Zobrazeno 1 - 10
of 348
pro vyhledávání: '"M. Clozel"'
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
Autor:
F. Di Fonzo, E.J. Olivier, I. Jóźwik, M. Clozel, Ryszard Diduszko, Alexander Azarov, M. Vanazzi, Łukasz Kurpaska, J.H. O'Connell, M. Frelek-Kozak, Johannes H. Neethling, Jacek Jagielski, A. Zaborowska
Publikováno v:
Ceramics International. 47:34740-34750
In this study structural and mechanical properties of a 1 μm thick Al2O3 coating, deposited on 316L stainless steel by Pulsed Laser Deposition (PLD), subjected to high energy ion irradiation were assessed. Mechanical properties of pristine and ion-m
Akademický článek
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Autor:
J. Zagorski, M. Clozel, A. Kosinska, K. Gniadek, L. Kurpaska, E. Wyszkowska, Jacek Jagielski, Dariusz M. Bieliński, B. Staszkiewicz
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 473:6-9
The main aim of this work is to get a deeper insight into the problem of insulation properties of materials exposed to radiative environment, namely to compare hardness and electrical resistivity in selected polymers which may be used as electric ins
Autor:
M. Sauzay, F. Jiménez, Igor Simonovski, Chu-Chun Fu, P.-W. Ma, Pär Olsson, H. Namburi, G. Bonny, M. Prester, O. Libera, Francesca Boioli, L. Gélébart, Fernando Mota, Philippe Spätig, M.J. Konstantinović, D. Tanguy, Ermile Gaganidze, Mihai-Cosmin Marinica, C. Pareige, N. Kvashin, Karin Vogel, C. Guerrero, Susana Merino, C. Kaden, E. Meslin, M. Hernández-Mayoral, Qamar Hayat, Max Boleininger, L. Kurpaska, Gonzalo de Diego, R.R. Rajakrishnan, M. Clozel, S. Austin, C. Robertson, N. Anento, Lorenzo Malerba, Frédéric Mompiou, Anna Serra, Jarir Aktaa, C.J. Ortiz, P.M. Gueye, Alexander Bakaev, A. Kraych, Jacob B. J. Chapman, Jacek Jagielski, J. Zhao, Benoit Devincre, Dorival Gonçalves, T. Manninen, Ana Ruiz-Moreno, M. Vallet, Michal Trebala, J.P. Balbuena, N. Castin, P. Chekhonin, Frank Bergner, Mickaël Trochet, David Rodney, B. Gómez-Ferrer, Peter Hähner, Nigel M. Jennett, Sergei L. Dudarev, F. Soisson, R. Gatti, M.J. Caturla, A. Ulbricht, G. Kapoor, Tuncay Yalçinkaya, D. Terentyev, Marta Serrano, A. Kuronen, Tymofii Khvan, Simo-Pekka Hannula, L. Dupuy
Publikováno v:
Nuclear Materials and Energy
Nuclear Materials and Energy, Elsevier, 2021, 29, pp.101051. ⟨10.1016/j.nme.2021.101051⟩
Nuclear Materials and Energy, 2021, 29, pp.101051. ⟨10.1016/j.nme.2021.101051⟩
Nuclear materials and energy, 29, Art.-Nr. 101051
Nuclear Materials and Energy, Vol 29, Iss, Pp 101051-(2021)
RUA. Repositorio Institucional de la Universidad de Alicante
Universidad de Alicante (UA)
Nuclear Materials and Energy 29(2021), 101051
UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)
Nuclear Materials and Energy, Elsevier, 2021, 29, pp.101051. ⟨10.1016/j.nme.2021.101051⟩
Nuclear Materials and Energy, 2021, 29, pp.101051. ⟨10.1016/j.nme.2021.101051⟩
Nuclear materials and energy, 29, Art.-Nr. 101051
Nuclear Materials and Energy, Vol 29, Iss, Pp 101051-(2021)
RUA. Repositorio Institucional de la Universidad de Alicante
Universidad de Alicante (UA)
Nuclear Materials and Energy 29(2021), 101051
UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)
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://explore.openaire.eu/search/publication?articleId=doi_dedup___::3a4b291e2cb760ed160988dd09171941
https://hdl.handle.net/2117/366747
https://hdl.handle.net/2117/366747
Autor:
A. Kosinska, E. Wyszkowska, Magdalena Romaniec, U. Ostaszewska, L. Kurpaska, M. Clozel, Jacek Jagielski
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 443:15-18
The paper presents recent studies focused on improving friction and wear properties of acrylonitrile-butadiene rubber (NBR). The main objective of the presented study is to investigate impact of wide range of ions, irradiated with different energies
Akademický článek
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Autor:
K. Mulewska, A. Ibrayeva, N.S. Kirilkin, Vladimir A. Skuratov, M. Clozel, E.A. Korneeva, A. Janse van Vuuren, M.V. Zdorovets, L. Kurpaska, Johannes H. Neethling
Publikováno v:
Journal of Nuclear Materials. 555:153120
We report the results of the nanoindentation tests of silicon nitride irradiated with Ar (46 MeV), Kr (107 MeV), Xe (167 MeV, 220 MeV) and Bi (710 MeV) ions. The behaviour of hardness with respect to ion fluence was analyzed and correlated with the m
Autor:
E. Wyszkowska, W. Chmurzynski, M. Duchna, L. Kurpaska, Iwona Jozwik, A. Kosinska, I. Cieslik, B. Zajac, M. Frelek-Kozak, M. Wilczopolska, W. Bonicki, G. Olszewski, R. Diduszko, M. Clozel, Jacek Jagielski, A. Zaborowska
Publikováno v:
Journal of Molecular Structure. 1217:128370
Graphite is known as a material with excellent thermo-mechanical, structural and neutron moderation properties. It is currently used as a core structural component for High Temperature Gas Cooled Reactor (HTGR). It is due to the fact that graphite ha
Publikováno v:
Surface and Coatings Technology
Ferritic-martensitic steels are among the prime candidates to make up structural parts of new generation reactors. Nanoindentation was conducted on 2 materials: low activation Fe-9Cr-1WVTa (Eurofer97) and a model pure iron. Both materials were implan