Philippe Spaetig
Nationalité: swiss
+41 56 310 29 34
Office:
PSI M 1
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Mission
Évaluation de l'intégrité des internes des réacteurs nucléaires et des composants du système de refroidissement primaire, ainsi que de la fragilisation des aciers des cuves sous pression.
Développement de techniques d'essai sur petits échantillons, de méthodes non destructives et d'analyses analytiques et numériques pour déterminer l'évolution des propriétés des matériaux dans des environnements difficiles.
Enseignement dans le cadre du master en génie nucléaire et formation de jeunes scientifiques dans le domaine des matériaux et des combustibles nucléaires.
Développement de techniques d'essai sur petits échantillons, de méthodes non destructives et d'analyses analytiques et numériques pour déterminer l'évolution des propriétés des matériaux dans des environnements difficiles.
Enseignement dans le cadre du master en génie nucléaire et formation de jeunes scientifiques dans le domaine des matériaux et des combustibles nucléaires.
Philippe Spätig est actuellement professeur adjoint à l'EPFL à l'École des sciences fondamentales, au Laboratoire de physique des réacteurs et de comportement des systèmes. Il a obtenu son diplôme d'ingénieur physicien à l'EPFL en 1991 et son doctorat à l'EPFL en 1995 sur le rôle de l'activation thermique dans la plasticité de l'intermétallique Ni3Al.
De 1995 à 1997, il a travaillé comme post-doctorant au sein du groupe Matériaux du Centre de recherche en physique des plasmas de l'EPFL, où il a étudié les effets de l'irradiation par protons à haute énergie sur les alliages et les métaux purs. Il a ensuite rejoint l'université de Californie à Santa Barbara et a passé deux ans dans le groupe du professeur G.R. Odette, où il a travaillé sur la mécanique de la rupture des aciers ferritiques de construction.
Il a rejoint à nouveau le groupe Matériaux du Centre de recherche en physique des plasmas de l'EPFL en 2000 et a travaillé dans ce groupe jusqu'à la fin de 2012. Ses recherches ont porté sur le durcissement et la fragilisation des aciers sous irradiation, ainsi que sur le développement d'aciers renforcés par dispersion d'oxydes. Il a également travaillé et développé des techniques expérimentales et analytiques d'essai sur petits échantillons afin d'extraire de manière fiable les propriétés mécaniques d'un volume limité de matériau.
En 2013, il a rejoint le Laboratoire des matériaux nucléaires de l'Institut Paul Scherrer, tout en restant associé au Laboratoire de physique des réacteurs et de comportement des systèmes de l'EPFL. Depuis lors, il travaille principalement sur la fatigue et la rupture assistées par l'environnement des aciers austénitiques et des aciers pour cuves sous pression, où il étudie les effets de l'environnement des réacteurs à eau légère sur les propriétés mécaniques.
De 1995 à 1997, il a travaillé comme post-doctorant au sein du groupe Matériaux du Centre de recherche en physique des plasmas de l'EPFL, où il a étudié les effets de l'irradiation par protons à haute énergie sur les alliages et les métaux purs. Il a ensuite rejoint l'université de Californie à Santa Barbara et a passé deux ans dans le groupe du professeur G.R. Odette, où il a travaillé sur la mécanique de la rupture des aciers ferritiques de construction.
Il a rejoint à nouveau le groupe Matériaux du Centre de recherche en physique des plasmas de l'EPFL en 2000 et a travaillé dans ce groupe jusqu'à la fin de 2012. Ses recherches ont porté sur le durcissement et la fragilisation des aciers sous irradiation, ainsi que sur le développement d'aciers renforcés par dispersion d'oxydes. Il a également travaillé et développé des techniques expérimentales et analytiques d'essai sur petits échantillons afin d'extraire de manière fiable les propriétés mécaniques d'un volume limité de matériau.
En 2013, il a rejoint le Laboratoire des matériaux nucléaires de l'Institut Paul Scherrer, tout en restant associé au Laboratoire de physique des réacteurs et de comportement des systèmes de l'EPFL. Depuis lors, il travaille principalement sur la fatigue et la rupture assistées par l'environnement des aciers austénitiques et des aciers pour cuves sous pression, où il étudie les effets de l'environnement des réacteurs à eau légère sur les propriétés mécaniques.
Formation
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1991 – 1991 EPFL - Switzerland
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1995 – 1995
EPFL - Switzerland
Dirigée par
Prof. J.-L. Martin
Microscopic Digital Image Correlation Analysis of Strain Distributions in Stainless Steel 316L Induced by Multiaxial Cyclic Loading
Lausanne, EPFL, 2023. DOI : 10.5075/epfl-thesis-10202.Domain Imaging and Switching Dynamics in BaTiO3-Based Photonic Integrated Devices
Lausanne, EPFL, 2023. DOI : 10.5075/epfl-thesis-10308.Design, prototyping, and thermo-mechanical modelling of a neutron spallation target impacted by high-energy proton-beam pulses in the n_TOF facility at CERN
Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8370.Protein Engineering for Personalized therapy and diagnosis
Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8705.Optical spectroscopy of earth-abundant zinc pnictides for photovoltaics
Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8873.Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments
International Journal Of Fatigue. 2021-04-01. DOI : 10.1016/j.ijfatigue.2020.106111.Characterization of Austenitic Stainless Steels with Regard to Environmentally Assisted Fatigue in Simulated Light Water Reactor Conditions
Metals. 2021-02-01. DOI : 10.3390/met11020307.Mean Stress Effect on the Fatigue Life of 304L Austenitic Steel in Air and PWR Environments Determined with Strain- and Load-Controlled Experiments
Metals. 2021-02-01. DOI : 10.3390/met11020221.First observation of spalling in tantalum at high temperatures induced by high energy proton beam impacts
European Journal of Mechanics - A/Solids. 2020-10-22. DOI : 10.1016/j.euromechsol.2020.104149.Post-irradiation examination of refractory metal candidates for antiproton targets at the European Laboratory for Particle Physics (CERN)
Lausanne, EPFL, 2020. DOI : 10.5075/epfl-thesis-7542.Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments
Lausanne, EPFL, 2020. DOI : 10.5075/epfl-thesis-7831.Dynamic study of contact damping in martensitic stainless steels using nano-indentation
Mechanics Of Materials. 2020-10-01. DOI : 10.1016/j.mechmat.2020.103541.Round Robin into Best Practices for the Determination of Indentation Size Effects
Nanomaterials. 2020-01-10. DOI : 10.3390/nano10010130.Mean Stress Effect on Fatigue Behavior of Austenitic Stainless Steel in Air and LWR Conditions
Mechanical Fatigue of Metals; Springer, Cham, 2019-05-08. p. 386.Evaluation of Quasi-Static and Dynamic Fracture Toughness on the Low-Alloy Reactor Pressure Vessel Steel JRQ in the Transition Region
2019-12-13. 18th International Conference on Fracture and Damage Mechanics. p. 294-299. DOI : 10.4028/www.scientific.net/KEM.827.294.Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments
Corrosion Science. 2019-05-15. DOI : 10.1016/j.corsci.2019.03.013.Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents
Corrosion Science. 2019-07-01. DOI : 10.1016/j.corsci.2019.04.011.Ferritic and Tempered Martensitic Steels
Structural alloys for nuclear energy applications; Elsevier, 2019. p. 485-527.High-Temperature Water Effects on the Fracture Behaviour of Low-Alloy Reactor Pressure Vessel Steels
Lausanne, EPFL, 2019. DOI : 10.5075/epfl-thesis-9391.Evolution of the tensile properties of the tempered martensitic steel Eurofer97 after spallation irradiation at SINQ
Nuclear Materials and Energy. 2018-09-22. DOI : 10.1016/j.nme.2018.09.002.Deformation twinning in irradiated ferritic/martensitic steels
Journal of Nuclear Materials. 2018-04-01. DOI : 10.1016/j.jnucmat.2018.01.057.Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface
Materials Science and Engineering:. 2018-10-01. DOI : 10.1016/j.msea.2018.09.107.Influence of mean stress and light water reactor environment on fatigue life and dislocation microstructures of 316L austenitic steel
Journal of Nuclear Materials. 2018-05-28. DOI : 10.1016/j.jnucmat.2018.05.064.Investigations and numerical modeling of mechanical properties of tempered martensitic steel Eurofer97 at various loading rates, temperatures and after spallation irradiation
Lausanne, EPFL, 2018. DOI : 10.5075/epfl-thesis-8535.Helium effects on irradiation assisted stress corrosion cracking susceptibility of 316L austenitic stainless steel
Lausanne, EPFL, 2018. DOI : 10.5075/epfl-thesis-8268.Helium effects on IASCC susceptibility in as-implanted solution annealed, cold-worked and post-implantation annealed 316L steel
Corrosion Engineering, Science and Technology. 2017-02-09. DOI : 10.1080/1478422X.2017.1323709.Effect of residual stresses on notch toughness of the tempered martensitic steel F82H-MOD
Theoretical and Applied Fracture Mechanics. 2017-05-26. DOI : 10.1016/j.tafmec.2017.05.023.Microstructure and tensile properties of ODS ferritic steels mechanically alloyed with Fe 2 Y
Nuclear Materials and Energy. 2016. DOI : 10.1016/j.nme.2016.09.019.An inverse method based on finite element model to derive the plastic flow properties from non-standard tensile specimens of Eurofer97 steel
Nuclear Materials and Energy. 2016. DOI : 10.1016/j.nme.2016.06.017.Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel
Journal of Nuclear Materials. 2016. DOI : 10.1016/j.jnucmat.2016.05.033.Embrittlement induced by the synergistic effects of radiation damage and helium in structural steels
Lausanne, EPFL, 2015. DOI : 10.5075/epfl-thesis-6824.Hardening induced by radiation damage and helium in structural materials
Lausanne, EPFL, 2015. DOI : 10.5075/epfl-thesis-6490.Investigation of microstructure and microhardness of pure W and W-2Y(2)O(3) materials before and after ion-irradiation
International Journal Of Refractory Metals & Hard Materials. 2014. DOI : 10.1016/j.ijrmhm.2014.06.004.Measurement of residual stresses around the notch of tensile specimens of the high-Cr tempered martensitic steel F82H-mod
2014. 7th International Conference on Materials Structure and Micromechanics of Fracture (MSMF 7), Brno, CZECH REPUBLIC, JUL 01-03, 2013. p. 295-298. DOI : 10.4028/www.scientific.net/KEM.592-593.295.Analytical determination of the constitutive behavior from micro-pillar testing: Application to a tempered martensitic steel
Aip Advances. 2014. DOI : 10.1063/1.4873155.Measurement of residual stresses around the notch of tensile specimens of the high-Cr tempered martensitic steel F82H-mod
2014. p. 295-298.Microstructure and mechanical properties of a W-2wt.%Y2O3 composite produced by sintering and hot forging
Journal Of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.301.On determination of the constitutive behavior of tempered martensitic steels from micro-indentations: Application to Eurofer97 steel
Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.003.Helium embrittlement of a lamellar titanium aluminide
Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2012.11.031.Fracture toughness characterization in the lower transition of neutron irradiated Eurofer97 steel
Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.002.Effect of warm pre-stressing on fracture toughness of Eurofer97 steel
2013. 27th Symposium on Fusion Technology (SOFT), Liège, Belgium, September 24-28, 2012. p. 644-647. DOI : 10.1016/j.fusengdes.2013.05.056.Effect of ion-irradiation on the microstructure and microhardness of the W-2Y(2)O(3) composite materials fabricated by sintering and hot forging
2013. 27th Symposium on Fusion Technology (SOFT). p. 1668-1672. DOI : 10.1016/j.fusengdes.2013.03.060.Interaction between liquid aluminium and solid iron Al-rich intermetallics formation
Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-6044.Modelling oriented investigations of primary radiation damage in ultra high purity Fe and FeCr alloys
Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-6008.Characterization and modeling of neutron irradiation, pre-deformation and warm prestressing effects on the fracture behavior of the tempered martensitic steel Eurofer97
Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-5867.Nanocomposites of carbon nanotubes embedded in a (Ti,Al)N coated film
Surface & Coatings Technology. 2012. DOI : 10.1016/j.surfcoat.2012.09.053.W-2 wt.%Y2O3 composite: Microstructure and mechanical properties
Materials Science And Engineering A-Structural Materials Properties Microstructure And Processing. 2012. DOI : 10.1016/j.msea.2012.01.011.Creep Properties and Related Microstructural Changes of a Lamellar Titanium Aluminide Alloy before and after Helium-Implantation
Lausanne, EPFL, 2012. DOI : 10.5075/epfl-thesis-5306.Effect of thermo-mechanical treatments on the microstructure and mechanical properties of an ODS ferritic steel
Journal Of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.03.006.Strain-rate behavior in tension of the tempered martensitic reduced activation steel Eurofer97
Journal Of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.05.002.From materials development to their test in IFMIF: an overview
Nuclear Fusion. 2011. DOI : 10.1088/0029-5515/51/11/113006.From Materials Development to their Test in IFMIF: an Overview
2010. 23rd IAEA Fusion Energy Conference, Daejon, Korea, 11-16 October 2010.Fracture toughness master-curve analysis of the tempered martensitic steel Eurofer97
2009. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice, France, December 10-14, 2007. p. 323-327. DOI : 10.1016/j.jnucmat.2008.12.122.3D finite element and experimental study of the size requirements for measuring toughness on tempered martensitic steels
Journal of Nuclear Materials. 2009. DOI : 10.1016/j.jnucmat.2009.01.311.Recent progress toward development of reduced activation ferritic/martensitic steels for fusion applications
2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 411-417. DOI : 10.1016/j.jnucmat.2008.12.323.Assessment of irradiation embrittlement of the Eurofer97 steel after 590 MeV proton irradiation
2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 245-248. DOI : 10.1016/j.jnucmat.2008.12.110.Numerical investigation by finite element simulations of the ball punch test: Application to tempered martensitic steels
2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 319-322. DOI : 10.1016/j.jnucmat.2008.12.120.Finite element modeling and experimental study of brittle fracture in tempered martensitic steels for thermonuclear fusion applications
Lausanne, EPFL, 2009. DOI : 10.5075/epfl-thesis-4518.Fracture properties of notched and pre-cracked specimens of a tempered martensitic steel at low temperature
2008. 14th International Conference on the Strength of Materials (ICSMA 14), Xian, PEOPLES R CHINA, June 4-9, 2006. p. 346-349. DOI : 10.1016/j.msea.2006.09.172.Analysis of high temperature deformation mechanism in ODS EUROFER97 alloy
2008. Symposium on Microstructural Processes in Irradiated Materials held at the 2007 TMS Annual Meeting, Orlando, FL, USA, February 25 - March 1, 2007. p. 210-216. DOI : 10.1016/j.jnucmat.2008.08.009.The evolution of the mobile dislocation density during successive stress relaxation transients
Materials Science and Engineering A. 2008. DOI : 10.1016/j.msea.2006.10.196.Fracture toughness behavior in the ductile-brittle transition region of the tempered martensitic Eurofer97 steel: Experiments and modeling
Engineering fracture mechanics. 2008. DOI : 10.1016/j.engfracmech.2008.01.016.A multiscale approach to measuring and modeling cleavage fracture in structural steels
Materials Issues for Generation IV Systems; Dordrecht, The Netherlands: Springer, 2008. p. 203-226.Fracture toughness properties in the transition region of the Eurofer97 tempered martensitic steel
Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.031.The role of small specimen test technology in fusion materials development
Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.04.034.Plastic flow properties and fracture toughness characterization of unirradiated and irradiated tempered martensitic steels
Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.038.The European effort towards the development of a demo structural material: Irradiation behaviour of the European reference RAFM steel EUROFER
Fusion Engineering and Design. 2006. DOI : 10.1016/j.fusengdes.2005.08.044.Constitutive behavior and fracture properties of tempered martensitic steels for nuclear applications
Lausanne, EPFL, 2006. DOI : 10.5075/epfl-thesis-3405.On the strain-hardening of tempered martensitic alloys
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2005. DOI : 10.1016/j.msea.2004.12.056.Assessment of irradiation-hardening on Eurofer97' and Zircaloy 2 with punch tests and finite-element modeling
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2005. DOI : 10.1016/j.msea.2005.02.088.Deformation behaviour and microstructure of nanocrystalline electrodeposited and high pressure torsioned nickel
Acta Materialia. 2005. DOI : 10.1016/j.actamat.2005.01.041.Mechanical behaviour of nanocrystalline electrodeposited Ni above room temperature
Scripta Materialia. 2005. DOI : 10.1016/j.scriptamat.2005.03.026.Dislocation defect interaction in irradiated Cu
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2005. DOI : 10.1016/j.msea.2005.03.093.Assessment of plastic flow and fracture properties with small specimen test techniques for IFMIF-designed specimens
Nuclear Fusion. 2005. DOI : 10.1088/0029-5515/45/7/011.The tensile properties of irradiated Ni single crystals and their temperature dependence
Philosophical Magazine. 2005. DOI : 10.1080/14786430412331319947.Assessment of mechanical properties in unirradiated and irradiated zircaloys and steels with non-standard tests and finite element calculations
Lausanne, EPFL, 2005. DOI : 10.5075/epfl-thesis-3304.A master curve analysis of F82H using statistical and constraint loss size adjustments of small specimen data
Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.255.Hardening mechanisms in ferritic/martensitic steels
2004. Effects of radiation on materials, Tucson, June 18-20, 2002. p. 341-351.On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors
Nuclear Fusion. 2004. DOI : 10.1088/0029-5515/44/1/006.Plastic flow of martensitic model alloys
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2004. DOI : 10.1016/j.msea.2004.02.074.Tensile properties of a tempered martensitic iron-chromium- carbon model alloy
Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.054.Assessment of the constitutive properties from small ball punch test: experiment and modeling
Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.07.052.SANS investigation of proton-irradiated EUROFER97
Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.052.Materials design data for reduced activation martensitic steel type EUROFER
Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.020.Second IEA Fusion Materials Agreement Workshop - Proceedings of the Second IEA Fusion Materials Agreement Workshop on Modeling and Experimental Validation - Les Diableret, Switzerland - September 30-October 4, 2002 - Preface
Journal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.016.Second IEA fusion materials agreement workshop on modeling and experimental validation
Journal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.017.Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H
Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01075-9.Recent progress in small specimen test technology
Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01171-6.Assessment of mechanical properties of the martensitic steel EUROFER97 by means of punch tests
Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01194-7.Microstructure and mechanical properties of two ODS ferritic/martensitic steels
Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01193-5.On the mechanical properties of the advanced martensitic steel EUROFER 97
Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01213-8.Relation between microstructures and constitutive behavior of advanced tempered martensitic steels
2001. Material Instabilities and Patterning in Metals, San Francisco, USA, April 2001. p. BB1.10.1- BB1.10.6. DOI : 10.1557/PROC-679-BB1.10.Transition regime fracture toughness-temperature properties of two advanced ferritic/martensitic steels
2001. Mat. Res. Soc. Symposium Proc.: on Multiscale modelling of materials. p. Z7.8.1-Z7.8.6. DOI : 10.1557/PROC-653-Z7.8.Characterising thermally activated dislocatin mechanisms
Materials Science and Engineering A. 2001. DOI : 10.1016/S0921-5093(00)01763-9.On the constitutive behavior of the F82H ferritic/martensitic steel
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2001. DOI : 10.1016/S0921-5093(00)01634-8.Structural materials for fusion reactors
Nuclear Fusion. 2001. DOI : 10.1088/0029-5515/41/8/308.Dislocation core geometry and mechaical strenght in Ni3Al compounds
2000. 12th Eureopean Congress on Electron Microscopy (EUREM 12).Constitutive behavior and fracture toughness properties of the F82H ferritic/martensitic steel
Journal of Nuclear Materials. 2000. DOI : 10.1016/S0022-3115(00)00232-4.The mechanical properties of 590 MeV proton irradiated iron
Journal of Nuclear Materials. 1999. DOI : 10.1016/S0022-3115(98)00702-8.Low temperature yield properties of two 7-9Cr Ferritic/martensitic steels
Journal of Nuclear Materials. 1999. DOI : 10.1016/S0022-3115(99)00121-X.Impurity segregation investigation in low activation martensitic steels using EFTEM
1998. 11th European Congress on Electron Microscopy.Microstructure assessment of the low activation ferritic/martensitic steel F82H
Journal of Nuclear Materials. 1998. DOI : 10.1016/S0022-3115(98)00182-2.Chemical segregation behavior of the low activation ferritic/martensitic steel F82H
Journal of Nuclear Materials. 1998. DOI : 10.1016/S0022-3115(98)00337-7.Evolution of the mechanical properties of the F82H ferritic/martensitic steel after 590 MeV proton irradiation
Journal of Nuclear Materials. 1998. DOI : 10.1016/S0022-3115(98)00397-3.Deformation microstructures in Ni-3(Al, Hf)
Materials Science and Engineering A -Structural Materials Properties Microstructure and Processing. 1997. DOI : 10.1016/S0921-5093(97)00578-9.Microstructure and mechanical properties of newly developed low activation martensitic steels
Journal of Nuclear Materials. 1996. DOI : 10.1016/S0022-3115(96)00133-X.Rôle de l'activation thermique dans la plasticité de composés intermétalliques ordonnés: Ni3 (Al, X)
Lausanne, EPFL, 1995. DOI : 10.5075/epfl-thesis-1407.Enseignement et PhD
Doctorant·es actuel·les
Rémi Martinie, Gabriel Artus Benedikt Brinkmann
A dirigé les thèses EPFL de
Emiliano Campitelli, Raul Alejandro Bonadé, Pablo Federico Mueller, Per Magnusson, Nazar Ilchuk, Anna Prokhodtseva, Christiane Vieh, Kun Wang, Ignasi Villacampa Roses, Serafin Knitel, Zaiqing Que, Elvis Fornasiere, Wen Chen, Elif Cansu Kursun, Puyi Gao, Dongyang Jiang
Cours
Advanced topics in nuclear reactor materials
ETH-530
Comprendre les aspects avancés de sciences des matériaux en application à l'énergie nucléaire (fission et fusion). Se familiariser avec les matériaux pour des centrales modernes, la caractérisation avancée des dommages et évaluation de durée de vie