Zobrazeno 1 - 10
of 188
pro vyhledávání: '"F. Bergner"'
Publikováno v:
Frontiers in Nuclear Engineering, Vol 2 (2023)
Post-irradiation annealing of neutron-irradiated reactor pressure vessel steels is a matter of both technical and scientific interest. Small-angle neutron scattering (SANS), while being sensitive to nm-sized irradiation-induced solute-atom clusters,
Externí odkaz:
https://doaj.org/article/e30c7001f971417193657c950b6acb33
Publikováno v:
Nuclear Materials and Energy, Vol 30, Iss , Pp 101105- (2022)
Hardening of Fe-9%Cr alloys exposed to irradiation with Fe2+ ions of two different energies, 1 and 5 MeV, is investigated using nanoindentation. The limited penetration depth of the ions causes steep damage gradients in the near-surface volumes of th
Externí odkaz:
https://doaj.org/article/96e36d70e01b43f5acd9af144035f6f1
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 27, Iss , Pp 101007- (2021)
It is generally accepted that the microstructure of ion-irradiated Fe-based alloys does not only depend on the local level of displacement damage and the initial microstructure. Other factors such as the vicinity of a surface and the injected ions al
Externí odkaz:
https://doaj.org/article/e23070c1f8fa445e9b063fee6b2d8ed5
Publikováno v:
Nuclear Materials and Energy, Vol 26, Iss , Pp 100918- (2021)
The small punch test is evaluated as a screening procedure for irradiation embrittlement of reactor pressure vessel steels. In particular, the correlation between ductile-to-brittle transition temperatures obtained from this small specimen test techn
Externí odkaz:
https://doaj.org/article/e0d7151f0b9d4fc28b454055cc5723b0
Publikováno v:
Nuclear Materials and Energy, Vol 24, Iss , Pp 100759- (2020)
Ion irradiations are indispensable for exploring radiation effects on materials, for example, radiation hardening. However, the extraction of radiation hardening as function of displacement damage from the nanoindentation (NI) response of self-ion-ir
Externí odkaz:
https://doaj.org/article/d9682e966a464cd095f587064046ab5c
Autor:
J Häusele, M Viermetz, N Gustschin, C Schmid, M von Teuffenbach, P Meyer, F Bergner, T Lasser, R Proksa, D Pfeiffer, T Koehler, F Pfeiffer
Publikováno v:
RöFo - Fortschritte auf dem Gebiet der Röntgenstrahlen und der bildgebenden Verfahren.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b5c9c0288a0eaceac6766c4d7499e717
https://doi.org/10.1055/s-0043-1763137
https://doi.org/10.1055/s-0043-1763137
Autor:
N. Castin, G. Bonny, M.J. Konstantinović, A. Bakaev, F. Bergner, C. Courilleau, C. Domain, B. Gómez-Ferrer, J.M. Hyde, L. Messina, G. Monnet, M.I. Pascuet, B. Radiguet, M. Serrano, L. Malerba
Publikováno v:
Materials Today Physics
Materials Today Physics, 2022, 27, pp.100802. ⟨10.1016/j.mtphys.2022.100802⟩
Materials Today Physics 27(2022), 100802
Materials Today Physics, 2022, 27, pp.100802. ⟨10.1016/j.mtphys.2022.100802⟩
Materials Today Physics 27(2022), 100802
Radiation-induced embrittlement of nuclear steels is one of the main limiting factors for safe long-term operation of nuclear power plants. In support of accurate and safe reactor pressure vessel (RPV) lifetime assessments, we developed a physics-bas
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8c67aef6ef20b5f656c22fa3c6c9a6c7
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