STARS PhD Theses

NameThesis titleDirectorSupervisor(s)Year (Start)
Portolan, SofiaSwissneutronics: Swiss neutronics methods for used nuclear fuel simulationsA. ManeraD. Rochman2024
Güttlein, CynthiaDevelopment of steady-state and transient neutronic solvers for reactor core simulationsA. ManeraA. Cherezov2024
Ponce Tovar, MarioDevelopment of multi-physics solvers for coupled core and propulsion system analysesA. ManeraI. Clifford2024
Kelk, RainerUse of machine-learning for severe accident analysisA. ManeraT. Lind2024
Mazzone, Daniel VincentDevelopment and integration of new models for annular flow phenomenaA. ManeraO. Al-Yahia2024
Maccario, SaraDevelopment and Demonstration of a Bayesian Calibration Methodology applicable to Complex ModelsM. HursinM. Hursin2022
Arnold, BenjaminThermal-Hydraulics Analysis of a Dual Fluid ReactorA. ManeraI. Clifford2022
NameThesis titleDirectorSupervisor(s)Year (Finished)
Vitullo, FannyMiniature and Minimalistic Neutron Detectors for Online High-Resolution Experiments in the Zero-Power Reactor CROCUSA. PautzV. Lamirand2022
Wei, ZonglanDevelopment of anisotropic unsteady RANS turbulence modelsA. PautzB. Niceno, I. Clifford2022
Papadionysiou, MariannaMulti-physics modeling of VVERs with high fidelity high-resolution codesA. PautzM. Hursin2022
Shama, AhmedData-Driven Predictive Models: Calculational Bias in Characterization of Spent Nuclear FuelA. PautzD. Rochman2021
Chionis DionysiosDevelopment of Advanced Methodologies for monitoring and Modelling of Neutron Noise in Modern Nuclear ReactorsA. PautzA. Dokhane2020
Mala, PetraPin-by-Pin Treatment of LWR Cores with Cross Section Equivalence Procedures and Higher-Order Transport MethodsA. PautzM. Hursin2018
Wicaksono, DamarBayesian Uncertainty Quantification of Physical Models in Thermal-Hydraulics System CodeA. PautzO. Zerkak, G. Perret2018
Brankov, VladimirModeling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light-Water ReactorsA. PautzG. Khvostov, K. Mikityuk2017
Zhu, TingSampling-Based Nuclear Data Uncertainty Quantification for Continuous Energy Monte Carlo CodesA. PautzA. Vasiliev2015
Giust, Flavio DanteAppraisal of BWR core analysis methods against the LWR-PROTEUS experimentsR. ChawlaP. Grimm2012
Rätz, DominikNeutronics experiments and analysis related to strong moderation heterogeneity in LWRsR. ChawlaK. Jordan2012
Sun, KaichaoAnalysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety CharacteristicsR. ChawlaJ. Krepel, K. Mikityuk2012
Bertolotto, DavideCoupling of a system code with computational fluid dynamics for the simulation of complex coolant reactivity effectsR. ChawlaA. Manera2011
Chenu, AuréliaSingle- and two-phase flow modeling for coupled neutronics/thermal-hydraulics transient analysis of advanced sodium-cooled fast reactorsR. ChawlaK. Mikityuk2011
Kröhnert, HannaFission rates measured using high-energy gamma-rays from short half-life fission products in fresh and spent nuclear fuelR. ChawlaM. Plaschy, M. Murphy, G. Perret2011
Epiney, Aaron SimonImprovement of the decay heat removal characteristics of the Generation IV Gas-cooled Fast ReactorR. ChawlaK. Mikityuk2010
Girardin, GaëtanDevelopment of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR)R. ChawlaS. Pelloni, G. Rimpault2009
Blair, PaulModelling of fission gas behaviour in high burnup nuclear fuelR. ChawlaCh. Hellwig, A. Romano, G. Khvostov2008
Petkevich, PetrDevelopment and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactorR. ChawlaK. Mikityuk2008
Caruso, StefanoCharacterisation of high-burnup LWR fuel rods through gamma-tomographyR. ChawlaM. F. Murphy2007
Vinai, PaoloDevelopment and application of objective uncertainty measures for transient code predictionsR. Chawla 2007
Filippo, TaniDecomposition analysis of reactivity effect predictions for modern LWR fuelR. Chawla 2006
Negreanu, Cezarina ElenaDevelopment and validation of data sets and Monte Carlo methods for electron/positron transport at low and medium energiesR. ChawlaO. P. Joneja, J. Stepanek2005
Zilio, Valery OlivierDevelopment and validation of on-line dosimetric methods for the treatment of prostate cancerR. ChawlaO. P. Joneja2005
Dokhane, AbdelhamidBWR stability analysis using a novel reduced order model and the system code RAMONAR. ChawlaD. Henning2004
Plaschy, MichaelNumerical and experimental studies of the characteristics of a sub-critical fast system driven by an external sourceR. ChawlaG. Rimpault2004
Cometto, MarcoBenchmarking of ADS calculational tools and their application to different waste transmutation scenariosR. ChawlaM. Wydler2003
Pralong, CatherineInvestigation of within-pin reaction rate distributions in a highly heterogeneous fuel assemblyR. Chawla 2002
Sengstag, ThierryOn the modelling of reactivity initiated accidents in light water reactor cores containing high-burnup fuelR. Chawla 2001
Lüthi, AntonDevelopment and validation of gamma-heating calculational methods for Pu-burning fast reactorsR. Chawla 1999
Rosselet, MarcReactivity measurements and their interpretation in systems with large spatial effectsR. Chawla 1999
Kasemeyer, UweDesign of a uranium-free LWR core for plutonium burningR. Chawla 1998
Köberl, OliverExperimental neutron balance investigations of water entry in a HTR with low enriched uranium fuelR. Chawla 1998