Zobrazeno 1 - 10
of 36
pro vyhledávání: '"G. R. Longhurst"'
Autor:
Masahiro Ishihara, Kunihiko Tsuchiya, Edgar E. Vidal, G. R. Longhurst, S. L. Folkman, H. Kawamura, M. Uchida, C. Dorn, T. N. Tranter, R. Rohe, T. H. Fronk
Publikováno v:
Nuclear Technology. 176:430-441
Beryllium plays important roles in nuclear facilities. Its neutron multiplication capability and low atomic weight make it very useful as a reflector in fission reactors. Its low atomic number and high chemical affinity for oxygen have led to its con
Autor:
David A. Petti, Mark S. Tillack, Farrokh Najmabadi, S. Malang, P. West, Brad J. Merrill, A. Abdou, V.C. Chan, Ronald L. Miller, T. K. Mau, Paul P. H. Wilson, G.M. Syaebler, A.R. Raffray, Thomas Brown, M.C. Chu, Don Steiner, E. A. Mogahed, L. L. Lao, F. Dahlgren, X. R. Wang, I.N. Sviatoslavsky, Douglass L. Henderson, C.E. Kessel, Leslie Bromberg, P. A. Politzer, T.W. Petrie, Laila El-Guebaly, G. R. Longhurst, H.E. St. John, P.J. Heitzenroeder, Lester M. Waganer, P. Synder, A. D. Turnbull, R. L. Moore
Publikováno v:
Fusion Engineering and Design. 80:3-23
The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areas with the highest leverage for achieving attractive
Publikováno v:
Fusion Science and Technology. 41:568-572
The Safety and Tritium Applied Research (STAR) Facility has been established at the Idaho National Engineering and Environmental Laboratory (INEEL) and is designated as a National User Facility. ST...
Autor:
Robert A. Anderl, R.P. Doerner, Rion A. Causey, William R. Wampler, A.A. Haasz, K.L. Wilson, G. R. Longhurst, J.W. Davis, G. Federici
Publikováno v:
Journal of Nuclear Materials. 273:1-26
Beryllium has been used as a plasma-facing material to effect substantial improvements in plasma performance in the Joint European Torus (JET), and it is planned as a plasma-facing material for the first wall (FW) and other components of the Internat
Autor:
Jeffrey N. Brooks, Wolfgang Jacob, C. H. Skinner, R. A. Anderl, J. P. Coad, R. A. Causey, J. Roth, G. Janeschitz, G. Federici, R. P. Doerner, A.A. Haasz, A. Peacock, W R Wampler, D. Cowgill, P.L. Andrew, G. R. Longhurst, V. Philipps, M Pick, R. Nygren
Publikováno v:
Journal of Nuclear Materials. :14-29
Tritium retention inside the vacuum vessel has emerged as a potentially serious constraint in the operation of the International Thermonuclear Experimental Reactor (ITER). In this paper we review recent tokamak and laboratory data on hydrogen, deuter
Publikováno v:
Journal of Nuclear Materials. :761-765
This paper presents the results of deuterium implantation/permeation experiments and TMAP4 simulations for a CuCrZr alloy, for OFHC-Cu and for a Cu/Be bi-layered structure at temperatures from 700 to 800 K. Experiments used a mass-analyzed, 3-keV D3+
Publikováno v:
Journal of Nuclear Materials. :601-606
The paper describes the main problems and the R&D for the beryllium to be used as neutron multiplier in blankets. As the four ITER partners propose to use beryllium in the form of pebbles for their DEMO relevant blankets (only the Russians consider t
Autor:
C.H. Wu, Rion A. Causey, Dennis L. Youchison, M Pick, C.H. Skinner, S. C. Luckhardt, William R. Wampler, C.P.C. Wong, Robert A. Anderl, A.A. Haasz, R.P. Doerner, K.L. Wilson, A. Peacock, D Mueller, J.P. Coad, G. R. Longhurst, Donald F. Cowgill, Jeffrey N. Brooks, G. Federici
Publikováno v:
Fusion Engineering and Design. :445-464
New data on hydrogen plasma isotopes retention in beryllium and tungsten are now becoming available from various laboratories for conditions similar to those expected in the International Thermonuclear Experimental Reactor (ITER) where previous data
Publikováno v:
Journal of Fusion Energy. 16:95-100
Deuterium implantation experiments have been conducted on samples of clean and carbon-coated beryllium. These studies entailed preparation and characterization of beryllium samples coated with carbon thicknesses of 100, 500, and 1000 A. Heat treatmen
Publikováno v:
Journal of Fusion Energy. 16:113-118
The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We