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A. Alamo
Researcher at French Alternative Energies and Atomic Energy Commission
Publications - 26
Citations - 1581
A. Alamo is an academic researcher from French Alternative Energies and Atomic Energy Commission. The author has contributed to research in topics: Small-angle neutron scattering & Hardening (metallurgy). The author has an hindex of 17, co-authored 26 publications receiving 1463 citations.
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Journal ArticleDOI
Present development status of EUROFER and ODS-EUROFER for application in blanket concepts
Rainer Lindau,Anton Möslang,Michael Rieth,M. Klimiankou,E. Materna-Morris,A. Alamo,A.-A.F. Tavassoli,Cyril Cayron,A.M Lancha,Pilar Fernández,Nadine Baluc,Robin Schäublin,E. Diegele,G. Filacchioni,J.W. Rensman,B.v.d. Schaaf,Enrico Lucon,W. Dietz +17 more
TL;DR: In this article, the authors present the results of the 23rd SOFT Conference, Venice, Italy (2004) Reference CRPP-CONF-2005-006 Record created on 2008-05-13, modified on 2017-05/12
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A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels
TL;DR: In this article, small angle neutron scattering (SANS) under magnetic field after neutron irradiation (0.7-2.9 dpa between 250 and 400 °C) was shown to contribute significantly to the irradiation-induced hardening of 9-12 wt% Cr content steels.
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Assessment of ODS-14%Cr ferritic alloy for high temperature applications
TL;DR: In this article, the mechanical properties of ODS-ferritic alloy, Fe-14Cr-1Ti-0.25Y2O3 (MA957), were evaluated with two microstructures characterized by different grain sizes and degree of crystallographic texture.
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Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications
Richard J. Kurtz,A. Alamo,Enrico Lucon,Qing Huang,S. Jitsukawa,Akihiko Kimura,Ronald L. Klueh,G.R. Odette,C. Petersen,Mikhail A. Sokolov,Philippe Spätig,J.W. Rensman +11 more
TL;DR: Significant progress has been achieved in the international research effort on reduced activation ferritic/martensitic steels for fusion structural applications as discussed by the authors, which is the leading structural material for test blankets in ITER and future fusion power systems.
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Mechanical properties of 9Cr martensitic steels and ODS-FeCr alloys after neutron irradiation at 325 °C up to 42 dpa
TL;DR: In this article, the tensile and impact properties of reduced activation ferritic/martensitic steels (F82H, JLF-1, 9Cr2WTaV and EUROFER-9Cr1WTAV) were investigated in different neutron irradiation experiments performed in the range 300-325°C.