Zobrazeno 1 - 10
of 658
pro vyhledávání: '"J. Noirot"'
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 2, Pp 259-267 (2018)
Focused ion beam–scanning electron microscope and electron backscattered diffraction examinations were conducted in the center of a 73 GWd/tU UO2 fuel. They showed the formation of subdomains within the initial grains. The local crystal orientation
Externí odkaz:
https://doaj.org/article/47a69d4a70b840cb904a9da621cfb05c
Autor:
Thierry Blay, Philippe Bienvenu, J. Noirot, Myriam Dumont, Rébecca Dowek, K. Hanifi, Isabelle Zacharie-Aubrun, Céline Cagna, Martiane Cabié, I. Roure
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 543, pp.152591. ⟨10.1016/j.jnucmat.2020.152591⟩
Journal of Nuclear Materials, 2021, 543, pp.152591. ⟨10.1016/j.jnucmat.2020.152591⟩
Journal of Nuclear Materials, Elsevier, 2021, 543, pp.152591. ⟨10.1016/j.jnucmat.2020.152591⟩
Journal of Nuclear Materials, 2021, 543, pp.152591. ⟨10.1016/j.jnucmat.2020.152591⟩
In oxide nuclear fuels, at high burn-up or during high temperature periods such as ramp tests, out-of- pile heating tests, or any irradiations at high linear heat rates, fission gases can form micrometric or quasi-micrometric bubbles. During nominal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f55174b4445d799e35ecf93e84a8fbbf
https://hal.archives-ouvertes.fr/hal-03385660/file/MSMP_JNUCMAT_2021_DUMONT.pdf
https://hal.archives-ouvertes.fr/hal-03385660/file/MSMP_JNUCMAT_2021_DUMONT.pdf
Autor:
Isabelle Zacharie-Aubrun, Th. Blay, L. Brunaud, Sylvain Meille, J. Noirot, Jean-Marie Gatt, R. Henry
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, 2021, 547, ⟨10.1016/j.jnucmat.2021.152821⟩
Journal of Nuclear Materials, 2021, 547, ⟨10.1016/j.jnucmat.2021.152821⟩
Vickers indentation was used to evaluate the hardness and the apparent fracture toughness of unirradiated and irradiated UO2 fuels, with the objective to determine the effects of the irradiation on mechanical properties. Indentation tests were realiz
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::53943c2be7b917b67706d9f8a8757096
https://hal.science/hal-03484852
https://hal.science/hal-03484852
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 2, Pp 259-267 (2018)
Nuclear Engineering and Technology
Nuclear Engineering and Technology, Elsevier, 2018, 50 (2), pp.259-267. ⟨10.1016/j.net.2017.12.002⟩
Nuclear Engineering and Technology, 2018, 50 (2), pp.259-267. ⟨10.1016/j.net.2017.12.002⟩
Nuclear Engineering and Technology
Nuclear Engineering and Technology, Elsevier, 2018, 50 (2), pp.259-267. ⟨10.1016/j.net.2017.12.002⟩
Nuclear Engineering and Technology, 2018, 50 (2), pp.259-267. ⟨10.1016/j.net.2017.12.002⟩
Focused ion beam–scanning electron microscope and electron backscattered diffraction examinations were conducted in the center of a 73 GWd/tU UO2 fuel. They showed the formation of subdomains within the initial grains. The local crystal orientation
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Publikováno v:
Journal of Nuclear Materials. 462:77-84
Within the Nuclear Fuel Industry Research (NFIR) programme, several fuel variants –in the form of thin circular discs – were irradiated in the Halden Boiling Water Reactor (HBWR) at burn-ups up to ∼100 GWd/tHM. The design of the fuel assembly w
Autor:
J. Noirot, J.-C. Richaud, Giannina Dottavio, Lionel Desgranges, Yves Pontillon, Renaud C. Belin, Christophe Valot
Publikováno v:
Progress in Nuclear Energy. 72:22-26
During the irradiation of oxide nuclear fuels used in pressurized water reactors, many microstructural modifications occur which affect the fuel performance. This work focuses on the thermodynamic evolution of the fuel under these conditions, with a
Publikováno v:
Journal of Nuclear Materials. 446:163-171
Within the Nuclear Fuel Industry Research (NFIR) program, several fuel variants, in the form of thin circular discs, were irradiated in the Halden Boiling Water Reactor (HBWR) to a range of burn-ups ∼100 GWd/t HM . The design of the assembly was si
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2016, 480, pp.32-39. ⟨10.1016/j.jnucmat.2016.07.056⟩
Journal of Nuclear Materials, 2016, 480, pp.32-39. ⟨10.1016/j.jnucmat.2016.07.056⟩
Journal of Nuclear Materials, Elsevier, 2016, 480, pp.32-39. ⟨10.1016/j.jnucmat.2016.07.056⟩
Journal of Nuclear Materials, 2016, 480, pp.32-39. ⟨10.1016/j.jnucmat.2016.07.056⟩
International audience; The present study describes the in-situ electrochemical modifications which affect irradiated PWR UO$_2$ fuels in the course of a power ramp, by means of in-situ oxido-reduction indicators such as chromium or neo-formed chemic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e1d0a18d68c8c82faf00543a732226fe
https://hal-cea.archives-ouvertes.fr/cea-02389290/document
https://hal-cea.archives-ouvertes.fr/cea-02389290/document
Publikováno v:
Journal of Nuclear Materials. 442:309-319
A UO2 fuel with a heterogeneous distribution of 235U was irradiated up to a high burn-up in the Halden Boiling Water Reactor (HBWR). The last 100 days of irradiation were performed with an increased level of linear power. The effect of the heterogene