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High heat flux components—Readiness to proceed from near term fusion systems to power plants |
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| Authors: | A.R. Raffray R. Nygren S. Abdel-Khalik R. Doerner F. Escourbiac T. Evans R.J. Goldston D.T. Hoelzer S. Konishi P. Lorenzetto M. Merola R. Neu P. Norajitra R.A. Pitts M. Rieth M. Roedig T. Rognlien S. Suzuki M.S. Tillack C. Wong |
| Affiliation: | a CER, EBU-II, Room 460, University of California, San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0417, USA b Sandia National Laboratories, P.O. Box 5800, MS-1129, Albuquerque, NM 87185, USA c Plasma Science and Fusion Center, MIT, 77 Massachusetts Ave., NW17-105, Cambridge, MA 02139-4307, USA d Mechanical Engineering 0405, Georgia Institute of Technology, Atlanta, GA 30332, USA e CEA, IRFM, F-13108 St Paul Lez Durance, France f General Atomics, P.O. Box 85608, 3550, San Diego, CA 92186, USA g Princeton Plasma Physics Laboratory, MS-41, Princeton, NJ 08543, USA h Oak Ridge National Laboratory, P.O. Box 2008, MS-6136, Oak Ridge, TN 37831, USA i Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011, Japan j Fusion For Energy, C/Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona, Spain k ITER Organization, Cadarache Centre, Bat 524, F-13108 Saint Paul lez Durance, France l Max-Planck Institut für Plasmaphysik, Euratom Association, 85748 Garching, Germany m Forschungszentrum Karlsruhe, Institute for Materials Research III, P.O. Box 3640, D-76021 Karlsruhe, Germany n Forschungszentrum Karlsruhe, Institute for Materials Research I, P.O. Box 3640, D-76021, Karlsruhe, Germany o Forschungszentrum Jülich, D-52425 Jülich, Germany p Lawrence Livermore National Laboratory, Livermore, CA, USA q Fusion Research and Development Directorate, Japan Atomic Energy Agency, Naka-shi, Ibaraki-ken, 311-0193 Japan |
| Abstract: | A present topic of high interest in magnetic fusion is the “gap” between near-term and long-term concepts for high heat flux components (HHFC), and in particular for divertors. This paper focuses on this issue with the aim of characterizing the international status of current HHFC design concepts for ITER and describing the different technologies needed in the designs being developed for fusion power plants. Critical material and physics aspects are highlighted while evaluating the current readiness level of long-term concepts, identifying the design and R&D gaps, and discussing ways to bridge them. |
| Keywords: | Plasma-facing components Divertor ITER DEMO Fusion power plants |
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