Zobrazeno 1 - 10 of 19 pro vyhledávání: '"Martine Blat"'
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Akademický článek
Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
Autor: Jorge Enrique MUÑOZ GARCIA, Cécile PÉTESCH, Thierry LEBARBÉ, Dominique BONNE, Claude PASCAL, Martine BLAT
Publikováno v: Mechanical Engineering Journal, Vol 7, Iss 4, Pp 20-00052-20-00052 (2020)
The very last edition of the RCC-MRx Code (Design and Construction Rules for Mechanical Components in high-temperature structures, experimental reactors and fusion reactors) was published end of 2018 by AFCEN, the French Association for the rules gov
Externí odkaz: https://doaj.org/article/6b63dd8c733e49df877cb58ca3236d39
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2
Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
Autor: T. Lebarbé, Cécile Pétesch, Martine Blat, D. Bonne, Jorge Enrique Muñoz Garcia, Claude Pascal
Publikováno v: Mechanical Engineering Journal, Vol 7, Iss 4, Pp 20-00052-20-00052 (2020)
Mechanical Engineering Journal
Mechanical Engineering Journal, 2020, 7 (4), pp.20-00052-20-00052. ⟨10.1299/mej.20-00052⟩
The very last edition of the RCC-MRx Code (Design and Construction Rules for Mechanical Components in high-temperature structures, experimental reactors and fusion reactors) was published end of 2018 by AFCEN, the French Association for the rules gov
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ca7e4c8955ba275c969a3110a09ffde7
https://www.jstage.jst.go.jp/article/mej/7/4/7_20-00052/_pdf/-char/en
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3
Matériaux de structures - Installations nucléaires innovantes
Autor: Martine Blat Yrieix, Cécile Petesch, Jérôme Garnier
Publikováno v: Génie nucléaire.
Le developpement de nouveaux concepts de reacteurs (dits de generation IV ou de fusion thermonucleaire controlee) est un enjeu majeur des prochaines decennies dans le domaine de l’energie. Ces nouveaux reacteurs amenent de nouveaux defis et le deve
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::01d5028950191e5a2a2d165f2dbf73a2
https://doi.org/10.51257/a-v1-bn3731
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4
Coating Toughness Estimation through a Laser Shock Testing in Ni-Cr-B-Si-C Coatings
Autor: Pierre Sallamand, Pascal Aubry, C. Cossange, Fabien Rouillard, M. Duband, Martine Blat-Yrieix, Cécile Blanc, Thorsten Marlaud, Gilles Rolland, A. Andrieu
Publikováno v: Materials Science Forum. 941:1886-1891
In the nuclear field, efforts are made to find substitutes to cobalt hardfacing alloys since these alloys have a principal drawback, the transmutation from stable 59Co to 60Co under neutron irradiation. In case of wear, fragments could be deposed on
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ae3cceb91571bbb6e0abdf27000d55b6
https://doi.org/10.4028/www.scientific.net/msf.941.1886
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5
Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour
Autor: Gilles Rolland, Cécile Blanc, Brigitte Duprey, Hicham Maskrot, Michel Tabarant, J. L. Courouau, Fabien Rouillard, Thorsten Marlaud, Martine Blat-Yrieix, Pascal Aubry, Laetitia Nicolas, Raphaël Robin
Publikováno v: EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2019, 5, pp.10. ⟨10.1051/epjn/2019025⟩
EPJ Nuclear Sciences & Technologies, Vol 5, p 10 (2019)
EPJ N-Nuclear Sciences & Technologies, 2019, 5, pp.10. ⟨10.1051/epjn/2019025⟩
The feedback produced by operating Sodium-cooled Fast Reactors (SFRs) has shown the importance of material tribological properties. Where galling or adhesive wear cannot be allowed, hardfacing alloys, known to be galling-resistant coatings, are usual
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2eb857ed6dc9bca87bf955dd8ccd0546
https://hal-cea.archives-ouvertes.fr/cea-02458447
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6
Precipitates and boundaries interaction in ferritic ODS steels
Autor: Bertrand Radiguet, Martine Blat-Yrieix, Philippe Pareige, Laurent Chaffron, Denis Sornin, N. Sallez, Yves Bréchet, Frederic Delabrouille, Patricia Donnadieu, Constantinos Hatzoglou
Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2016, 472, pp.118-126. ⟨10.1016/j.jnucmat.2016.01.021⟩
Journal of Nuclear Materials, 2016, 472, pp.118-126. ⟨10.1016/j.jnucmat.2016.01.021⟩
International audience; In the course of a recrystallization study of Oxide Dispersion Strengthened (ODS) ferritic steels during extrusion, particular interest was paid to the (GB) Grain Boundaries interaction with precipitates. Complementary and cor
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b1fd6a7428697dca8d1c009ae97b42fc
https://doi.org/10.1016/j.jnucmat.2016.01.021
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8
2018 rcc-mrx code edition context, overview, on-going developments
Autor: Cécile Pétesch, Martine Blat-Yrieix, Odile Gelineau, T. Lebarbé, Damien Vallot
Publikováno v: Pressure Vessel and Piping 2018
Pressure Vessel and Piping 2018, Jul 2018, Prague, Czech Republic
The 2018 edition of the RCC-MRx Code (1) will be issued, by the end of the 2018, in French and English versions by AFCEN (Association Française pour les règles de Conception et de Construction des Matériels des Chaudières Electro-nucléaires). Th
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::149e2a432254272f5d61fea2503dc631
https://hal.science/hal-02415499
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9
Understanding of Corrosion Mechanisms after Irradiation: Effect of Ion Irradiation of the Oxide Layers on the Corrosion Rate of M5
Autor: Sandrine Miro, G. Baldacchino, Isabel Idarraga, Martine Blat-Yrieix, Marc Tupin, Krzysztof Wolski, Damien Kaczorowski, Kimberly Colas, Romain Verlet, Philippe Bossis, Antoine Ambard, Michael Jublot
Publikováno v: Zirconium in the Nuclear Industry: 18th International Symposium
Zirconium in the Nuclear Industry: 18th International Symposium, 2018, West Conshohocken, United States. ⟨10.1520/STP159720160081⟩
International audience; Irradiation damage in fuel cladding material is mainly caused by the neutron flux that results from fission reactions occurring in the fuel. To avoid the constraints inherent in handling radioactive material, the irradiation e
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::08a73d64b3837013a09716d41b2be552
https://doi.org/10.1520/stp159720160081
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10
Oxygen segregation in pre-hydrided Zircaloy-4 cladding during a simulated LOCA transient
Autor: S. Guilbert, Antoine Ambard, Marie-Christine Baietto, Martine Blat, Jean Desquines, Elodie Torres, Michel Coret, Pauline Lacote
Publikováno v: EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, ⟨10.1051/epjn/2017020⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 27 (2017)
International audience; Oxygen and hydrogen distributions are key elements influencing the residual ductility of zirconium-based nuclear fuel cladding during the quench phase following a Loss Of Coolant Accident (LOCA). During the high temperature ox
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1573820a48e0f05b2a682e03ae4759a8
https://hal.archives-ouvertes.fr/hal-01951563/document
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