| Mikael Mille |
Anisotropic influence of hydrides on fatigue properties of zirconium alloy based nuclear cladding material |
| An Zhang |
Metallographical Characterization of High-Temperature Water Effects on Fracture Behavior of Low Alloy Steels |
| Cavaliere Andrea |
Formation process of ODS particles in steels |
| Aaron Colldeweih |
Evaluation of mechanical properties of irradiated zirconium alloys at the metal-oxide interface |
| Shama Ahmed |
Study of Microfluidic Mixing and Droplet Generation for 3D Printing of Nuclear Fuels |
| Daniel Ulloa |
Modelling of Kr and Xe amount and isotopic abundances in fuel pins as a function of reactor type, burn-up, linear heat rate and irradiation time |
| Marc Raventos |
Construction and qualification of a micro-tensile testing machine for lower scale digital image correlation applied to Zirconium alloys |
| Damien Vacouret |
Caractérisation mécanique de gaines sous chargement mécanique et thermique |
| Ferruccio Bolla |
Chemical and Dielectric studies of internal gelation reagents |
| Raphael Heierli |
Creep-Fatigue of P91 at 400°C |
| Loïc G. Fave |
Determination of helium implantation induced swelling in ODS steels |
| Nathan Barber |
Modeling of thermodynamic properties of chromium in doped nuclear fuel |
| Thomas Schreier |
Bau eines Dampfüberhitzers zu Thermoschockanlage |
| Bhadri Narayanan Lalgudi Srinivas |
Measurement and Evaluation of Oxide growth in Zirconium Binary Alloys and Zircaloy-2 by Steam Corrosion Test |
| Sebastian Lässig |
Thermomechanische Ermüdung infolge zyklischen Thermoschocks |
| Katja Kumpf |
The Potential of Electrochemical Noise to Detect Stress Corrosion Cracking Initiation under Simulated Boiling Water Reactor Conditions |
