K. Nordlund S. J. Zinkle A. E. Sand F. Granberg R. S. Averback R. Stoller T. Suzudo L. Malerba F. Banhart W. J. Weber F. Willaime S. L. Dudarev D. Simeone
Atomic collision processes are fundamental to numerous advanced materials technologies such as electron microscopy, semiconductor processing and nuclear power generation. Extensive experimental and computer simulation studies over the past several decades provide the physical basis for understanding the atomic-scale processes occurring during prima…
PublishedC. Challis R. Dumont D. Frigione L. Garzotti J. Graves E Lerche J. Mailloux M. Mantsinen F. Rimini F. Casson A. Czarneka R. Felton J. Garcia C. Giroud E. Joffrin H.-T. Kim M. Lennholm P. Lomas C. Lowry L. Meneses I Nunes et al.
The JET exploitation plan foresees D-T operations in 2019-2020. With respect to the first D-T campaign in 1998, when JET was equipped with a carbon wall, the experiments will be conducted in presence of a beryllium-tungsten ITER-like wall and will benefit from an extended and improved set of diagnostics and higher available additional heating power…
Preprint PublishedC. Giroud N. Aiba F. Militello C. Challis A. Chankin B. Lomanowski D. Hatch J. Harrison D. Frigione D. Moulton S. Pamela F. Parra J. Parisi I. Putzai D. Refy S. Saarelma C. Stavrou B. Tal E. Belonohy S. Brezinsek S. Buller C. Bowman E. Delabie A. Field J. Fontdecaba A. Huber A. Meigs S. Menmuir J. Simpson JET Contributors
Preprint Published
H. Lux M. Morgan M. Siccinio W. Biel G. Federici R. Kembleton A. W. Morris E. Patelli H. Zohm
During the pre-conceptual design phase of fusion devices such as the European demonstration fusion power plant (DEMO), systems codes provide a fast evaluation of optimal design points and highlight high impact areas. However, determining or evaluating a design point at such an early stage comes with uncertainties in many of the design parameters. T…
Preprint PublishedS. Dowson S. Dorling H. K. Sheikh T. Blackman G. Jones A. Goodyear P. Puglia P. Blanchard A. Fasoli D. Testa N. Fil V. Aslanyan M. Porkolab W. Pires De Sa R. Galvao L. Ruchko J. Figueiredo C. Perez Von Thun JET Contributors
The Alfvén Eigenmode Active Diagnostic system (AEAD) has undergone a major upgrade and redesign to provide a state of the art excitation and real-time detection system for JET. The new system consists of individual 4kW amplifiers for each of the six antennas, allowing for increased current, separate excitation and real time control of relative …
Preprint PublishedJ. 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 PublishedA. Shepherd R. Akers A. Barth I.E. Day G. Fishpool R. McAdams R. Tivey R. Verhoeven
Neutral beam injection is one of the primary auxiliary heating systems for tokamak plasmas. Once the neutral beam leaves the neutraliser collisions with background neutral particles in the beamline and tokamak vessel re-ionises part of the neutral beam. These particles can be deflected by the tokamak magnetic field, potentially damaging unshielded …
Preprint PublishedG.F.Matthews R.Nygren W. Morgan S. A. Silburn R. Otin A.Tallarigo the Magnum PSI Team
In 1998 Makhankov [1] described the concept of modular exchangeable plasma facing components (PFCs) based on liquid metal heat pipes which are radiatively cooled. Here we present results from recent experiments with a lithium filled tubular heat pipe owned by Sandia National Laboratories. The tantalum envelope (~20mm diameter by ~200mm long) was he…
Preprint PublishedJ.E. Menard R. Majeski M. Ono N.N. Bakharev V.K. Gusev M. Gryaznevich D. Kingham S. McNamara P. Thomas K. Hanada J. Harrison B. Lloyd Y.S. Hwang B. Lipschultz H. Wilson Y. Nagayama Y. Ono Y. Takase M. Reinke K. Tobita Z. Gao F. Alladio R.J. Fonck
The spherical torus/tokamak (ST) is a potentially attractive configuration for narrowing scientific and technical gaps to a fusion demonstration power plant and as a more compact and/or modular fusion power source. Due to a reduced plasma surface area to volume ratio, the ST configuration offers the potential to access high power exhaust heat fl…
PreprintD. Iglesias W. Arter I. Balboa P. Bunting C. Challis J.W. Coenen Y. Corre S. Esquembri S. Jachmich K. Krieger G.F. Matthews R.A. Pittsh V. Riccardo M.L. Richiusa M. Porton F. Rimini S. Silburn V.K. Thompson R. Otin D. Valcarcel L. Vitton-Mea Z. Vizvary J. Williams JET contributors
The JET outboard divertor targets are the in-vessel components which receive the largest heat flux density. Surface delamination, radial cracks, and tie rod failures have been observed in the outboard tungsten-coated CFC tiles, while bulk tungsten special lamellas were intentionally melted in dedicated experiments. These different types of damag…
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