis D. Ciric J.W. Coenen L. Colas C. Giroud M. Graham I. Jenkins E. Joffrin T. Jones D.
The major aspects linked to the use of the JET auxiliary heating systems: NBI, ICRF and LHCD, in the new JET ITER-like wall (JET-ILW) are presented. We show that although there were issues related to the operation of each system, efficient and safe plasma heating was obtained with room for higher power. For the NBI up to 25.7MW was safely injected;…
PublishedF. Militello V. Naulin A.H. Nielsen
Numerical simulations of L-mode turbulence in the Scrape-Off Layer (SOL) are used to construct power scaling laws for the characteristic decay lengths of the temperature, density and heat flux at the outer midplane. Most of the results obtained are in qualitative agreement with the experimental observations despite the known limitation of the model…
PublishedI.T. Chapman V. Igochine M. Maraschek P.J. Mccarthy G. Tardini The Asdex Upgrade Ecrh Group The Asdex Upgrade Team
Sawtooth control using steerable electron cyclotron current drive (ECCD) has been demonstrated in ASDEX Upgrade plasmas with a significant population of energetic ions in the plasma core and long uncontrolled sawtooth periods. The sawtooth period is found to be minimised when the ECCD resonance is swept to just inside the q = 1 surface. By utilisin…
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