Characterization of Irradiation Damage of Ferritic ODS Alloys with Advanced Micro-Sample Methods
Tóm tắt
Từ khóa
Tài liệu tham khảo
Wirth BD, Odette GR, Stoller RE (2001) Recent progress toward an integrated multiscale-multiphysics model of reactor pressure vessel embrittlement. Mat Res Soc Symp Proc 677:AA5.2.1–AA5.2.6
Samaras M, Hoffelner W, Fu CC, Guttmann M, Stoller RE (2007) Materials modeling—a key for the design of advanced high temperature reactor components. Rev Gén Nucl 5:50–57
Korb G, Sporer D (1990) Recrystallization behaviour of pm 2000 oxide dispersoid strengthened iron-base superalloy. In: Bachelet R, Brunetaud R, Coutsouradis D, Esslinger P, Ewald J, Kvernes I, Lindblom Y, Meadowcroft DB, Regis V, Scarlin R, Schneider K, Singer R (eds) High temperature materials for power engineering. Kluwer, pp 1417–1430
Kimura A (2005) Current status of reduced-activation ferritic/martensitic steels R&D for fusion energy. Mater Trans 463:394–404 doi: 10.2320/matertrans.46.394
Pouchon MA, Chen J, Dobeli M, Hoffelner W (2006) Oxide dispersion strengthened steel irradiation with helium ions. J Nucl Mater 3521–3:57–61 doi: 10.1016/j.jnucmat.2006.02.070
Jung P, Schwarz A, Sahu H (1985) An apparatus for applying tensile, compressive and cyclic stresses on foil specimens during light ion irradiation. Nucl Instrum Methods Phys Res 2342:331–334 doi: 10.1016/0168-9002(85)90925-8
Chen J, Jung P, Pouchon M, Rebac T, Hoffelner W (2008) Irradiation creep and precipitation in a ferritic ods steel under helium implantation. J Nucl Mater 373 1–3:22–27 doi: 10.1016/j.jnucmat.2007.04.051
Lee J, Jang C, Kim I, Kimura A (2007) Embrittlement and hardening during thermal aging of high Cr oxide dispersion strengthened alloys. J Nucl Mat 367–370Part 1:229–233 doi: 10.1016/j.jnucmat.2007.03.007
Li X, Bhushan B (2002) A review of nanoindentation continuous stiffness measurement technique and its applications. Mater Charact 481:11–36
Pouchon MA, Döbeli M, Schelldorfer R, Chen J, Hoffelner W, Degueldre C (2005) ODS steel as structural material for high temperature nuclear reactors. In: Physics of Radiation Effect and Radiation Materials Science, Vol. 86 of Problems of atomistic science and technology, Kharkov Institute of Physics and Technology, pp 122–127
Uchic MD, Dimiduk DM, Florando JN, Nix WD (2004) Sample dimensions influence strength and crystal plasticity. Science 13, 305(5686):986–989
Volkert CA, Lilleodden ET (2006) Size effects in the deformation of sub-micron Au columns. Philos Mag 86:5567–5579 doi: 10.1080/14786430600567739
Hoffelner W, Chen J (2006) Thermal and Irradiation creep of advanced high temperature materials. Proceedings HTR2006: 3rd International Topical Meeting on High Temperature Reactor Technology October 1–4, 2006, Johannesburg, South Africa, Paper E 00000038see also: http://htr2006.co.za/downloads/final_download_papers/E00000038.pdf?PHPSESSID=38832e3d46b6d1e343651755c0025951
Chen J, Pouchon MA, Kimura A, Jung P, Hoffelner W (2009) Irradiation creep and microstructural change in an ods ferritic steel with very fine oxide particles after helium implantation under stress. J Nucl Mater in press
U.S. DOE Nuclear Energy Research Advisory Committee.Generation IV International Forum, A technology roadmap for generation iv nuclear energy systems, Tech. Rep. GIF-002-00 03-GA50034 (Dec. 2002). http://www.gen-4.org/PDFs/GenIVRoadmap.pdf