Materials RD for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group
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Steven J. Zinkle | David Ward | Mark R. Gilbert | Baldev Raj | E. Diegele | Michael Rieth | Pietro Agostini | Antonella Li Puma | Colin English | Christian Linsmeier | G. Marbach | Angel Ibarra | Derek Stork | Gianfranco Federici | Derek Buckthorpe | J.-L. Boutard | Sergei L. Dudarev | Sehila Gonzalez | Lee W. Packer | Min Quang Tran | B. Raj | S. Zinkle | M. Rieth | S. Dudarev | M. Gilbert | C. Linsmeier | Á. Ibarra | D. J. Ward | M. Tran | C. English | G. Federici | L. Packer | J. Boutard | E. Diegele | D. Stork | P. Agostini | D. Buckthorpe | S. Gonzalez | A. Puma | G. Marbach
[1] J. Thomason,et al. Application of accelerator based neutron sources in fusion materials research , 2013, 2013 IEEE 25th Symposium on Fusion Engineering (SOFE).
[2] G. Federici,et al. The application of systems engineering principles to the European DEMO design and R&D studies , 2013, 2013 IEEE 25th Symposium on Fusion Engineering (SOFE).
[3] T. Muroga,et al. Multimodal options for materials research to advance the basis for fusion energy in the ITER era , 2013 .
[4] Mikhail A. Sokolov,et al. Fracture toughness and Charpy impact properties of several RAFMS before and after irradiation in HFIR , 2007 .
[5] Janne Wallenius,et al. The EU programme for modelling radiation effects in fusion reactor materials: An overview of recent advances and future goals , 2009 .
[6] S. Dudarev,et al. Neutron-induced dpa, transmutations, gas production, and helium embrittlement of fusion materials , 2013, 1311.5079.
[7] Omesh K. Chopra,et al. A review of irradiation effects on LWR core internal materials - Neutron embrittlement , 2011 .
[8] S. Dudarev,et al. An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation , 2012 .
[9] Shuichi Takamura,et al. Chapter 4: Power and particle control , 2007 .
[10] K. Ikeda. Progress in the ITER Physics Basis , 2007 .
[11] Jet Efda Contributors,et al. The effect of a metal wall on confinement in JET and ASDEX Upgrade , 2013 .
[12] Steven J. Zinkle,et al. Prospects for accelerated development of high performance structural materials , 2011 .
[13] Huijun Li,et al. Recent progress in research on tungsten materials for nuclear fusion applications in Europe , 2013 .
[14] Pierre Cortes,et al. Progress in the Safety and Licensing of ITER , 2013 .
[15] Steven J. Zinkle,et al. Materials Challenges in Nuclear Energy , 2013 .
[16] Frederic Escourbiac,et al. ITER plasma-facing components , 2010 .
[17] R. Ruprecht,et al. He-cooled divertor development for DEMO , 2007 .
[18] Nariaki Okubo,et al. Irradiation effects on reduced activation ferritic/martensitic steels—tensile, impact, fatigue properties and modelling , 2009 .
[19] Mikhail A. Sokolov,et al. Microstructure control for high strength 9Cr ferritic–martensitic steels , 2012 .
[20] P B Parks,et al. Reduction of edge-localized mode intensity using high-repetition-rate pellet injection in tokamak H-mode plasmas. , 2013, Physical review letters.
[21] Andreas Bürger,et al. Evolution of tungsten degradation under combined high cycle edge-localized mode and steady-state heat loads , 2011 .
[22] J.-H. You,et al. In situ synchrotron tomography estimation of toughening effect by semi-ductile fibre reinforcement in a tungsten-fibre-reinforced tungsten composite system , 2013 .
[23] S. Zinkle,et al. Evaluation of irradiation facility options for fusion materials research and development , 2013 .
[24] David E.J. Armstrong,et al. Tungsten foil laminate for structural divertor applications – Analyses and characterisation of tungsten foil , 2012 .
[25] Jean Paul Allain,et al. Plasma–surface interaction issues of an all-metal ITER , 2009 .
[26] J. Moteff,et al. Swelling in neutron irradiated molybdenum based on dimensional changes , 1976 .
[27] J. Aktaa,et al. Mechanical properties and TEM examination of RAFM steels irradiated up to 70 dpa in BOR-60 , 2011 .
[28] Michael Rieth,et al. Modelling structural and plasma facing materials for fusion power plants: Recent advances and outstanding issues in the EURATOM fusion materials programme , 2011 .
[29] P. Barabaschi,et al. Technical analysis of an early fusion neutron source based on the enhancement of the IFMIF/EVEDA accelerator prototype , 2014 .
[30] Takanori Hirose,et al. Development of the Toughness-Improved Reduced-Activation F82H Steel for DEMO Reactor , 2012 .
[31] J.-H. You,et al. Enhanced toughness and stable crack propagation in a novel tungsten fibre-reinforced tungsten composite produced by chemical vapour infiltration , 2014 .
[32] Yves Poitevin,et al. Survey of in-vessel candidate materials for fusion power plants—the European materials R&D programme , 2003 .
[33] D. Hoelzer,et al. Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT , 2009 .
[34] H.-C. Schneider,et al. Embrittlement behavior of neutron irradiated RAFM steels , 2007 .
[35] P. Sardain,et al. Power plant conceptual studies in Europe , 2007 .
[36] Jarir Aktaa,et al. Assessment of neutron irradiation effects on RAFM steels , 2013 .
[37] Ying Yang,et al. Effects of Alloying Elements and Thermomechanical Treatment on 9Cr Reduced Activation Ferritic-Martensitic (RAFM) Steels , 2013 .
[38] P. F. Morris,et al. Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment , 2014, 1408.3546.
[39] Z. Vizvary,et al. Balance of plant challenges for a near-term EU demonstration power plant , 2013, 2013 IEEE 25th Symposium on Fusion Engineering (SOFE).
[40] R. Doerner,et al. Formation of helium induced nanostructure ‘fuzz’ on various tungsten grades , 2010 .
[41] J. Schweinzer,et al. Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO , 2013 .
[42] Angel Ibarra,et al. IFMIF specifications from the users point of view , 2011 .