Philippe Spaetig

Nationality: swiss

Mission

Integrity assessment of nuclear reactor internals and of components of the primary coolant system, as well as of embrittlement of pressure vessel steels.
Development of small specimen test techniques, non-destructive methods, and analytical and numerical analysis to determine materials properties evolution in harsh environments.
Teaching for the Master in Nuclear Engineering and education of young scientists in the field of nuclear materials and fuel.

Philippe Spätig is currently Adjunct Professor at EPFL in the School of Basic Sciences, in the Laboratory of Reactor Physics and Systems Behaviours. He obtained his diploma of Engineer Physicist at EPFL in 1991 and his PhD at EPFL in 1995 on the role of thermal activation in the plasticity of the intermetallic Ni3Al.
From 1995 to 1997, he worked as postdoc in the Materials Group of the Center for Research in Plasma Physics at EPFL, studying the effects of high-energy proton irradiation on alloys and pure metals. He then moved to the University of California Santa Barbara and spent two years in the group of Professor G.R. Odette, working on fracture mechanics of ferritic structural steels.
He joined again the Materials Group of the Center for Research in Plasma Physics at EPFL in 2000 and worked in this group until the end of 2012. His research was focused on irradiation hardening and embrittlement of steels, as well as on the development of oxide dispersion strengthened steels. He also worked and developed experimental and analytical small specimen test techniques to reliably extract mechanical properties from limited material volume.
In 2013, he joined the Laboratory for Nuclear Materials at Paul Scherrer Institute, while being affiliated with the Laboratory for Reactor Physics and System Behaviours at EPFL. Since then he mainly works on environmentally-assisted fatigue and fracture on austenitic and pressure vessel steels, where the effects of light water reactor environment on mechanical properties are investigated.

Education

Physicist Engineer

| Physics

1991 – 1991 EPFL - Switzerland

PhD

| Physical Metallurgy

1995 – 1995 EPFL - Switzerland
Directed by Prof. J.-L. Martin

EBSD and TKD for Multiscale Crystallography of Shape Memory Alloys

J. Xiao

Lausanne, EPFL, 2025. DOI : 10.5075/epfl-thesis-11538.

Fracture Toughness Evaluation of Inhomogeneous Reactor Pressure Vessel Steels Using Sub-sized Specimens

D. Jiang

Lausanne, EPFL, 2025. DOI : 10.5075/epfl-thesis-10963.

Development of a crack arrest toughness measurement technique using small specimens to evaluate the fracture behavior in the ductile-brittle transition of "ferritic" steels

P. Gao

Lausanne, EPFL, 2025. DOI : 10.5075/epfl-thesis-10989.

Effect of temperature on apparent crack arrest toughness of Eurofer97 measured by a newly developed small specimen test technique

P. GaoP. Spatig

Journal of Nuclear Materials. 2024. DOI : 10.1016/j.jnucmat.2024.155222.

Study of the irradiation hardening of a Fe9Cr ferritic model alloy by nanoindentations

D. ZhouP. SpatigQ. HayatP. SongN. Jennett  et al.

Nuclear Materials and Energy. 2024. DOI : 10.1016/j.nme.2024.101667.

On the determination of the reference temperature T0 of the Master-Curve method using subsized compact tension specimens

D. ZhouD. JiangP. SpätigH.-P. Siefert

Procedia Structural Integrity. 2024. DOI : 10.1016/j.prostr.2023.12.044.

Domain Imaging and Switching Dynamics in BaTiO3-Based Photonic Integrated Devices

J. Geler Kremer

Lausanne, EPFL, 2023. DOI : 10.5075/epfl-thesis-10308.

Microscopic Digital Image Correlation Analysis of Strain Distributions in Stainless Steel 316L Induced by Multiaxial Cyclic Loading

E. C. Kursun

Lausanne, EPFL, 2023. DOI : 10.5075/epfl-thesis-10202.

Optical spectroscopy of earth-abundant zinc pnictides for photovoltaics

E. Z. Stutz

Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8873.

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

R. Esposito

Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8370.

Protein Engineering for Personalized therapy and diagnosis

L. Wei

Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8705.

Insights into hardening, plastically deformed zone and geometrically necessary dislocations of two ion-irradiated FeCrAl(Zr)-ODS ferritic steels: A combined experimental and simulation study

P. SongK. YabuuchiP. Spaetig

Acta Materialia. 2022. DOI : 10.1016/j.actamat.2022.117991.

Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments

W. ChenP. SpatigH. P. Seifert

International Journal Of Fatigue. 2021. DOI : 10.1016/j.ijfatigue.2020.106111.

Mean Stress Effect on the Fatigue Life of 304L Austenitic Steel in Air and PWR Environments Determined with Strain- and Load-Controlled Experiments

P. SpatigJ.-C. Le RouxM. BruchhausenK. Mottershead

Metals. 2021. DOI : 10.3390/met11020221.

Characterization of Austenitic Stainless Steels with Regard to Environmentally Assisted Fatigue in Simulated Light Water Reactor Conditions

M. BruchhausenG. DundulisA. McLennanS. ArrietaT. Austin  et al.

Metals. 2021. DOI : 10.3390/met11020307.

First observation of spalling in tantalum at high temperatures induced by high energy proton beam impacts

C. Torregrosa MartinN. SolieriE. FornasiereJ. Busom DescarregaM. Calviani  et al.

European Journal of Mechanics - A/Solids. 2020. DOI : 10.1016/j.euromechsol.2020.104149.

Dynamic study of contact damping in martensitic stainless steels using nano-indentation

R. MouginotP. SpatigH.-P. Seifert

Mechanics Of Materials. 2020. DOI : 10.1016/j.mechmat.2020.103541.

Round Robin into Best Practices for the Determination of Indentation Size Effects

A. Ruiz-MorenoP. HähnerL. KurpaskaJ. JagielskiP. Spätig  et al.

Nanomaterials. 2020. DOI : 10.3390/nano10010130.

Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments

W. Chen

Lausanne, EPFL, 2020. DOI : 10.5075/epfl-thesis-7831.

Post-irradiation examination of refractory metal candidates for antiproton targets at the European Laboratory for Particle Physics (CERN)

E. Fornasiere

Lausanne, EPFL, 2020. DOI : 10.5075/epfl-thesis-7542.

Evaluation of Quasi-Static and Dynamic Fracture Toughness on the Low-Alloy Reactor Pressure Vessel Steel JRQ in the Transition Region

P. SpätigV. MazánováS. SumanH. P. Seifert

2019. 18th International Conference on Fracture and Damage Mechanics. p. 294 - 299. DOI : 10.4028/www.scientific.net/KEM.827.294.

Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents

Z. QueH. SeifertP. SpätigJ. HolzerA. Zhang  et al.

Corrosion Science. 2019. DOI : 10.1016/j.corsci.2019.04.011.

Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments

Z. QueH. SeifertP. SpätigA. ZhangJ. Holzer  et al.

Corrosion Science. 2019. DOI : 10.1016/j.corsci.2019.03.013.

Mean Stress Effect on Fatigue Behavior of Austenitic Stainless Steel in Air and LWR Conditions

W. ChenP. SpätigH. P. Seifert

Mechanical Fatigue of Metals; Springer, Cham, 2019.

Ferritic and Tempered Martensitic Steels

P. SpätigJ.-C. ChenG. R. Odette

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

Z. Que

Lausanne, EPFL, 2019. DOI : 10.5075/epfl-thesis-9391.

Stress relaxation in the presence of sudden strain bursts: Methodology and stress relaxation data of microcast aluminium microwires

S. VerheydennL. DeillonA. Mortensen

Data In Brief. 2018. DOI : 10.1016/j.dib.2018.11.047.

Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface

A. W. ColldeweihA. BarisP. SpätigS. Abolhassani

Materials Science and Engineering:. 2018. DOI : 10.1016/j.msea.2018.09.107.

Evolution of the tensile properties of the tempered martensitic steel Eurofer97 after spallation irradiation at SINQ

S. KnitelP. SpätigT. YamamotoH. SeifertY. Dai  et al.

Nuclear Materials and Energy. 2018. DOI : 10.1016/j.nme.2018.09.002.

Influence of mean stress and light water reactor environment on fatigue life and dislocation microstructures of 316L austenitic steel

P. SpätigM. HeczkoT. KrumlH.-P. Seifert

Journal of Nuclear Materials. 2018. DOI : 10.1016/j.jnucmat.2018.05.064.

Deformation twinning in irradiated ferritic/martensitic steels

K. WangY. DaiP. Spätig

Journal of Nuclear Materials. 2018. DOI : 10.1016/j.jnucmat.2018.01.057.

Helium effects on irradiation assisted stress corrosion cracking susceptibility of 316L austenitic stainless steel

I. Villacampa Roses

Lausanne, EPFL, 2018. DOI : 10.5075/epfl-thesis-8268.

Thermal activation parameters of plastic flow reveal deformation mechanisms in the CrMnFeCoNi high-entropy alloy

G. LaplancheJ. BonnevilleC. VarvenneW. A. CurtinE. P. George

Acta Materialia. 2018. DOI : 10.1016/j.actamat.2017.10.014.

Investigations and numerical modeling of mechanical properties of tempered martensitic steel Eurofer97 at various loading rates, temperatures and after spallation irradiation

S. Knitel

Lausanne, EPFL, 2018. DOI : 10.5075/epfl-thesis-8535.

Effect of residual stresses on notch toughness of the tempered martensitic steel F82H-MOD

N. IlchukV. DavydovP. SpätigH.-P. Seifert

Theoretical and Applied Fracture Mechanics. 2017. DOI : 10.1016/j.tafmec.2017.05.023.

Helium effects on IASCC susceptibility in as-implanted solution annealed, cold-worked and post-implantation annealed 316L steel

I. VillacampaJ. C. ChenP. SpätigH. P. SeifertF. Duval

Corrosion Engineering, Science and Technology. 2017. DOI : 10.1080/1478422X.2017.1323709.

Strength and fracture of silicon second-phase particles in aluminium casting alloys

M. G. Mueller

Lausanne, EPFL, 2017. DOI : 10.5075/epfl-thesis-7892.

Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel

S. RoychowdhuryH. P. SeifertP. SpätigZ. Que

Journal of Nuclear Materials. 2016. DOI : 10.1016/j.jnucmat.2016.05.033.

Microstructure and tensile properties of ODS ferritic steels mechanically alloyed with Fe 2 Y

J. Macías-DelgadoT. LegueyV. De CastroM. AugerM. Monge  et al.

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

S. KnitelP. SpätigH. P. Seifert

Nuclear Materials and Energy. 2016. DOI : 10.1016/j.nme.2016.06.017.

Physics-based constitutive modelling for crystal plasticity finite element computation of cyclic plasticity in fatigue

N. Grilli

Lausanne, EPFL, 2016. DOI : 10.5075/epfl-thesis-7251.

Hardening induced by radiation damage and helium in structural materials

C. Vieh

Lausanne, EPFL, 2015. DOI : 10.5075/epfl-thesis-6490.

Embrittlement induced by the synergistic effects of radiation damage and helium in structural steels

K. Wang

Lausanne, EPFL, 2015. DOI : 10.5075/epfl-thesis-6824.

Investigation of microstructure and microhardness of pure W and W-2Y(2)O(3) materials before and after ion-irradiation

M. BattabyalP. SpätigB. S. MurtyN. Baluc

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

N. IlchukP. SpätigV. DavydovS. van Petegem

2014. p. 295 - 298.

Analytical determination of the constitutive behavior from micro-pillar testing: Application to a tempered martensitic steel

N. IlchukP. SpätigH.-P. Seifert

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

N. IlchukP. SpätigV. DavydovS. van Petegem

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.

Effect of warm pre-stressing on fracture toughness of Eurofer97 steel

N. IlchukL. ComminP. SpätigG. R. Odette

2013. 27th Symposium on Fusion Technology (SOFT), Liège, Belgium, September 24-28, 2012. p. 644 - 647. DOI : 10.1016/j.fusengdes.2013.05.056.

Fracture toughness characterization in the lower transition of neutron irradiated Eurofer97 steel

N. IlchukP. SpätigG. R. Odette

Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.002.

Microstructure and mechanical properties of a W-2wt.%Y2O3 composite produced by sintering and hot forging

M. BattabyalR. SchäublinP. SpätigM. WalterM. Rieth  et al.

Journal Of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.301.

Helium embrittlement of a lamellar titanium aluminide

P. MagnussonJ. ChenP. JungT. SauvageW. Hoffelner  et al.

Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2012.11.031.

Characterization and modeling of neutron irradiation, pre-deformation and warm prestressing effects on the fracture behavior of the tempered martensitic steel Eurofer97

N. Ilchuk

Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-5867.

Interaction between liquid aluminium and solid iron Al-rich intermetallics formation

G. Pasche

Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-6044.

On determination of the constitutive behavior of tempered martensitic steels from micro-indentations: Application to Eurofer97 steel

P. SpätigN. Ilchuk

Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.003.

Modelling oriented investigations of primary radiation damage in ultra high purity Fe and FeCr alloys

A. Prokhodtseva

Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-6008.

Effect of ion-irradiation on the microstructure and microhardness of the W-2Y(2)O(3) composite materials fabricated by sintering and hot forging

M. BattabyalP. SpätigN. Baluc

2013. 27th Symposium on Fusion Technology (SOFT). p. 1668 - 1672. DOI : 10.1016/j.fusengdes.2013.03.060.

Creep Properties and Related Microstructural Changes of a Lamellar Titanium Aluminide Alloy before and after Helium-Implantation

P. Magnusson

Lausanne, EPFL, 2012. DOI : 10.5075/epfl-thesis-5306.

W-2 wt.%Y2O3 composite: Microstructure and mechanical properties

M. BattabyalR. SchäublinP. SpätigB. Baluc

Materials Science and Engineering: A. 2012. DOI : 10.1016/j.msea.2012.01.011.

Nanocomposites of carbon nanotubes embedded in a (Ti,Al)N coated film

L. MarotT. de los ArcosA. BünzliC. WäckerlinR. Steiner  et al.

Surface and Coatings Technology. 2012. DOI : 10.1016/j.surfcoat.2012.09.053.

Strain-rate behavior in tension of the tempered martensitic reduced activation steel Eurofer97

E. CadoniM. DottaD. ForniP. Spätig

Journal Of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.05.002.

From materials development to their test in IFMIF: an overview

N. BalucR. SchäublinP. SpätigN. llchukL. Veleva  et al.

Nuclear Fusion. 2011. DOI : 10.1088/0029-5515/51/11/113006.

Effect of thermo-mechanical treatments on the microstructure and mechanical properties of an ODS ferritic steel

Z. OksiutaP. MuellerP. SpätigN. Baluc

Journal of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.03.006.

From Materials Development to their Test in IFMIF: an Overview

N. BalucR. SchäublinP. SpätigJ. TheileM.-Q. Tran

2010. 23rd IAEA Fusion Energy Conference, Daejon, Korea, 11-16 October 2010.

Fracture toughness master-curve analysis of the tempered martensitic steel Eurofer97

P. MuellerP. SpätigR. BonadéG. R. OdetteD. Gragg

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

P. MuellerP. Spätig

Journal of Nuclear Materials. 2009. DOI : 10.1016/j.jnucmat.2009.01.311.

Finite element modeling and experimental study of brittle fracture in tempered martensitic steels for thermonuclear fusion applications

P. F. Mueller

Lausanne, EPFL, 2009. DOI : 10.5075/epfl-thesis-4518.

Numerical investigation by finite element simulations of the ball punch test: Application to tempered martensitic steels

E. CampitelliP. SpätigJ. Bertsch

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.

Recent progress toward development of reduced activation ferritic/martensitic steels for fusion applications

R. J. KurtzA. AlamoE. LuconQ. HuangS. Jitsukawa  et al.

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

P. SpätigR. StoenescuP. MuellerG. R. OdetteD. Gragg

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.

Analysis of high temperature deformation mechanism in ODS EUROFER97 alloy

A. RamarP. SpätigR. Schaeublin

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

R. BonadéP. Spätig

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

R. BonadéP. MuellerP. Spätig

Engineering fracture mechanics. 2008. DOI : 10.1016/j.engfracmech.2008.01.016.

Fracture properties of notched and pre-cracked specimens of a tempered martensitic steel at low temperature

P. MuellerR. BonadeP. Spätig

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.

A multiscale approach to measuring and modeling cleavage fracture in structural steels

G. R. OdetteH. J. RathbunM. HribernickT. YamamotoM. He  et al.

Materials Issues for Generation IV Systems; Dordrecht, The Netherlands: Springer, 2008. p. 203 - 226.

Measurement of the effective activation volume in 45 XD titanium aluminides by repeated transient tests

F. DiologentT. Kruml

Materials Science and Engineering: A. 2008. DOI : 10.1016/j.msea.2007.10.029.

Plastic flow properties and fracture toughness characterization of unirradiated and irradiated tempered martensitic steels

P. SpätigR. BonadeG. R. OdetteJ. W. RensmanE. N. Campitelli  et al.

Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.038.

Fracture toughness properties in the transition region of the Eurofer97 tempered martensitic steel

R. BonadeP. SpätigN. Baluc

Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.031.

The role of small specimen test technology in fusion materials development

G. E. LucasG. R. OdetteH. MatsuiA. MöslangP. Spätig  et al.

Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.04.034.

Constitutive behavior and fracture properties of tempered martensitic steels for nuclear applications : experiments and modelling

R. A. Bonadé

Lausanne, EPFL, 2006. DOI : 10.5075/epfl-thesis-3405.

The European effort towards the development of a demo structural material: Irradiation behaviour of the European reference RAFM steel EUROFER

E. LuconP. BenoitP. JacquetE. DiegeleR. Lasser  et al.

Fusion Engineering and Design. 2006. DOI : 10.1016/j.fusengdes.2005.08.044.

Dislocation defect interaction in irradiated Cu

R. SchäublinZ. YaoP. SpätigM. Victoria

Materials Science and Engineering: A. 2005. DOI : 10.1016/j.msea.2005.03.093.

On the strain-hardening of tempered martensitic alloys

R. BonadéP. Spätig

Materials Science and Engineering: A. 2005. DOI : 10.1016/j.msea.2004.12.056.

Mechanical behaviour of nanocrystalline electrodeposited Ni above room temperature

F. Dalla TorreH. Van SwygenhovenR. SchäublinP. SpätigM. Victoria

Scripta Materialia. 2005. DOI : 10.1016/j.scriptamat.2005.03.026.

The relationship between the irradiation induced damage and the mechanical properties of single crystal Ni

Z. Yao

Lausanne, EPFL, 2005. DOI : 10.5075/epfl-thesis-3177.

Assessment of irradiation-hardening on Eurofer97' and Zircaloy 2 with punch tests and finite-element modeling

E. N. CampitelliP. SpätigJ. BertschC. Hellwig

Materials Science and Engineering: A. 2005. DOI : 10.1016/j.msea.2005.02.088.

Assessment of plastic flow and fracture properties with small specimen test techniques for IFMIF-designed specimens

P. SpätigE. N. CampitelliR. BonadéN. Baluc

Nuclear Fusion. 2005. DOI : 10.1088/0029-5515/45/7/011.

Assessment of mechanical properties in unirradiated and irradiated zircaloys and steels with non-standard tests and finite element calculations

E. Campitelli

Lausanne, EPFL, 2005. DOI : 10.5075/epfl-thesis-3304.

The tensile properties of irradiated Ni single crystals and their temperature dependence

Z. YaoR. SchäublinP. Spätig

Philosophical Magazine. 2005. DOI : 10.1080/14786430412331319947.

Deformation behaviour and microstructure of nanocrystalline electrodeposited and high pressure torsioned nickel

F. Dalla TorreP. SpätigR. SchäublinM. Victoria

Acta Materialia. 2005. DOI : 10.1016/j.actamat.2005.01.041.

On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors

N. BalucR. SchäublinP. SpätigM. Victoria

Nuclear Fusion. 2004. DOI : 10.1088/0029-5515/44/1/006.

Hardening mechanisms in ferritic/martensitic steels

M. L. GrossbeckT. R. AllenR. G. LottA. S. KumarN. Baluc  et al.

2004. Effects of radiation on materials, Tucson, June 18-20, 2002. p. 341 - 351.

A master curve analysis of F82H using statistical and constraint loss size adjustments of small specimen data

G. OdetteT. YamamotoH. KishimotoM. SokolovP. Spätig  et al.

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.255.

Plastic flow of martensitic model alloys

R. BonadéP. SpätigR. SchäublinM. Victoria

Materials Science and Engineering: A. 2004. DOI : 10.1016/j.msea.2004.02.074.

SANS investigation of proton-irradiated EUROFER97

P. SpätigR. SchäublinN. BalucJ. KohlbrecherM. Victoria

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.052.

Materials design data for reduced activation martensitic steel type EUROFER

A. A. F. TavassoliA. AlamoL. BedelL. ForestJ. M. Gentzbittel  et al.

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.020.

Assessment of the constitutive properties from small ball punch test: experiment and modeling

E. N. CampitelliP. SpätigR. BonadéW. HoffellnerM. Victoria

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.07.052.

Tensile properties of a tempered martensitic iron-chromium- carbon model alloy

R. BonadéP. SpätigM. VictoriaT. YamamotoG. R. Odette

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.054.

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

M. VictoriaP. Spätig

Journal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.016.

Second IEA fusion materials agreement workshop on modeling and experimental validation

M. VictoriaP. Spätig

Journal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.017.

Recent progress in small specimen test technology

G. E. LucasG. R. OdetteM. SokolovP. SpätigT. Yamamoto  et al.

Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01171-6.

Teaching & PhD

PhD Students

Rémi Martinie, Gabriel Artus Benedikt Brinkmann

Past EPFL PhD Students

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

Courses

Advanced topics in nuclear reactor materials

ETH-530

To comprehend advanced aspects of materials science as applied to nuclear power (fission and fusion), to get acquainted with materials for advanced plants, advanced damage characterization and life-time assessments

Effects of radiation on materials

MSE-600

The purpose of this course is to provide the necessary background to understand the effects of irradiation on pure metals and on alloys used in the nuclear industry. The relation between the radiation-induced defects and the evolution of the mechanical properties is highlighted.