Master Theses and Trainees

NameProjectUniversity/ScopeSupervisor(s)Year (Start)
Vocke, MaeganPIV and LIF Measurements in densely stratified mixture layersMcMaster Hamilton / PhDR. Kapulla2024
De Failly, GauthierImpact of the final reactor core fuel loading on the back-end strategy and safety parametersEcole Polytechnique Paris / MSCD. Rochman2024
Zweifel, SandroLocal measurements of particle mass transfer in gas-liquid flowsETHZ/MScA. Ramos, T. Lind2024
Colombo, Dino EzioCFD models validation for nuclear reactors applicationsETHZ/MScA. Manera, V. Petrov2024
Fournier, Victor ColmanNeural Network-Based Estimation of Control Blades Worth for Identifying Limited Patterns in BWRsEPFL/MScA. Cherezov2024
Monney, Axel DanielLIQUID METAL FAST REACTORS / Westinghouse design - experimentsETHZ/MScA. Manera, V. Petrov2024
Pelletier, Augustin JeanCFD simulations of turbulent penetration in T-junctionEPFL/MScE. Fogliatto2024
Sansone, Riccardo LuigiDevelopment of a theoretical model for predicting the physical properties of molten salts systemsEPFL/MScA. Manera, V. Petrov2024
Wang, YatingExperiments to determine gas-liquid two-phase flow properties; related simulation of bubble behaviour and particle motion from gas to liquidTsinghua University in Beijing / PhDA. Ramos, T. Lind2024
NameProjectUniversity/ScopeSupervisor(s)Year (Finished)
König, NicolasStability of passive safety systems - a mathematical analysisETHZ / MScA. Manera, V. Petrov2024
Declerck, AlexandreSensitivity and uncertainty studies for the loading curve derivation for a pseudo-application case of used nuclear fuel final disposalIMT Atlantique / MScM. Frankl2024
Kwon, Sung JoonOECD/NEA/NSC/WPRS Watts Bar 1 benchmark simulation with nTRACER/CTFSeoul National University / BScM. Hursin, M. Papadionysiou2024
Cho, YeongjaeMELCOR UQ study and validation based on PANDA experimentUNIST - Ulsan National Institute of Science & TechnologyM. Malicki2024
Elshater Mohamed, ShadyDevelopment of SPARTACUS: A Toolbox for Trajectory, Mission and System Design (Nuclear Electric Propulsion for Space Exploration)ETHZ/MScA. Cherezov2024
Berti, NicolaFuel Behaviour - Thermo-mechanical behaviour of ATF composite claddingETHZ/MScC. Cozzo2024
Baldo, EduardoThermal analysis of a nuclear space reactorETHZ/MScI. Clifford2024
Valentin, Jean-Baptiste Bruno MarieLarge Volume Dosimetry for BLOOM in CROCUSEPFL/MScV. Lamirand2024
Meunier, Benjamin Arthur HugoValidation of Novel Nuclear Data EvaluationEPFL/MScM. Hursin2024
Colombo, Dino EzioCFD models validation for nuclear reactors applicationsETHZ/MScA. Manera, V. Petrov2024
Fernandez de Losada, Lucas JavierTechno-economic modeling of the nuclear technology in the Swiss energy systemETHZ/MScA. Manera, G. Sansavini (ETHZ)2024
Freyssinet, Léonard Loïc BrunoTechno-economic modeling of the nuclear technology in the Swiss energy systemETHZ/MScA. Manera, G. Sansavini (ETHZ)2024
Monney, Axel DanielLIQUID METAL FAST REACTORS / Westinghouse design - experimentsETHZ/MScA. Manera, V. Petrov2024
Sansone, Riccardo LuigiDevelopment of a theoretical model for predicting the physical properties of molten salts systemsEPFL/MScA. Manera, V. Petrov2024
Tagliabue, PierluigiCFD models validation for nuclear reactors applicationsETHZ/MScA. Manera, V. Petrov2024
Tasiopoulou, TheodoraHigh resolution experiments and CFD modeling of hot spots in wire-wrapped fuel assembliesEPFL/MScA. Manera, V. Petrov2024
Arfinengo del Carpio, SofíaComputational analyses using the GOTHIC code related to the PANDA P1A1 seriesUniversitad Politécnica de Madrid, Spain/PhDD. Paladino2023
Gabicagogeascoa Cuesta, CarlotaComputational analyses using the GOTHIC code related to the PANDA P1A1 seriesUniversitad Politécnica de Madrid, Spain/MScD. Paladino2023
Lee, JuwookAnalyses of PANDA experiments performed within the OECD/NEA framework with containmentFOAMSeoul National University | MScM. S. Chae2023
Orive Soto, JavierEffects of the Final Reactor Core Fuel Loading on Back-End StrategyEPFL/MScD. Rochman, G. Girardin (KKG)2023
Oliva, AngelaThe analyses of experiments related to pressure suppression pool phenomena relevant for SMRsCEA/PhDD. Paladino2023
Biot, GrégoireReactor Mathematics - Reactor Core Transient Simulations on Low-Precision HardwareEPFL/MScA. Cherezov2023
Jang, Ji-HyeMitigation of source term from severe accidents in nuclear reactors; characterization of solid absorbents applied for retention of organic iodide speciesSejong University of Seoul, Rep. Korea/KONICOF/BScF. Espegren, T. Lind2023
King, StephenAnalyses using CFD Code of aerosol transport in large containment building, using experimental data optained at TAMUTexas A&M University, USA/PhDA. Dehbi / D. Paladino2023
Arnold, BenjaminDevelopment and Validation of Machine Learning supported Methodology for Critical Power Ratio Estimation by Sub channel CodesUni Basel/MScK. Nikitin2022
Arfinengo del Carpio, SofíaAnalyses using the GOTHIC code of the PANDA P1A3 seriesUniversitad Politécnica de Madrid, Spain/PhDM. Andreani2023
Liu, ZhipengModeling the Rostov-II boron dilution transient with TRACE/PARCSXi'an Jiaotong University, China/PhD TraineeM. Hursin2022
Biot, GrégoireReactor Mathematics - Reactor Core Transient Simulations on Low-Precision HardwareEPFL/MScA. Cherezov2022
Orive Soto, JavierEffects of the Final Reactor Core Fuel Loading on Back-End StrategyEPFL/MScD. Rochman, G. Girardin (KKG)2022
Saliba, MichelThe SAFFRON core-mapping array in CROCUS for fission chain correlation studiesEPFL/MScV. Lamirand, W. Monange (IRSN)2022
Schmid Fernandes, Clife100% Renewables with no blackouts, dream or realityEPFL/MScA. Manera, V. Petrov2022
Nervi GiovanniCFD for thermal fatigue in branch lines / Turbulence/induced thermal fatigue in isolated branch linesEPFL/MScA. Manera, V. Petrov2022
König NicolasHigh-speed gamma tomography based on positron emittersETHZ/MSCA. Manera, V. Petrov2022
Borys, FrancisHigh-speed gamma tomography based on positron emittersEPFL/MScA. Manera, V. Petrov2022
Jermann, EliotExtension and testing of electronics for in-house gamma tomography systemEPFL/MScA. Manera, V. Petrov2022
Mazzone, DanielComparison of Different Fuel Elements for their Susceptibility for Novel CRUD-DepositionsEPFL/MScA. Manera, V. Petrov, L. Robers (Axpo)2022
Rivera Durán, YagoHigh-resolution liquid film measurementsUniversitat Politècnica de València, ES/PhDA. Manera, V. Petrov2022
Vocke, MaeganPouring space into time: From the Eulerian to the Lagrangian frequency based on planar DNS dataUniversity of Calgary, Canada/MScR. Kapulla2022
Kirkby, EthanProper Orthogonal Decomposition Analysis of a DNS Planar Jet (HYMERES-2 NEST)University of Calgary, Canada/BScR. Kapulla2021
Seyffert, Caroline MELCOR code validation based on PANDA experimentETHZ/MScM. Malicki2022
Xu, RuiCFD modeling of two-phase flow in a helical coilETHZ/MScA. Manera2022
Lapaire-Lemoine, SophieDesign of a conductivity detector for Voidmeasurement in a two component mixtureEPFL/MScM. Hursin2022
Liu, ProsperThermal hydraulic Interaction between the reactor coolant system and containment buildingGrenoble Institute of Technology, France /MScO. Al-Yahia2022
Kwack, DahuiMachine learning and CFD Models for the prediction of thermal-mechanical fatigue in insulated branch pipesETHZ/MScA. Manera, V. Petrov2022
Hwang, Hye-JinAnalysis of loss-of-coolant accident in a spent fuel pool and subsequent release of radionuclides using an integral severe accident analysis codeKONICOF/TraineeM. Malicki2021
Vaiarelli, VittorioSevere Accidents Simulations of SMRsEPFL/MScM. Malicki2021
Varbella, AnnaImproved energy-selective cross-section measurements using a compact neutron generatorEPFL/MScR. Adams, G. Perret2021
De Buys Roessingh, VincentCharacterization of a neutron detector efficiency as a function if energyETHZ/MScR. Adams, G. Perret2021
Lartaud, PaulVerification of the conventional approach for full core calculations on hexagonal geometriesETHZ/MScM. Papadionysiou2020
Solans, VirginieOptimisation of canister loading using a neural networkEPFL/MScD. Rochman2020
Roth, BernhardExperimental study of pool scrubbing bubble hydrodynamics in the globule flow regimeETHZ/MScD. Suckow2020
Manohar, KevinThe Proper Orthogonal Decomposition (POD) and its Application to Turbulent Jet DataUniversity of Calgary, Canada/MScR. Kapulla2020
Bellotti, MicheleTechnological and economic strengths of SMRs and
problems of CAREM reactor modeling with TRACE
EPFL/MScK. Nikitin2019
Vazquez, CarlosH2P4: scoping calculations regarding the pressurization of vessels 3 and 4 due to the pool stratificationUPM, Spain/MScM. Andreani2019
King, StephenThe Porous Media ApproachTAMU, USA/MScA. Dehbi2019
Zimmermann, LeaExperimental Characterization of Flow Velocity Development Downstream of Tube BendsETHZ/MScR. Kapulla2019
Kim, Yu-gyungHydrodynamic characterization of pool scrubbing using a wire mesh sensorKONICOF/TraineeP. Papadopoulos2019
Brazell, ChristianOptimization of Spent Nuclear Fuel Storage using a Neural Network and Simulated AnnealingTAMU, USA/MScD. Rochman2019
Ramadane, MohamedDataanalysis of wire-mesh sensor dataETHZ/MScP. Papdopoulos2019
Leisinger, SebastianSynthetic Data for CHF
using Machine Learning Methods
ETHZ/MScR. Mukin2019
Ceder, JoakimElemental iodine retention and hydrodynamic measurements relevant for pool scrubbing and FCVS and modelling with BUSCAKTH/TraineeS. Tietze2018
Jung, ByunghoPWR structures activation forecasts using Monte Carlo neutron transport simulationETHZ-EPFL/MScA. Vasiliev (M. Pecchia)2018
Westlund, M.Monte Carlo simulations of Bowing effects using realistic fuel data in nuclear fuel assembliesUppsala University/MScD. Rochman2018
Di Pierno, L.Development of a CAD Fluid Model for the PKL facilityETHZ/TraineeR. Mukin2017
Li, JiahzhiSimulations of Bowing Effects on Isotopic Inventories for Simplified Pin, Assembly and Full Core ModelsEPFL/MScD. Rochman2016
Savelli, R.Towards extended Validation of PSI BWR FNF Modeling Methodology using KKL Long-Term Irradiation Dosimetry DataETHZ-EPFL/MScA. Vasiliev2015
Janin, G.Development of optimal micro/macroscopic cross-section model for a transport pin-by-pin solverETHZ-EPFL/MScP. Mala2015
Guo, W.Development of TRACE/CAD Methodology for System Code NodalizationETHZ-EPFL/MScI. Clifford2015
Nguyen Van Ho, R.Nuclear Data Uncertainty Propagation for LWR Fuel Assembly LatticesPHELMA-U. Seoul/TraineeO. Leray2015
Ryu, M.Development and Refinements of nTRACERU. Seoul/NE MScS. Canepa (H. Ferroukhi)2015
Yao, H.Thermal-Hydraulic Simulation of Rig-Of-Safety Assessment Tests in Large Scale Test Facility using Updated TRACE CodeETHZ-EPFL/MScI. Clifford2015
Zhang, D.Bundle Reconstruction History Method for Direct Whole Core Calculations with the Code nTRACERETHZ-EPFL/MScS. Canepa2015
Guo, Z.Simulation of Irradiation Damage in Chromium-doped LWR FuelETHZ-EPFL/MScM. Krack (R. Ngayam-Happy)2015
Chunyan, L.Development and Optimization of Fast Solution Algorithms for the Fuel Depletion EquationsETHZ-EPFL/MScP. Mala2014
Perrier, H.Development of Hybrid CASMO/SERPENT Deterministic/Stochastic Fuel Depletion SchemeETHZ-EPFL/MScM. Pecchia (O. Leray, H. Ferroukhi)2014
Dupre, A.Modelling and Validation Enhancements of the PSI Fast Neutron Fluence MCNPX based Computational Scheme using recent KKG Experimental DataETHZ-EPFL/MScA. Vasiliev2014
Rossinelli, L.Assessment of SERPENT for BWR Lattice Modelling and Development of Coupling to SIMULATE-3 CodeETHZ-EPFL/MScM. Hursin (H. Ferroukhi)2014
Zhou, Q.Validation of CFD Solvers for Buoyancy Driven Flows on the basis of ROCOM TestsETHZ-EPFL/MScR. Puragliesi (O. Zerkak)2014
Bogetic, S.Development and Verification of TRACE/PARCS Methodology for analyses of the Swiss ReactorsETHZ-EPFL/MScM. Hursin (A. Dokhane, H. Ferroukhi)2013
Demeshko, M.Development and Verification of CSARMA Noise Analysis Method for BWR CausalityOsaka U./TraineeA. Dokhane (H. Ferroukhi)2013
Li, S.CFD Simulations of Boiling and Natural Circulation in Passice Containment Condenser System PoolsNPIC/IAEA FellowR. Puragliesi2013
nigam, A.Modelling and Validation of COBRA-TF Sub-Channel Code for OECD/NEA BFBT BenchmarkMSc EMINE/TraineeC. Adamson2013
Wicaksono, D.Comparative Study of Monte-Carlo Code Systems for LWR Fuel DepletionETHZ-EPFL/TraineeA. Vasiliev (H. Ferroukhi)2013
Wicaksono, D.Development and Asssement of Advanced Temporal Coupling Schemes for TRACE/S3K AnalysesETHZ-EPFL/MScO. Zerkak2012
Zvoncek, P.Numerical Methods for Nuclear Design Optimization of LWR Assemblies with Inert-Matrix FuelETHZ-EPFL/TraineeW. Wieselquist (H. Ferroukhi)2012
Belaid, S.Modelling and Validation of System Thermal-Hydraulic Codes for Experiments at Integral Test FacilitiesIAEA Fellow/TraineeJ. Freixa2012
Dufresne, A.Development of MCNPX-based Computational Scheme for Reference Numerical Estimations of High-Energy PWR Control Rod Tip FluenceETHZ-EPFL/MScH. Ferroukhi (A. Vasiliev)2011
Gudmundsson, P.Study of minimal requirements for thermal-hydraulics/neutronics mapping schemes in BWR ATWS SimulationsETHZ/MScK. Nikitin2011
Bernatowicz, K.Trend Analysis of PWR Core Modelling AccuracyU. Gdansk/TraineeW. Wieselquist (H. Ferroukhi)2010
Pittarello, R.Monte Carlo analysis of RPV dosimetry experimentsETHZ-EPFL/MScA. Vasiliev2010
Gupta, A.Modelling of KKG Steam Generator using TRACEIIT Kharagpur/MScW. Barten2009
Kalfuss, L.Simulation of a HALDEN-LOCA experiment with the thermohydraulic code TRACETU-Dresden/MScY. Aounallah2008