High heat flux components—Readiness to proceed from near term fusion systems to power plants
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Said I. Abdel-Khalik | Mark S. Tillack | A. R. Raffray | P. Lorenzetto | F. Escourbiac | Michael Rieth | Mario Merola | Robert J. Goldston | Dennis G. Whyte | Satoshi Konishi | R. Neu | R. A. Pitts | Clement Wong | S. Suzuki | Richard E. Nygren | P. Norajitra | T. E. Evans | David T. Hoelzer | R. Neu | T. Evans | S. Abdel-Khalik | T. Rognlien | M. Merola | M. Rieth | M. Tillack | F. Escourbiac | R. Nygren | S. Suzuki | R. Goldston | R. Pitts | D. Hoelzer | C. Wong | R. Doerner | A. Raffray | P. Norajitra | P. Lorenzetto | M. Roedig | T. D. Rognlien | R. P. Doerner | M. Roedig | S. Konishi | D. Whyte | Prachai Norajitra
[1] Michael Rieth,et al. Fracture Behaviour of Tungsten Based Alloys Depending on Microstructure and Notch Fabrication Method , 2009 .
[2] S. Malang,et al. Design Optimization of High-Performance Helium-Cooled Divertor Plate Concept , 2009 .
[3] A. R. Raffray,et al. DESIGN OPTIMIZATION OF HIGH-PERFORMANCE HELIUM-COOLED DIVERTOR PLATE CONCEPT , 2009 .
[4] R. Neu,et al. Dynamic and static deuterium inventory in ASDEX Upgrade with tungsten first wall , 2009 .
[5] Minami Yoda,et al. Thermal Performance of a Prototypical Gas-Cooled T-Tube Divertor Module with Single-Sided Heating , 2009 .
[6] C. Wong,et al. Innovative tokamak DEMO first wall and divertor material concepts , 2009 .
[7] K. Tokunaga,et al. The effects of high fluence mixed-species (deuterium, helium, beryllium) plasma interactions with tungsten , 2009 .
[8] R. Neu,et al. Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade , 2009 .
[9] Joachim Roth,et al. Recent analysis of key plasma wall interactions issues for ITER , 2009 .
[10] T. Loarer. Fuel retention in tokamaks , 2009 .
[11] J. Likonen,et al. Post-mortem measurements of fuel retention at JET , 2009 .
[12] M. Wade,et al. PLASMA IMPURITY CONTENT, GAS FUELING, AND EXHAUST ON DIII-D OVER EXTENDED PERIODS BETWEEN BORONIZATIONS , 2009 .
[13] Suk-Ho Hong,et al. Investigation of temporal evolution and spatial distribution of dust creation events in DITS campaign using visible CCD cameras in Tore Supra , 2009 .
[14] R. Neu,et al. Carbon balance and deuterium inventory from a carbon dominated to a full tungsten ASDEX Upgrade , 2009 .
[15] P. Hertout,et al. Overview of the deuterium inventory campaign in Tore Supra: Operational conditions and particle balance , 2009 .
[16] D. Hoelzer,et al. Mechanical properties of neutron irradiated nanostructured ferritic alloy 14YWT , 2009 .
[17] J. Stober,et al. Non-boronized compared with boronized operation of ASDEX Upgrade with full-tungsten plasma facing components , 2009 .
[18] W. Fundamenski,et al. Nonlinear impact of edge localized modes on carbon erosion in the divertor of the JET tokamak. , 2009, Physical review letters.
[19] P. Sardain,et al. Divertor conceptual designs for a fusion power plant , 2008 .
[20] M. Rieth,et al. Impact Bending Tests on Selected Refractory Materials , 2008 .
[21] R. Bell,et al. NSTX Experiments with Lithium Plasma-Facing Components -- Recent Results and Future Plans , 2008 .
[22] P. Cochat,et al. Et al , 2008, Archives de pediatrie : organe officiel de la Societe francaise de pediatrie.
[23] A. R. Raffray,et al. Engineering Design and Analysis of the ARIES-CS Power Plant , 2008 .
[24] J. S. deGrassie,et al. RMP ELM suppression in DIII-D plasmas with ITER similar shapes and collisionalities , 2008 .
[25] G. Odette,et al. The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/dpa ratios and dpa rates , 2007 .
[26] Mikhail A. Sokolov,et al. Influence of Particle Dispersions on the High-Temperature Strength of Ferritic Alloys , 2007 .
[27] B. Lipschultz,et al. Influence of boronization on operation with high-Z plasma facing components in Alcator C-Mod , 2007 .
[28] A. Hyatt,et al. Migration of Artificially Introduced Micron Size Carbon Dust in the DIII-D Divertor , 2007 .
[29] T. Jernigan,et al. Disruption mitigation on Alcator C-Mod using high-pressure gas injection: Experiments and modeling toward ITER , 2007 .
[30] Said I. Abdel-Khalik,et al. Design and performance study of the helium-cooled T-tube divertor concept , 2007 .
[31] D. P. Luigi,et al. DEMO and fusion power plant conceptual studies in Europe , 2006 .
[32] T. Ihli,et al. An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD , 2005 .
[33] M. Merola,et al. Activity of the European high heat flux test facility: FE200 , 2005 .
[34] B. Lipschultz. Operation of Alcator C-Mod with high-Z plasma facing components and implications , 2005 .
[35] John P. Shingledecker,et al. Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys , 2005 .
[36] R. Doerner,et al. High temperature erosion of beryllium , 2005 .
[37] B. Schweer,et al. Flux dependence of carbon chemical erosion by deuterium ions , 2004 .
[38] G. R. Odette,et al. The development and stability of Y–Ti–O nanoclusters in mechanically alloyed Fe–Cr based ferritic alloys , 2004 .
[39] M. Merola,et al. Post irradiation testing of samples from the irradiation experiments PARIDE 3 and PARIDE 4 , 2004 .
[40] Kazuya Miyahara,et al. Effect of Ti and W on the Mechanical Properties and Microstructure of 12% Cr Base Mechanical-alloyed Nano-sized ODS Ferritic Alloys , 2003 .
[41] M. Merola,et al. Overview on fabrication and joining of plasma facing and high heat flux materials for ITER , 2002 .
[42] S. Malang,et al. Gas-cooled high performance divertor for a power plant , 2002 .
[43] S. Zinkle,et al. Operating temperature windows for fusion reactor structural materials , 2000 .
[44] G. Federici,et al. RACLETTE: a model for evaluating the thermal response of plasma facing components to slow high power plasma transients. Part II: Analysis of ITER plasma facing components , 1997 .
[45] G. Federici,et al. RACLETTE: a Model for Evaluating the Thermal Response of Plasma Facing Components to Slow High Power Plasma Transients. Part I: Theory and Description of Model Capabilities , 1997 .
[46] G. Ambrosino,et al. Power and particle fluxes at the plasma edge of ITER: Specifications and Physics Basis , 2009 .
[47] M. Rieth,et al. Tungsten as structural material , 2008 .
[48] A. R. Raffray,et al. Issues and R & D needs for commercial fusion energy – An interim report of the ARIES technical working groups – August 2008 , 2008 .