STARS PhD Theses

Name Thesis title Director Supervisor(s) Year (Start)
Maccario, Sara Development and Demonstration of a Bayesian Calibration Methodology applicable to Complex Models M. Hursin M. Hursin 2022
Arnold, Benjamin Thermal-Hydraulics Analysis of a Dual Fluid Reactor A. Manera I. Clifford 2022
Name Thesis title Director Supervisor(s) Year (Finished)
Vitullo, Fanny Miniature and Minimalistic Neutron Detectors for Online High-Resolution Experiments in the Zero-Power Reactor CROCUS A. Pautz V. Lamirand 2022
Wei, Zonglan Development of anisotropic unsteady RANS turbulence models A. Pautz B. Niceno, I. Clifford 2022
Papadionysiou, Marianna Development of VVER Computational Scheme for Plant System Analyses Coupled to Higher Resolution Core Multi-Physics Simulations A. Pautz M. Hursin 2022
Shama, Ahmed Data-Driven Predictive Models: Calculational Bias in Characterization of Spent Nuclear Fuel A. Pautz D. Rochman 2021
Chionis Dionysios Development of Advanced Methodologies for monitoring and Modelling of Neutron Noise in Modern Nuclear Reactors A. Pautz A. Dokhane 2020
Mala, Petra Pin-by-Pin Treatment of LWR Cores with Cross Section Equivalence Procedures and Higher-Order Transport Methods A. Pautz M. Hursin 2018
Wicaksono, Damar Bayesian Uncertainty Quantification of Physical Models in Thermal-Hydraulics System Code A. Pautz O. Zerkak, G. Perret 2018
Brankov, Vladimir Modeling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light-Water Reactors A. Pautz G. Khvostov, K. Mikityuk 2017
Zhu, Ting Sampling-Based Nuclear Data Uncertainty Quantification for Continuous Energy Monte Carlo Codes A. Pautz A. Vasiliev 2015
Giust, Flavio Dante Appraisal of BWR core analysis methods against the LWR-PROTEUS experiments R. Chawla P. Grimm 2012
Rätz, Dominik Neutronics experiments and analysis related to strong moderation heterogeneity in LWRs R. Chawla K. Jordan 2012
Sun, Kaichao Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics R. Chawla J. Krepel, K. Mikityuk 2012
Bertolotto, Davide Coupling of a system code with computational fluid dynamics for the simulation of complex coolant reactivity effects R. Chawla A. Manera 2011
Chenu, Aurélia Single- and two-phase flow modeling for coupled neutronics/thermal-hydraulics transient analysis of advanced sodium-cooled fast reactors R. Chawla K. Mikityuk 2011
Kröhnert, Hanna Fission rates measured using high-energy gamma-rays from short half-life fission products in fresh and spent nuclear fuel R. Chawla M. Plaschy, M. Murphy, G. Perret 2011
Epiney, Aaron Simon Improvement of the decay heat removal characteristics of the Generation IV Gas-cooled Fast Reactor R. Chawla K. Mikityuk 2010
Girardin, Gaëtan Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR) R. Chawla S. Pelloni, G. Rimpault 2009
Blair, Paul Modelling of fission gas behaviour in high burnup nuclear fuel R. Chawla Ch. Hellwig, A. Romano, G. Khvostov 2008
Petkevich, Petr Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor R. Chawla K. Mikityuk 2008
Caruso, Stefano Characterisation of high-burnup LWR fuel rods through gamma-tomography R. Chawla M. F. Murphy 2007
Vinai, Paolo Development and application of objective uncertainty measures for transient code predictions R. Chawla   2007
Filippo, Tani Decomposition analysis of reactivity effect predictions for modern LWR fuel R. Chawla   2006
Negreanu, Cezarina Elena Development and validation of data sets and Monte Carlo methods for electron/positron transport at low and medium energies R. Chawla O. P. Joneja, J. Stepanek 2005
Zilio, Valery Olivier Development and validation of on-line dosimetric methods for the treatment of prostate cancer R. Chawla O. P. Joneja 2005
Dokhane, Abdelhamid BWR stability analysis using a novel reduced order model and the system code RAMONA R. Chawla D. Henning 2004
Plaschy, Michael Numerical and experimental studies of the characteristics of a sub-critical fast system driven by an external source R. Chawla G. Rimpault 2004
Cometto, Marco Benchmarking of ADS calculational tools and their application to different waste transmutation scenarios R. Chawla M. Wydler 2003
Pralong, Catherine Investigation of within-pin reaction rate distributions in a highly heterogeneous fuel assembly R. Chawla   2002
Sengstag, Thierry On the modelling of reactivity initiated accidents in light water reactor cores containing high-burnup fuel R. Chawla   2001
Lüthi, Anton Development and validation of gamma-heating calculational methods for Pu-burning fast reactors R. Chawla   1999
Rosselet, Marc Reactivity measurements and their interpretation in systems with large spatial effects R. Chawla   1999
Kasemeyer, Uwe Design of a uranium-free LWR core for plutonium burning R. Chawla   1998
Köberl, Oliver Experimental neutron balance investigations of water entry in a HTR with low enriched uranium fuel R. Chawla   1998
SQS Signet
IQNET Signet

General Contact

Reactor Systems, Nuclear Fuel and Radiation Safety

Paul Scherrer Institute
5232 Villigen PSI
Switzerland

Hakim Ferroukhi
Project Leader
Office: OHSA/C10
Telephone: +41 56 310 4062
E-mail: hakim.ferroukhi@psi.ch

Petra kull
Administration & Assistance
Office: OHSA/C18
Telephone: +41 56 310 2685
E-mail: petra.kull@psi.ch

LRT

Homepage of Laboratory for Reactor Physics and Thermal-Hydraulics (LRT).

Anfahrt zum PSI

Wie Sie uns finden (Beschreibung und Karte)