Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Thierry Alpettaz"'
Autor:
Alan BRUNEL, Andrea Quaini, Thierry ALPETTAZ, Christophe BONNET, Raphaëlle Guillou, Laurent CORMIER
Publikováno v:
SSRN Electronic Journal.
Autor:
Christine Guéneau, Emmanuelle Brackx, Mathieu Garrigue, Matthieu Touzin, Thierry Alpettaz, Christophe Bonnet, Olivier Tougait, Andrea Quaini, Renaud Domenger
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, Journal of Nuclear Materials, 557, pp.153266. ⟨10.1016/j.jnucmat.2021.153266⟩
Journal of Nuclear Materials, 2021, Journal of Nuclear Materials, 557, pp.153266. ⟨10.1016/j.jnucmat.2021.153266⟩
Journal of Nuclear Materials, Elsevier, 2021, Journal of Nuclear Materials, 557, pp.153266. ⟨10.1016/j.jnucmat.2021.153266⟩
Journal of Nuclear Materials, 2021, Journal of Nuclear Materials, 557, pp.153266. ⟨10.1016/j.jnucmat.2021.153266⟩
International audience; For the understanding of severe accidents in sodium cooled fast reactors (SFR), it is necessary to understand two prototypic accident scenarios such as ULOF (Unprotected Loss of Flow Accident) and UTOP (Unprotected Transient O
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f7c4f4f3a1e8c29e57ec700a9a6c37e0
https://hal.univ-lille.fr/hal-03336510
https://hal.univ-lille.fr/hal-03336510
Autor:
Cédric Sauder, Fanny Balbaud-Célérier, E. Brackx, Stéphane Gossé, James Braun, Christine Guéneau, Thierry Alpettaz, Renaud Domenger
Publikováno v:
Journal of Nuclear Materials. 487:380-395
Silicon carbide-silicon carbide (SiC/SiC) composites are considered to replace the current zirconium-based cladding materials thanks to their good behavior under irradiation and their resistance under oxidative environments at high temperature. In th
Publikováno v:
Journal of Chemical Thermodynamics
Journal of Chemical Thermodynamics, 2017, 114, pp.144-150. ⟨10.1016/j.jct.2017.01.015⟩
Journal of Chemical Thermodynamics, Elsevier, 2017, 114, pp.144-150. ⟨10.1016/j.jct.2017.01.015⟩
Journal of Chemical Thermodynamics, 2017, 114, pp.144-150. ⟨10.1016/j.jct.2017.01.015⟩
Journal of Chemical Thermodynamics, Elsevier, 2017, 114, pp.144-150. ⟨10.1016/j.jct.2017.01.015⟩
The first activity measurements of nickel, copper, chromium and iron in industrial nickel-base alloys (Monel®400, Monel®K-500, Nicorros®400, Nicorros®K-500, Hastelloy-X®, Hastelloy-C2000®, model alloy 1181) and steels (Uranus®65 and Uranus®45
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cf45e9b66db10ba91005368262321090
https://hal.science/hal-01784981
https://hal.science/hal-01784981
Publikováno v:
The Journal of Chemical Thermodynamics. 43:458-466
Temperatures of solid/liquid transitions and vanadium thermodynamic activity data are measured in the U–V system to improve the thermodynamic description of the U–V and C–U–V systems. Binary alloys are synthesized from the pure metals in a hi
Autor:
Céline Cabet, Stéphane Gossé, Sylvie Chatain, Christine Guéneau, Fabien Rouillard, Thierry Alpettaz
Publikováno v:
Materials Science Forum. :975-985
Chromium rich, nickel based alloys Haynes 230 and Inconel 617 are candidate materials for the primary circuit and intermediate heat exchangers (IHX) of (Very)-High Temperature Reactors. The corrosion resistance of these alloys is strongly related to
Publikováno v:
Journal of Engineering for Gas Turbines and Power. 131
The alloys Haynes 230 and Inconel 617 are potential candidates for the intermediate heat exchangers (IHXs) of (very) high temperature reactors ((V)-HTRs). The behavior under corrosion of these alloys by the (V)-HTR coolant (impure helium) is an impor
Publikováno v:
Journal of Engineering for Gas Turbines and Power-Transactions of the Asme
Journal of Engineering for Gas Turbines and Power-Transactions of the Asme, 2009, 132, pp.1. ⟨10.1115/1.3098430⟩
Journal of Engineering for Gas Turbines and Power-Transactions of the Asme, 2009, 132, pp.1. ⟨10.1115/1.3098430⟩
For Very High Temperature Reactors (V-HTR), the study of the Uranium-Carbon-Oxygen system is of major importance to predict the high temperature behaviour of the TRISO fuel particle. Firstly, the high level operating temperature of the fuel materials
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::21bd4e87d8f594c812fe4a369fe031b8
https://hal.science/hal-00446061
https://hal.science/hal-00446061
Autor:
Thierry Alpettaz, Jean-Baptiste Sirven, Yacine M'Baye, Stéphane Gossé, Nadine Coulon, A. Pailloux
Publikováno v:
Journal of Analytical Atomic Spectrometry. 24:451
Yellow cake is a commonly used name for powdered uranium concentrate, produced with the uranium ore. It is the first step in the fabrication of nuclear fuel. As it contains fissile material its circulation needs to be controlled in order to avoid pro
Autor:
Jean-Baptiste Sirven, Agnès Pailloux, Yacine M'Baye, Nadine Coulon, Thierry Alpettaz, Stéphane Gossé
Publikováno v:
JAAS (Journal of Analytical Atomic Spectrometry); Apr2009, Vol. 24 Issue 4, p451-459, 9p