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STARS PhD Theses

Current 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
Wei, Zonglan	Development of anisotropic unsteady RANS turbulence models	Prof. Dr. H.-M. Prasser, Prof. Dr. J. Carmeliet	Niceno, Bojan (LSM)	2017

Completed Theses

Name	Thesis title	Year
Bertolotto, Davide	Coupling of a system code with computational fluid dynamics for the simulation of complex coolant reactivity effects	2011
Blair, Paul	Modelling of fission gas behaviour in high burnup nuclear fuel	2008
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
Chionis Dionysios	Development of advanced methodologies for monitoring and modelling of neutron noise in modern LWR cores	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
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
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
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
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
Rosselet, Marc	Reactivity measurements and their interpretation in systems with large spatial effects	1999
Sengstag, Thierry	On the modelling of reactivity initiated accidents in light water reactor cores containing high-burnup fuel	2001
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