PhD Theses

Name Thesis title Director Supervisor(s) Year
Shama, Ahmed Application of SCALE and Machine Learning algorithms for predictions of biases and uncertainties in UNF isotopic composition and decay heat estimations Prof. Dr. A. Pautz D. Rochman 2020
Papadionysiou, Marianna Development of VVER Computational Scheme for Plant System Analyses Coupled to Higher Resolution Core Multi-Physics Simulations Prof. Dr. A. Pautz Hursin, Mathieu 2018
Papadopoulos, Petros Experimental Validation of Gas Retention in Two-Phase Flows in Filtered Containment Venting Systems Prof. Dr. H.-M. Prasser Lind, Terttaliisa 2017
Wei, Zonglan Development of anisotropic unsteady RANS turbulence models Prof. Dr. H.-M. Prasser, Prof. Dr. J. Carmeliet Niceno, B.  (LSM) 2017
Wolfertz, Alexander Development, Characterization and Optimization of a Fast Neutron Detector System for Reactor Physics Measurements and Neutron Imaging Prof. Dr. A. Pautz Perret G., Adams R. 2018
Name Thesis title Year
Ammar, Yasmine Turbulent Agglomeration and Break-up of Nuclear Aerosols 2008
Badreddine, Hassan Finite Size Lagrangian Particle Tracking Approach for Dispersed Bubbly Flows Simulations 2015
Bertolotto, Davide Coupling of a system code with computational fluid dynamics for the simulation of complex coolant reactivity effects 2011
Betschart, Torsten Two-Phase Flow Investigations in Large Diameter Channels and Tube Bundles 2015
Blair, Paul Modelling of fission gas behaviour in high burnup nuclear fuel 2008
Bolesch, Christian Tomographic Dryout Experiment 2018
Bosshard, Christoph Large Eddy Simulation of Particle Dynamics Inside a Differentially Heated Cavity 2012
Brankov, Vladimir Modeling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light-Water Reactors 2017
Caruso, Stefano Characterisation of high-burnup LWR fuel rods through gamma-tomography 2007
Chenu, Aurélia Single- and two-phase flow modeling for coupled neutronics/thermal-hydraulics transient analysis of advanced sodium-cooled fast reactors 2011
Chionis Dionysios Development of Advanced Methodologies for monitoring and Modelling of Neutron Noise in Modern Nuclear Reactors 2020
Cometto, Marco Benchmarking of ADS calculational tools and their application to different waste transmutation scenarios 2003
Dokhane, Abdelhamid BWR stability analysis using a novel reduced order model and the system code RAMONA 2004
Dupont, Julien Thin liquid film dynamics in a condensing and re-evaporating environment 2017
Epiney, Aaron Simon Improvement of the decay heat removal characteristics of the Generation IV Gas-cooled Fast Reactor 2010
Filippo, Tani Decomposition analysis of reactivity effect predictions for modern LWR fuel 2006
Girardin, Gaëtan Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR) 2009
Giust, Flavio Dante Appraisal of BWR core analysis methods against the LWR-PROTEUS experiments 2012
Ihalainen, Mika Fragmentation and Bounce of Nanosize Agglomerates by Inertial Impaction 2014
Janasz, Filip Effect of non-Condensable gases on Reflux condensation in nuclear steam generator tubes 2019
Kalilainen, Jarmo Fission product transport in the primary circuit and in the containment in severe nuclear accidents 2014
Kapulla, Ralf Experimentelle Untersuchung von thermisch stratifizierten und unstratifizierten Mischungsschichten in Natrium und Wasser 2000
Kasemeyer, Uwe Design of a uranium-free LWR core for plutonium burning 1998
Köberl, Oliver Experimental neutron balance investigations of water entry in a HTR with low enriched uranium fuel 1998
Kröhnert, Hanna Fission rates measured using high-energy gamma-rays from short half-life fission products in fresh and spent nuclear fuel 2011
Kromer Heiko Optimization of a compact fast neutron generator for imaging purposes 2020
Kubasch, Jens Holger Bubble hydrodynamics in large pools 2001
Lopez del Pra, Claudia A Theoretical Investigation of Aerosol Retention within the Secondary Side of a Steam Generator under a SGTR Severe Accident Sequence in a PWR Nuclear Power Plant 2012
Lüthi, Anton Development and validation of gamma-heating calculational methods for Pu-burning fast reactors 1999
Mala, Petra Pin-by-Pin Treatment of LWR Cores with Cross Section Equivalence Procedures and Higher-Order Transport Methods 2018
Negreanu, Cezarina Elena Development and validation of data sets and Monte Carlo methods for electron/positron transport at low and medium energies 2005
Park, Sanggil Nitriding and Re-oxidation Behavior of Zircaloy-4 at High Temperatures 2020
Petkevich, Petr Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor 2008
Plaschy, Michael Numerical and experimental studies of the characteristics of a sub-critical fast system driven by an external source 2004
Pralong, Catherine Investigation of within-pin reaction rate distributions in a highly heterogeneous fuel assembly 2002
Rätz, Dominik Neutronics experiments and analysis related to strong moderation heterogeneity in LWRs 2012
Ritterath, Martin Instrumentation and mixing experiments on safety relevant gas flows in containments of nuclear reactors 2012
Rosselet, Marc Reactivity measurements and their interpretation in systems with large spatial effects 1999
Scolaro, Alessandro Development of a Novel Finite Volume Methodology for Multi-Dimensional Fuel Performance Applications 2021
Sengstag, Thierry On the modelling of reactivity initiated accidents in light water reactor cores containing high-burnup fuel 2001
Soubelet Benoit

Development of energy-selective fast neutron imaging for nondestructive elemental analysis

 2020
Sun, Kaichao Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics 2012
Vinai, Paolo Development and application of objective uncertainty measures for transient code predictions 2007
Wicaksono, Damar Bayesian Uncertainty Quantification of Physical Models in Thermal-Hydraulics System Code 2018
Zilio, Valery Olivier Development and validation of on-line dosimetric methods for the treatment of prostate cancer 2005
Zhu, Ting Sampling-Based Nuclear Data Uncertainty Quantification for Continuous Energy Monte Carlo Codes 2015

General Contact

Research Division
Nuclear Energy and Safety (NES)

Laboratory for Reactor Physics and Thermal-Hydraulics (LRT)
Paul Scherrer Institute
5232 Villigen PSI
Switzerland

Dr. Hakim Ferroukhi
Head of the Laboratory
Office: OHSA/C10
Telephone: +41 56 310 40 62
E-mail: hakim.ferroukhi@psi.ch

Petra Kull
Administration and Assistance
Office: OHSA/C18
Telephone: + 41 56 310 26 85
E-mail: petra.kull@psi.ch

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