J. Morris M. Y. Ye S. Mao
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
Preprint PublishedM. Kovari F. Fox C. Harrington R. Kembleton P. Knight H. Lux J. Morris
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. PROCESS allows the user to choose which constraints to impose and which to ignore, so when evaluating the results it is vital to study the list of constraints used. New …
Preprint PublishedA. Widdowson A. Baron-Wiechec P. Batistoni E. Belonohy J.P. Coad P. Dinca D. Flammini F. Fox K Heinola I. Jepu J. Likonen S. Lilley C.P. Lungu G.F. Matthews J. Naish O. Pompilian C. Porosnicu M. Rubel R. Villari JET Contributors
JET components are removed periodically for surface analysis to assess material migration and fuel retention. This paper describes issues related to handling JET components and procedures for preparing samples for analysis; in particular a newly developed procedure for cutting beryllium tiles is presented. Consideration is also given to the hazards…
Preprint PublishedS. S. Henderson L. Garzotti F. J. Casson D. Dickinson M. F. J. Fox M. O’Mullane A. Patel C. M. Roach H. P. Summers M. Valovic The Mast Team
Time-dependent helium gas puff experiments have been performed on the Mega Ampere Spherical Tokamak (MAST) during a two point plasma current scan in L-mode and a confinement scan at 900 kA. An evaluation of the He II spectrum line induced by charge exchange suggests anomalous rates of diffusion and inward convection in the outer regions of both L-m…
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