UKAEA Papers

"Co-operative scattering of laser light by a thetatron plasma"

• DE Evans
• MJ Forrest
• J Katzenstein

"Scattering of electromagnetic waves by electroacoustic plasma waves"

• PF Little
• SM Hamberger

"The determination of atomic collision cross sections using crossed electron and ion beams and some sources of error in such experiments"

• MFA Harrison

"A measurement of the cross section for production of He ions by electron impact excitation of ground state helium ions"

• DF Dance
• MFA Harrison
• ACH Smith

"Effect of fuel isotope mass on q-profile formation in JET hybrid plasmas"

• C.D. Challis
• S. Brezinsek
• I. Coffey
• M. Fontana
• N. Hawkes
• D. Keeling
• D. King
• G. Pucella
• E. Viezzer
• JET Contributors

The initial current ramp phase of JET hybrid plasmas is used to optimise the target q-profile for main heating to allow access to high beta and avoid MHD instabilities. Mixed protium-deuterium experiments, carried out at JET since the installation of the beryllium-tungsten wall, have shown that the q-profile evolution during this Ohmic phase varies…

"Benchmarking the TGLF turbulent transport code for a Q=10 burning spherical tokamak plasma using GS2"

• B. Patel
• C. Challis
• D. Dickinson
• L. Garzotti
• F. Koechl
• C. Roach
• G. Staebler
• H. Wilson

Spherical Tokamaks (STs) could provide a route towards a compact fusion reactor due to advantageous properties such as high plasma beta. A GW-scale ST plasma is explored where Q=10 and R=2.5m. In this design 110 MW of NBI is needed to provide 9 MA of noninductive current, where the remaining 12 MA is pressure driven. To penetrate into the core a 1 …

"The EUROfusion Materials Property Handbook for DEMO In-vessel Components – Status and the challenge to improve confidence level for engineering data"

• Michael Gorley
• Eberhard Diegele
• Ermile Gaganidze
• Ferenc Gillemot
• Gerald Pintsuk

The development of a specific materials database and handbook, for engineering design of in-vessel components of EU-DEMO, is an essential requirement for assessing the structural integrity by design. For key in-vessel materials, including EURFOER97, CuCrZr, Tungsten and dielectric and optical materials, this development has been ongoing now within …

"Towards understanding the relative role of divertor geometry and magnetic topology on detachment"

• A. Fil
• B. Dudson
• B. Lipschultz
• D. Moulton
• O. Myatra
• K. Verhaegh
• O. Fevrier
• J. Harrison
• A. Thornton
• M. Wensing

Plasma detachment needs to be achieved in ITER [1] and future devices such as DEMO to dissipate most of the power in the Scrape-Off-Layer (SOL) and reduce the particle flux reaching the divertor targets. In order to enhance our capability to improve current, and design future tokamaks, we must improve our understanding of the relative effect on det…

"Predicting Scrape-Off Layer profiles and filamentary transport for reactor relevant devices"

• F. Militello
• R. Akers
• L. Appel
• B. Cannas
• S. Carcangiu
• B. Dudson
• A. Fanni
• T. Farley
• A. Kirk
• J.R. Harrison
• B. Lipshultz
• A. Montisci
• T. Nicholas
• J.T. Omotani
• F. Pisano
• F. Riva
• G. Sias
• N.R. Walkden
• A. Wynn
• the MAST
• JET5 teams

In magnetic confinement devices, boundary turbulence is responsible for transporting plasma and energy from the well-confined region towards the material surfaces where it can severely harm reactor relevant machines. It is therefore essential to develop a solid understanding of the mechanisms behind the transport in the edge of the plasma. Large fl…

"Systems Studies of Double Null Divertor Models"

• A.J. Pearce
• R. Kembleton
• M. Kovari
• H. Lux
• J. Morris
• M. Siccinio

As conceptual design options for a demonstration fusion power plant (DEMO) are explored it is important to understand the design space for possible non-ITER like design options. The power exhaust is a key design driver for a fusion power plant, and puts strong constraints on the size of the machine. One candidate for a alternative design is a doubl…