PhD theses in LNM (and the former LWV):

Name Thesis title
Choi Kwanghoon Inflight Drying Process of Micro-Droplet to Improve the 3D Printing Resolution
S. Bhattacharya Atomic scale structure of standard and chromia-doped UO2 fuels
Andrea Cavaliere Thermophysical characterization of SiC ceramic-matrix-composite cladding with laser-based contactless approach
Puyi Gao Experimental assessment of fracture initiation and micro-crack arrest toughness on RPV steel
Dongyan Jiang Embrittlement assessment and Master-Curve application on inhomogeneous RPV steels with sub-sized and non-standard specimens
Adrianna Mackiewicz Mechanistic studies on the effect of Zn water chemistry on the oxidation and stress corrosion cracking behaviour of LWR structural materials
Okan Yetik Neutron radiography investigation of hydrides redistribution in active zirconium claddings
Anna Nastruzzi Study on mechanism of irradiation creep by using in-situ strain testing, ex-situ TEM observation and SIMS trace diffusion measurement
Name Thesis title


Elif Cansu Kursun Microscopic Digital Image Correlation Analysis of Strain Distributions in Stainless Steel 316L Induced by Multiaxial Cyclic Loading 2023
Francesco Fagnoni Hydrogen enhanced localized plasticity in zirconium-based nuclear fuel clads 2023
Aaron Colldeweih Delayed Hydride Cracking in Irradiated and Unirradiated Zircaloy-2 Cladding 2022
Cui Lijuan APT/TEM characterization of the element segregation in ferritic/martensitic steels after irradiation in SINQ 2021
Jonathan Hawes The causes of increased hydrogen uptake of zirconium based fuel claddings at high burnup 2020
Wen Chen Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments 2020
Adrienn Baris Increased Hydrogen uptake of Zirconium based claddings at high burnup 2019
Zaiqing Que High-Temperature Water Effects on the Fracture Behaviour of Low-Alloy Reactor Pressure Vessel Steels 2019
Jemila Habainy Characterisation of mechanical and thermal properties of tungsten for high power spallation target application 2018
Loïc Fave Investigation of the thermal conductivity of SiC/SiC cladding before and after irradiation 2017
Serafin Knitel Fracture of tempered martensitic and ODS steel 2018
Ignasi Villacampa Rosés The effects of helium on IASC 2017
Juxing Bai The effect of hydrogen on the SCC crack initiation and short crack growth. behaviour of Alloy 182 weld metal under BWR/HWC conditions 2017
Nicolò Grilli Constitutive modeling for crystal plasticity finite element computation of cyclic plasticity in fatigue 2016
Kun Wang Embrittlement induced by the Synergistic Effects of Radiation Damage and Helium in Structural Materials 2015
Christiane Vieh Hardening induced by synergistic effects of radiation damage and helium in structural materials 2015
Cyprian Mieszczynski Atomic scale structural modifications in irradiated nuclear fuels 2014
Wenwang Wu Free surface effects in TEM imaging of dislocation lines and loops in Fe 2014
Giacomo Facheris Cyclic plastic material behaviour leading to crack Initiation in stainless steel under complex fatigue loading conditions 2014
Andi Idhil The effect of Cr composition on the local atomic and magnetic structure of pristine and ion-irradiated FeCr alloys 2013
Maria Cabanes Sempere Innovative production of nuclear fuel by microwave internal gelation 2013
Per Magnusson Creep Properties and Related Microstructural Changes of a Lamellar Titanium Aluminide Alloy before and after Helium-Implantation 2012
Mathias Breimesser Establishment and Interpretation of Correlations between Macroscopic Electrochemical Noise and Signals from Microscopic Stress Corrosion Initiation Events by a Novel Micro-Electrochemical Approach 2012
Andrey Orlov Corrosion product deposition on fuel element surfaces of a boiling water reactor 2012
Christian Proff Microstructural Aspects of the Oxidation of Zirconium Alloys 2012
Ning Gao Molecular Dynamics Simulations of Helium Atoms Clustering in bcc Iron 2011
Mageshwaran Ramesh Thermomechanical Fatigue Behavior of Austenitic Stainless Steels 2010
Sebastiano Cammelli Investigation of clusters and precipitates in reactor pressure vessel steels by X-ray absorption spectroscopy 2009
Paul Blair Modelling of fission gas behaviour in high burnup nuclear fuel 2008
Mathias Horvath Development of a method for Xenon determination in the microstructure of high burn-up nuclear fuel 2007
Raluca Stoenescu Effects of Neutron Irradiation on the Microstructure and Mechanical Properties of the Affected Zone of Stainless Steel Welds 2005
Emilio Campitelli Assessment of Mechanical Properties in Unirradiated and Irradiated Zircaloys and Finite Element Calculations 2005
Marco Streit Fabrication and Characterisation of (Pu,Zr)N Fuels 2004
Jian Chen A Non-local Damage Model for Elasto-plastic Materials Based on Gradient Plasticity Theory 2001
Ralph Münch Application of the electrochemical impedance spectroscopy method to the study of the growth of zircalloy-oxides at high temperature and high pressure 2000
Manuel Pouchon Contribution to the Study of Zirconia-based Nuclear Fuel for Plutonium Use in Light Water Reactor 1999
Claude Bailat The effect of light water reactor irradiation conditions of the microstructure and mechanical properties of stainless steel 1999
Helena Loner Einflüsse der Wasserinhaltsstoffe auf den Aktivitätstransport im Wasserkreislauf eines Siedewasserreaktors 1995
Irene Mäiland Strukturelle und elektronische Eigenschaften der unter Heißwassereinwirkung auf Chrom-Nickel-Stahl gebildeten Spinelloxide - Elektrochemische Impedanzspektroskopie, Mott-Schottky-Analyse und Photoelektrochemie an Oxidschichten des austenitischen Chrom-Nickel-Stahls (1.4571) 1995