Slip resistance of interfaces and the strength of metallic multilayer composites RG Hoagland, RJ Kurtz, CH Henager Jr Scripta materialia 50 (6), 775-779, 2004 | 374 | 2004 |
Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials S Wurster, N Baluc, M Battabyal, T Crosby, J Du, C García-Rosales, ... Journal of Nuclear Materials 442 (1-3), S181-S189, 2013 | 351 | 2013 |
Recent progress of R&D activities on reduced activation ferritic/martensitic steels Q Huang, N Baluc, Y Dai, S Jitsukawa, A Kimura, J Konys, RJ Kurtz, ... Journal of Nuclear Materials 442 (1-3), S2-S8, 2013 | 227 | 2013 |
Present status of vanadium alloys for fusion applications T Muroga, JM Chen, VM Chernov, RJ Kurtz, M Le Flem Journal of Nuclear Materials 455 (1-3), 263-268, 2014 | 205 | 2014 |
Status of R&D activities on materials for fusion power reactors N Baluc, K Abe, JL Boutard, VM Chernov, E Diegele, S Jitsukawa, ... Nuclear Fusion 47 (10), S696, 2007 | 195 | 2007 |
TEM characterization of dislocation loops in irradiated bcc Fe-based steels B Yao, DJ Edwards, RJ Kurtz Journal of Nuclear Materials 434 (1-3), 402-410, 2013 | 194 | 2013 |
Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket H Tanigawa, K Shiba, A Möslang, RE Stoller, R Lindau, MA Sokolov, ... Journal of Nuclear Materials 417 (1-3), 9-15, 2011 | 193 | 2011 |
Overview of the vanadium alloy researches for fusion reactors JM Chen, VM Chernov, RJ Kurtz, T Muroga Journal of Nuclear Materials 417 (1-3), 289-294, 2011 | 190 | 2011 |
Modeling of dislocation–grain boundary interactions in FCC metals M De Koning, RJ Kurtz, VV Bulatov, CH Henager, RG Hoagland, W Cai, ... Journal of Nuclear Materials 323 (2-3), 281-289, 2003 | 175 | 2003 |
Properties of helium defects in bcc and fcc metals investigated with density functional theory XT Zu, L Yang, F Gao, SM Peng, HL Heinisch, XG Long, RJ Kurtz Physical Review B—Condensed Matter and Materials Physics 80 (5), 054104, 2009 | 165 | 2009 |
Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications RJ Kurtz, A Alamo, E Lucon, Q Huang, S Jitsukawa, A Kimura, RL Klueh, ... Journal of Nuclear Materials 386, 411-417, 2009 | 146 | 2009 |
Displacement cascades and defects annealing in tungsten, Part I: Defect database from molecular dynamics simulations W Setyawan, G Nandipati, KJ Roche, HL Heinisch, BD Wirth, RJ Kurtz Journal of Nuclear Materials 462, 329-337, 2015 | 144 | 2015 |
An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design CPC Wong, S Malang, M Sawan, M Dagher, S Smolentsev, B Merrill, ... Fusion Engineering and Design 81 (1-7), 461-467, 2006 | 142 | 2006 |
Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions J Marian, CS Becquart, C Domain, SL Dudarev, MR Gilbert, RJ Kurtz, ... Nuclear Fusion 57 (9), 092008, 2017 | 141 | 2017 |
Critical issues and current status of vanadium alloys for fusion energy applications RJ Kurtz, K Abe, VM Chernov, VA Kazakov, GE Lucas, H Matsui, ... Journal of nuclear materials 283, 70-78, 2000 | 139 | 2000 |
The effects of grain boundary structure on binding of He in Fe RJ Kurtz, HL Heinisch Journal of nuclear materials 329, 1199-1203, 2004 | 128 | 2004 |
Recent progress on development of vanadium alloys for fusion RJ Kurtz, K Abe, VM Chernov, DT Hoelzer, H Matsui, T Muroga, ... Journal of nuclear materials 329, 47-55, 2004 | 123 | 2004 |
The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/dpa ratios and dpa rates T Yamamoto, GR Odette, P Miao, DT Hoelzer, J Bentley, N Hashimoto, ... Journal of Nuclear Materials 367, 399-410, 2007 | 121 | 2007 |
Effects of transition metals on the grain boundary cohesion in tungsten W Setyawan, RJ Kurtz Scripta Materialia 66 (8), 558-561, 2012 | 107 | 2012 |
A new Fe–He interatomic potential based on ab initio calculations in α-Fe F Gao, H Deng, HL Heinisch, RJ Kurtz Journal of nuclear materials 418 (1-3), 115-120, 2011 | 107 | 2011 |