Recent progress of R&D activities on reduced activation ferritic/martensitic steels
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Qunying Huang | Baldev Raj | G. R. Odette | Roger E. Stoller | Nadine Baluc | Yican Wu | Hiroyasu Tanigawa | Farong Wan | Richard J. Kurtz | S. Jitsukawa | Yican Wu | B. Raj | T. Muroga | S. Jitsukawa | N. Baluc | R. Stoller | G. Odette | Qunying Huang | L. Tan | A. Kimura | Takuya Yamamoto | R. Lindau | H. Tanigawa | R. Kurtz | F. Wan | A. Tavassoli | T. Muroga | Lizhen Tan | A. Kimura | Takuya Yamamoto | Yong Dai | Y. Dai | A.-A.F. Tavassoli | R. Lindau | J. Konys | J. Konys
[1] M. Enomoto,et al. Precipitation behavior in F82H during heat treatments of blanket fabrication , 2011 .
[2] Jianxun Zhang,et al. Welding techniques development of CLAM steel for Test Blanket Module , 2009 .
[3] Qunying Huang,et al. Status and strategy of fusion materials development in China , 2009 .
[4] G. G. Stokes. "J." , 1890, The New Yale Book of Quotations.
[5] Li Guo-ping,et al. Tritium permeation barrier-aluminized coating prepared by Al-plating and subsequent oxidation process , 2011 .
[6] W. Krauss,et al. Comparison of corrosion behavior of bare and hot-dip coated EUROFER steel in flowing Pb-17Li , 2007 .
[7] T. Muroga,et al. Microstructure control and deuterium permeability of erbium oxide coating on ferritic/martensitic steels by metal-organic decomposition , 2010 .
[8] Takayuki Terai,et al. JUPITER-II molten salt flibe research : An update on tritium, mobilization and redox chemistry experiments , 2005 .
[9] E. Lucon,et al. Overview of the tensile properties of EUROFER in the unirradiated and irradiated conditions , 2009 .
[10] T. Muroga,et al. Examination of electrical insulating performance of Er2O3 ceramic coating under ion beam irradiation , 2008 .
[11] Kazuyuki Nakamura,et al. Tensile and impact properties of F82H steel applied to HIP-bond fusion blanket structures , 2003 .
[12] J. Chen,et al. Effect of implanted deuterium on tensile properties of helium-doped RAFM EUROFER97 , 2011 .
[13] T. Muroga,et al. Deuterium permeation behavior of erbium oxide coating on austenitic, ferritic, and ferritic/martensitic steels , 2009 .
[14] Z. Y. Xu,et al. Influence of smelting processes on precipitation behaviors and mechanical properties of low activation ferrite steels , 2010 .
[15] Qunying Huang,et al. Preliminary analysis of irradiation effects on CLAM after low dose neutron irradiation , 2009 .
[16] Mikhail A. Sokolov,et al. Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications , 2009 .
[17] Yong Dai,et al. Helium-induced hardening effect in ferritic/martensitic steels F82H and Optimax-A irradiated in a mixed spectrum of high energy protons and spallation neutrons , 2011 .
[18] R. Knitter,et al. Status of development of functional materials with perspective on beyond-ITER , 2008 .
[19] E. Gaganidze,et al. High dose, up to 80 dpa, mechanical properties of Eurofer 97 , 2009 .
[20] Takanori Hirose,et al. Long-term properties of reduced activation ferritic/martensitic steels for fusion reactor blanket system , 2011 .
[21] A. Nishimura,et al. Effect of Specimen Shape on the Low Cycle Fatigue Life of Reduced Activation Ferritic/Martensitic Steel , 2010 .
[22] M. Rieth,et al. Review of candidate welding processes of RAFM steels for ITER test blanket modules and DEMO , 2011 .
[23] J. Hegeman,et al. Low cycle fatigue of irradiated and unirradiated Eurofer97 steel at 300 °C , 2011 .
[24] Y. Hu,et al. Study of an iron-aluminide and alumina tritium barrier coating , 2011 .
[25] A. Alamo,et al. Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325 °C up to 78 dpa , 2011 .
[26] Michael Rieth,et al. Specific welds for test blanket modules , 2009 .
[27] W. Krauss,et al. Flow rate dependent corrosion behavior of Eurofer steel in Pb–15.7Li , 2011 .
[28] A. Möslang,et al. Effect of 16.3 dpa neutron irradiation on fatigue lifetime of the RAFM steel EUROFER97 , 2011 .
[29] R. Rolli,et al. Effect of helium on tensile properties and microstructure in 9%Cr–WVTa–steel after neutron irradiation up to 15 dpa between 250 and 450 °C , 2009 .
[30] Takashi Nozawa,et al. Fusion materials development program in the broader approach activities , 2009 .
[31] Ralph W. Moir,et al. Molten salts in fusion nuclear technology , 1998 .
[32] N. Holstein,et al. Development of advanced Al coating processes for future application as anti-corrosion and T-permeation barriers , 2010 .
[34] A. Hasegawa,et al. Effect of specimen shape on micro-crack growth behavior under fatigue in reduced activation ferritic/martensitic steel , 2011 .
[35] A. Ciampichetti,et al. An overview on tritium permeation barrier development for WCLL blanket concept , 2004 .
[36] C. Petersen,et al. Tensile and low cycle fatigue properties of different ferritic/martensitic steels after the fast reactor irradiation ‘ARBOR 1’ , 2009 .
[37] Steven J. Zinkle,et al. Overview of materials research for fusion reactors , 2002 .
[38] Shengbin Gao,et al. Corrosion analysis of CLAM steel in flowing liquid LiPb at 480 °C , 2010 .
[39] Mikhail A. Sokolov,et al. Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket , 2011 .
[40] Rene Moreau,et al. Eurofer corrosion by the flow of the eutectic alloy Pb–Li in the presence of a strong magnetic field , 2011 .
[41] T. Muroga,et al. Hydrogen permeation through steel coated with erbium oxide by sol-gel method , 2009 .
[42] A. Hasegawa,et al. Fatigue Life Assessment Based on Crack Growth Behavior in Reduced Activation Ferritic/Martensitic Steel , 2010 .
[43] Mohamed A. Abdou,et al. Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials , 2007 .
[44] Shaojun Liu,et al. Effects of tube rolling and heat treatment on microstructure and mechanical properties of CLAM rectangular tube , 2011 .
[45] E. Materna-Morris,et al. Determining irradiation damage and recovery by instrumented indentation in RAFM steel , 2011 .
[46] A. Sagara,et al. Flow accelerated corrosion and erosion–corrosion of RAFM steel in liquid breeders , 2011 .
[47] Jarir Aktaa,et al. Study of helium embrittlement in boron doped EUROFER97 steels , 2009 .
[48] A. Möslang,et al. Characterization of radiation induced defects in EUROFER 97 after neutron irradiation , 2011 .
[49] T. Kunugi,et al. Electrical insulation test of alumina coating fabricated by sol-gel method in molten PbLi pool , 2010 .
[50] Mikio Enoeda,et al. Effects of Tube Drawing on Structural Material for ITER Test Blanket Module , 2007 .
[51] Yican Wu,et al. Status of R&D activities on materials for fusion power reactors , 2007 .
[52] Qunying Huang,et al. Latest progress on R&D of ITER DFLL-TBM in China , 2011 .
[53] J. Aktaa,et al. Mechanical properties and TEM examination of RAFM steels irradiated up to 70 dpa in BOR-60 , 2011 .