Zobrazeno 1 - 10
of 66
pro vyhledávání: '"H.D. Falter"'
Autor:
D. Martin, D. Ciric, H.D. Falter, D. Young, M.J. Watson, S.L. Svensson, D. Godden, A.J. Bickley, S.J. Cox, C. D. Challis, D. Stork, T.T.C. Jones, H.P.L. de Esch
Publikováno v:
Fusion Engineering and Design. 47:205-231
Neutral Beam Injection (NBI) is a very flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Deuterium–Tritium Experimental campaign (DTE1) undertaken in the
Autor:
G LeMarois, A Lind, L Plöchl, Mario Merola, L. Giancarli, D.M Jacobson, Y. Severi, R. Duwe, M. Rödig, H.D. Falter, C. Ibbott, A. Cardella, R. Jakeman, B. Riccardi, P. Chappuis, Eliseo Visca, H.D. Pacher, V.R. Barabash, A. Pizzuto, S.P.S Sangha, G. Vieider, A.T. Peacock, M Febvre
Publikováno v:
Fusion Engineering and Design. :211-218
This task within the EU R&D for ITER was aimed at the development of basic manufacturing solutions for the high heat flux plasma facing components such as the divertor targets, the baffles and limiters. More than 50 representative small-scale mock-up
Autor:
P. Chappuis, G. Federici, H.D. Falter, R. Jakeman, H. Heidl, Mario Merola, G. Vieider, D. Ciric, L Plöchl, R. Tivey, M. Rödig, S. Chiocchio, T. Ando, C. Ibbott
Publikováno v:
Fusion Engineering and Design. :409-417
Beryllium and tungsten are candidate plasma-facing armour materials for the International Thermonuclear Experimental Reactor (ITER). These armours are proposed for areas with low heat flux (⩽5 MW m −2 ); however, in the divertor, surface melting
Publikováno v:
Fusion Engineering and Design. 37:515-530
JET has accumulated practical experience of plasma operation in both limiter and divertor configurations using massive beryllium plasma-facing components. These latter have shown evidence, even after a very short operational phase, for localised melt
Autor:
R. Tivey, H.D. Falter, R. Mohanti, D. Ciric, E.B. Deksnis, H. Altmann, J. Fanthome, M.A. Pick, P. Massman, C.G. Lowry, A.T. Peacock
Publikováno v:
Journal of Nuclear Materials. :595-600
The new Mark II divertor of JET is a radical design based on JET experience in designing, installing and operating a variety of x-point energy target plates. It incorporates large inertially cooled carbon fibre reinforced carbon (CFC) tiles (ca. 400
Publikováno v:
Journal of Nuclear Materials. :1266-1271
The successful operation of JET in the presence of beryllium target plates has been limited by overheating of the plates. Active cooling of these components is investigated as a way of solving this problem. Tests carried out at JET suggest that water
Publikováno v:
Journal of Nuclear Materials. :1131-1134
The measurement of the growth and decay of the neutron yield from a water-cooled copper target during bombardment with intense (6 MW) beams of deuterium and deuterium-doped hydrogen beams is reported. Data obtained from the desorption of tritium from
Autor:
J Lupo, A.C. Bell, Amber Miller, Noel W. Davies, T. Winkel, F. Delvart, R. Haange, S J Booth, M. Wykes, D. Holland, A. Peacock, G. Newbert, R. Laesser, P. Chuilon, R. Stagg, A. Carmichael, Luigi Serio, G. Saibene, C Caldwell-Nichols, A.D. Haigh, H.D. Falter, B. Grieveson, Ben Green, R. Sartori, E. Thompson, S.L. Svensson, J.L. Hemmerich, F. Erhorn, P. Trevalion, Ttc Jones, M. Huguet, J. Orchard, J. How, E. Usselmann, M. Laveyry, R.M. Russ, K.J. Dietz, P. Milverton
Publikováno v:
Fusion Engineering and Design. 19:121-131
The JET experimental programme has been extended from its former formal closing date, end of 1992, to the end of 1996. The extension allows the study of plasma operation with a pumped divertor to be installed in the JET vacuum vessel during a shutdow
Publikováno v:
Journal of Nuclear Materials. :678-682
Significant amounts of hydrogen and helium are found to be implanted into the beam-stopping panels during beam operation. The amount implanted appears to exceed the particle flux of the beam in the early stages of the pulse. Gas is released during th
Publikováno v:
18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050).
Recent results on high heat flux testing of hypervapotron beam stopping elements are discussed. Two issues are being addressed: a) fatigue lifetime of components presently used at JET, and b) performance of the optimised hypervapotron element for the