Zobrazeno 1 - 10
of 229
pro vyhledávání: '"J. Aktaa"'
Publikováno v:
Nuclear Materials and Energy, Vol 36, Iss , Pp 101497- (2023)
In the helium-cooled pebble bed blanket concept of DEMO, the reduced activation ferritic-martensitic steel EUROFER97 will be in direct contact with lithium ceramic pebbles and undergo cyclic thermomechanical loading during operation. This study compa
Externí odkaz:
https://doaj.org/article/a2ee9afafc664205b860935965941439
Autor:
L. Malerba, M.J. Caturla, E. Gaganidze, C. Kaden, M.J. Konstantinović, P. Olsson, C. Robertson, D. Rodney, A.M. Ruiz-Moreno, M. Serrano, J. Aktaa, N. Anento, S. Austin, A. Bakaev, J.P. Balbuena, F. Bergner, F. Boioli, M. Boleininger, G. Bonny, N. Castin, J.B.J. Chapman, P. Chekhonin, M. Clozel, B. Devincre, L. Dupuy, G. Diego, S.L. Dudarev, C.-C. Fu, R. Gatti, L. Gélébart, B. Gómez-Ferrer, D. Gonçalves, C. Guerrero, P.M. Gueye, P. Hähner, S.P. Hannula, Q. Hayat, M. Hernández-Mayoral, J. Jagielski, N. Jennett, F. Jiménez, G. Kapoor, A. Kraych, T. Khvan, L. Kurpaska, A. Kuronen, N. Kvashin, O. Libera, P.-W. Ma, T. Manninen, M.-C. Marinica, S. Merino, E. Meslin, F. Mompiou, F. Mota, H. Namburi, C.J. Ortiz, C. Pareige, M. Prester, R.R. Rajakrishnan, M. Sauzay, A. Serra, I. Simonovski, F. Soisson, P. Spätig, D. Tanguy, D. Terentyev, M. Trebala, M. Trochet, A. Ulbricht, M.Vallet, K. Vogel, T. Yalcinkaya, J. Zhao
Publikováno v:
Nuclear Materials and Energy, Vol 29, Iss , Pp 101051- (2021)
The M4F project brings together the fusion and fission materials communities working on the prediction of radiation damage production and evolution and their effects on the mechanical behaviour of irradiated ferritic/martensitic (F/M) steels. It is a
Externí odkaz:
https://doaj.org/article/16ebc0e4b8e34d40b03e788f4d806a2c
Publikováno v:
Nuclear Materials and Energy, Vol 21, Iss , Pp - (2019)
Polycrystalline tungsten is a promising candidate for future fusion applications as plasma facing material due to its good thermophysical properties at high temperatures. Fracture mechanical properties of sintered and rolled, commercially available p
Externí odkaz:
https://doaj.org/article/d3525a8995fb41eda25c3401904c416c
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 85-91 (2018)
For the design of future fusion reactors the ferritic-martensitic steel Eurofer97 is the main candidate for in-vessel structural application to be able to withstand harsh environment like irradiation and cyclic loading under elevated temperatures. In
Externí odkaz:
https://doaj.org/article/a38ec2adbb90454e86c8e63f9752fbf5
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 148-153 (2018)
Fusion like conditions for reduced activation ferritic/martensitic steels in the first wall are simulated with single Fe3+ and He+/Fe3+ dual ion beam irradiation of EUROFER97 at the Jannus laboratory, CEA Saclay, introducing a damage of 16 dpa and a
Externí odkaz:
https://doaj.org/article/8e3604092de342bc886d9c3ad6e31f0f
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 23-26 (2018)
The understanding of microstructural defects behavior after neutron irradiation is crucial for assessing the applicability of reduced activation ferritic/martensitic (RAFM) steel EUROFER 97 in future fusion reactors. Formation and evolution of disloc
Externí odkaz:
https://doaj.org/article/1b80e08a57304f2f9396c1b8ede68e52
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 535-538 (2016)
The damage caused by creep-fatigue is an important factor for materials at high temperatures. For in-vessel components of fusion reactors the material EUROFER97 is a candidate for structural application where it is subjected to irradiation and cyclic
Externí odkaz:
https://doaj.org/article/465724927e524f0799a855ef403d0892
Autor:
R. Coppola, E. Gaganidze, M. Klimenkov, C. Dethloff, R. Lindau, M. Valli, J. Aktaa, A. Möslang
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 189-193 (2016)
This contribution presents a comparative microstructural investigation, carried out by Small-Angle Neutron Scattering (SANS), of ferritic/martensitic steel Eurofer97 (0.12 C, 9 Cr, 0.2V, 1.08Wwt%) neutron irradiated at two different neutron sources,
Externí odkaz:
https://doaj.org/article/a4d481532d8942769e6a537b28bb37bc
Akademický článek
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Publikováno v:
Fusion Engineering and Design. 186:113351
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dd2ab0dbdfc5df9c7f026a316fa1e4b0
https://doi.org/10.1016/j.fusengdes.2022.113351
https://doi.org/10.1016/j.fusengdes.2022.113351