Zobrazeno 1 - 10
of 828
pro vyhledávání: '"D. Terentyev"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1490-1500 (2024)
Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000°С at the maximum damage leve
Externí odkaz:
https://doaj.org/article/abf874ff2cba4a8da766d2bb2252ac93
Publikováno v:
Nuclear Materials and Energy, Vol 32, Iss , Pp 101211- (2022)
Mechanical performance of reduced activation ferritic/martensitic (RAFM) steels for fission and fusion applications at high temperature (i.e. above the current limit of 550 °C) requires further improvement. In this contribution, we present the work
Externí odkaz:
https://doaj.org/article/43271de7e85e4c8a842a1c8c2b9bfbfd
Publikováno v:
Scientific Reports, Vol 11, Iss 1, Pp 1-17 (2021)
Abstract The development of appropriate materials for fusion reactors that can sustain high neutron fluence at elevated temperatures remains a great challenge. Tungsten is one of the promising candidate materials for plasma-facing components of futur
Externí odkaz:
https://doaj.org/article/3ab1988c527a49ed95ca9fdd7048cab5
Autor:
R. Arredondo, M. Balden, T. Schwarz-Selinger, T. Höschen, T. Dürbeck, K. Hunger, K. Schlueter, A. Golubeva, P. Wang, D. Terentyev, W. Jacob
Publikováno v:
Nuclear Materials and Energy, Vol 30, Iss , Pp 101118- (2022)
In this work, the RAFM steels EUROFER, RUSFER and CLAM, along with a reference pure Fe sample, were all exposed to the same source of deuterium and analyzed using the same techniques, allowing a direct comparison of the experimental results. A 200 eV
Externí odkaz:
https://doaj.org/article/3d5ccc9f98b145f8bf821fadde012423
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 29, Iss , Pp 101070- (2021)
In this work, we investigate an alternative route for the production of reduced activation ferritic-martensitic (RAFM) steels with reduced contents of manganese and carbon. Alternation of the chemical composition coupled with various heat treatments
Externí odkaz:
https://doaj.org/article/48f561561a504eac853535d738e3b96a
Autor:
F. Balbaud, C. Cabet, S. Cornet, Y. Dai, J. Gan, M. Hernández Mayoral, R. Hernández, A. Jianu, L. Malerba, S.A. Maloy, J. Marrow, S. Ohtsuka, N. Okubo, M.A. Pouchon, A. Puype, E. Stergar, M. Serrano, D. Terentyev, Y.G. Wang, A. Weisenburger
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss , Pp 101006- (2021)
The Nuclear Energy Agency (NEA) Expert Group on Innovative Structural Materials (EGISM) was established in 2008 under the guidance of the Nuclear Science Committee (NSC). Its objectives are to conduct joint and comparative studies to support the deve
Externí odkaz:
https://doaj.org/article/ea2018ddafaf4b3ba8d4fa6dbafb3ada
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 48-54 (2018)
The retention of deuterium (D) and helium (He) is studied in pure tungsten after high flux mono-plasma exposure. The recrystallized and plastically deformed tungsten samples are studied to clarify the impact of the material microstructure, in particu
Externí odkaz:
https://doaj.org/article/f3e0e85cdba44c98847416d328447298
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