T. Eade D. Stonell A. Turner
As nuclear fusion progresses towards a sustainable energy source and the power of tokamak devices increases, a greater understanding of the radiation fields will be required. As well as on-load radiation fields, off-load or shutdown radiation field are an important consideration for the safety and economic viability of a commercial fusion reactor. …
Preprint PublishedE. Surrey A.J.T. Holmes
A one dimensional model of the magnetic multipole volume plasma source has been developed for use in intense ion/neutral atom beam injectors. The model uses plasma transport coefficients for particle and energy flow to create a detailed description of the plasma parameters along an axis parallel to that of the extracted beam. Primarily constructed …
Preprint PublishedE. Surrey A.J.T. Holmes
A one dimensional model of the magnetic multipole volume plasma source has been developed for application to intense ion/neutral atom beam injectors. The model uses plasma transport coefficients for particle and energy flow to create a detailed description of the plasma parameters along an axis parallel to that of the extracted beam. In this paper …
Preprint PublishedN.R. Walkden J. Adamek S. Allan B. D. Dudson S. Elmore G. Fishpool J. Harrison A. Kirk M. Komm
The ball pen probe (BPP) technique is used successfully to make profile measurements of plasma potential, electron temperature, and radial electric field on the Mega Amp Spherical Tokamak. The potential profile measured by the BPP is shown to significantly differ from the floating potential both in polarity and profile shape. By combining the BPP p…
Preprint PublishedE.Peluso M.Gelfusa A.Murari I.Lupelli P.Gaudio
The H mode of confinement in Tokamaks is characterized by a thin region of high gradients, located at the edge of the plasma and called the Edge Transport Barrier. Even if various theoretical models have been proposed for the interpretation of the edge physics, the main empirical scaling laws of the plasma confinement time are expressed in terms of…
PublishedL. Giacomelli S. Conroy F. Belli G. Gorini E. Joffrin V. Kiptily E. Lerche A. Murari V.V. Plyusnin S. Popovichev C. Reux M. Riva D.B. Syme JET EFDA Contributors
The Joint European Torus (JET, Culham, UK) is the largest tokamak in the world. JET has been upgraded over the years and recently it has also become a test facility of the components designed for ITER, the next step fusion machine under construction in Cadarache (France). At JET, the neutron emission profile of Deuterium (D) or Deuterium-Tritium (D…
PublishedM. Fitzgerald M. J. Hole Z. S. Qu
In this work, we generalise linear magnetohydrodynamic (MHD) stability theory to include equilibrium pressure anisotropy in the uid part of the analysis. A novel `single-adiabatic' (SA) uid closure is presented which is complementary to the usual `double-adiabatic' (CGL) model and has the advantage of naturally reproducing exactly the MHD spectrum …
Preprint PublishedD. Hancock T. Barrett J. Foster M. Fursdon G. Keech S. McIntosh W. Timmis M. Rieth J. Reiser
The design of a divertor target for DEMO remains one of the most challenging engineering tasks to be overcome on the path to fusion power. Under the European DEMO programme, a promising concept known as Thermal Break has been developed at CCFE. This concept is a variation of the ITER tungsten divertor in which the pure Copper interlayer between Cop…
Preprint PublishedT. Eade S. Lilley Z. Ghani E. Delmas
The requirement for maintenance in areas with relatively high shutdown dose rate fields is a key issue to address in the design and engineering of ITER, next generation devices and future commercial fusion reactors. In order to estimate the shutdown dose rate during maintenance and intervention scenarios CCFEs Mesh Coupled implementation of the R…
Preprint PublishedV. Parail G. Corrigan P. Da Silva Aresta Belo E. De La Luna D. Harting F. Koechl T. Koskela A. Meigs E. Militello-Asp M. Romanelli M. Tsalas JET-EFDA contributors
The influence of the ITER-like Wall (ILW) with divertor target plate made of tungsten (W), on plasma performance in JET H-mode is being investigated since 2011 (see [1] and references therein). One of the key issues in discharges with low level of D fuelling is observed accumulation of W in the plasma core, which leads to a reduction in plasma perf…
Preprint Published