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Janos BODI / University of Birmingham, UK

Internship study
Development of the CAD models for the European Sodium Fast Reactor
Started in June 2017
On-going

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Emeline BELTJENS / EPFL-ETHZ

MS study
Modelling of the low-void SFR core during ULOF with spatial kinetics
Started in February 2017
On-going

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Fanny VITULLO / EPFL-ETHZ

MS study
Statistical burnup distribution of moving pebbles in HTR-PM reactor
In cooperation with LTH.
Started in February 2017
On-going

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Rodrigo GONZALEZ GONZAGA DE OLIVEIRA / EPFL

PhD study
Modeling of molten salt fast reactor with GeN-Foam
Started in February 2017
On-going

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Boris HOMBOURGER / EPFL

PhD study
Small modular Molten Salt Fast Reactor design for closed fuel cycle
Started in November 2013
On-going


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Simone MAMBELLI / EPFL-ETHZ

Semester project
Designing of the water test facility to mock up sodium boiling using TRACE
Started in October 2016
Completed in December 2016

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Ahmed SHAMA / EPFL-ETHZ

Semester project
Modeling of the SFR wrapper tube mechanical response to a sodium pressure pulse using CAST3M
Started in October 2016
Completed in December 2016

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Emeline BELTJENS / EPFL-ETHZ

Semester project
First assessments of new safety measures for the European Sodium Fast Reactor core using Serpent
Started in October 2016
Completed in December 2016

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Anne-Laurene PANADERO / EPFL

PhD study
Safety assessment of ASTRID Sodium-cooled Fast Reactor in Unprotected Loss of Flow Accident
Started in October 2014
Quit in December 2016

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Eirik Eide Pettersen / Université Paris-Saclay

MS study
Coupled multi-physics simulations of the Molten Salt Fast Reactor using coarse-mesh thermal-hydraulics and spatial neutronics
Started in April 2016
Completed in September 2016

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Kajetan DOBRENKO / Grenoble INP (France) / KTH (Sweden)

Attached MS study
Multi-dimensional modeling of the sodium boiling under Unprotected Loss of Flow conditions in the SFR core
Started in March 2016
Completed in August 2016

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Samuel VAN HAUWAERT / École Centrale Paris

Internship study
Analysis of selected sodium boiling experiments with the TRACE code
Started in March 2016
Completed in August 2016

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Jiadong BAO / EPFL-ETHZ

MS study
Development of the model for the multiphysics analysis of Molten Salt Reactor Experiment using GeN-Foam code
Started in February 2016
Completed in August 2016


Semester project
Assessment of Molten Salt Reactor with cold jet at the core center
Started in October 2015
Completed in December 2015

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Nikoleta VOZAROVA / EPFL-ETHZ

Semester project
Fission product composition in Molten Salt Reactor under various removal parameters
Started in October 2015
Completed in December 2015

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Alzbeta BEDNAROVA / University of Prague

Attached MS study

Modeling of Superphenix Sodium-cooled Fast Reactor core under static and transient conditions
Started in February 2015
Completed in December 2015

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Jeremie NEBES / EPFL-ETHZ

MS study (attachment to CEA Cadarache)
CFD simulations of sodium two-phase flows
Started in February 2015
Completed in November 2015


Semester project
Computational Multi-Fluid Dynamics for Nuclear Engineering
Started in October 2014
Completed in December 2014

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Evzen LOSA / University of Prague

Attached PhD student
U-Pu and Th-U fuel cycle closure
Started in December 2014
Completed in September 2015


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Hyemin KIM / EPFL-ETHZ

MS study
Static and transient analysis of Molten Salt Reactor Experiment using SERPENT-2/TRACE/PARCS codes
Started in January 2015
Completed in August 2015

Semester project
TRACE application to MSR transients initiated by primary, secondary, and tertiary pumps
Started in October 2014,
Completed in December 2014

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Jongsoo CHOE / EPFL-ETHZ

MS study
Empirical Decay Heat Correlations and Fission Products Behavior in MSRs
Started in February 2015
Completed in August 2015

Semester project
Study of the impact of fission products on neutronics and safety of various reactors
Started in October 2014
Completed in December 2014

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Benoit SOUBELET / EPFL-ETHZ

MS study
Time efficient fluid dynamics analysis of sodium fast reactor wire wrapped rod bundles
Started in February 2015
Completed in August 2015

Semester project
Euler-Euler methods for two-phase flow. Local instant and time-averaged formulation.
Started in October 2014
Completed in December 2014

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Matteo ZANETTI / POLIMI

Attached PhD student
Development of the model for the delayed neutron precursors transfer in Molten Salt Reactor
Started in February 2015
Completed in April 2015

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Valerio ARIU / EPFL-ETHZ

MS study
Heat exchanger analysis for innovative Molten Salt Fast Reactors
Started in February 2014
Completed in September 2014

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Miquel BONET / Polytechnic University of Catalonia (UPC)

MS study / ERASMUS
Simulation of sodium flow in a sub-assembly of a sodium fast reactor
Started in February 2014, Completed in August 2014

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Anne-Laurene PANADERO / EPFL-ETHZ

MS study
Static neutronic, thermal-hydraulic and fuel performance analysis of the ASTRID Sodium-cooled Fast Reactor core
Started in February 2014, Completed in August 2014

My Master thesis presents the core static analysis at the End-of-Cycle (EoC) of the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID), which is performed in the framework of FP7 EURATOM ESNII+ project. The goal of this work is to model the ASTRID core at nominal conditions, to learn the main static parameters of the core, and to prepare data for safety analysis. The static analysis is accomplished using the extended FAST code system and it involves neutronics, thermal hydraulics, and fuel thermal mechanics. The static neutronic analysis, performed by means of the SERPENT 2 Monte-Carlo code, provides the core excess reactivity, power distributions, kinetic parameters, reactivity coefficients, and control rod reactivity worth as the main outcomes. In addition, an extensive study is carried out concerning the coolant void worth by analyzing specific sodium voiding scenarii. It can be concluded that the ASTRID peculiar core design features a negative global coolant worth. Within the static thermal-hydraulic study, carried out by employing the TRACE code, the core assemblies division into cooling groups is performed. The respective coolant flow rates and temperatures at the core outlet are determined. Finally, the static thermal-mechanic analysis, which was accomplished by means of the FRED code, gives general insights about the fuel temperature distribution within the fuel pins, gas gap conductance, and fission gas release. As a major outcome of this work, the necessary data to couple neutronics, thermal hydraulics, and thermal mechanics for the further planned transient analyses of the ASTRID core at EoC are provided.

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Mate HALASZ / Budapest University of Technology and Economics (BUTE)

Attached PhD student
Comparison of the FITXS and EQL0D fuel cycle simulation tools on Generation IV GFR and MSR reactors
Started in March 2014, Completed in May 2014

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Valentyn BYKOV / EPFL-ETHZ

Semester work
Molten Salt Fast Reactor blanket characterization
Completed in December 2013

In my project I studied a blanket of a generic two fluid molten salt reactor utilizing fast thorium-uranium cycle. Neutron leakage and Pa-233 neutron absorption were evaluated as a function of the blanket radius. This behavior is important for the optimization of the blanket, which will involve reduction of neutron flux hitting the outer wall and improving the breeding performance. The burnup performance of this generic reactor was also investigated. Namely, the effect of uranium removal from the blanket was analyzed, demonstrating a significant reduction in the production of minor actinides. The uranium vector removed from the core was then investigated for proliferation resistance, using NUREC proliferation resistance metric. The evaluation concluded that while the presence of U-232 increases radiological hazard associated with this uranium, thereby erecting a radiological barrier, it cannot be treated as "self-protecting" based on IAEA and NRC standards, requiring 1 Sv/h at 1 m dose rate. Moreover ideas on how an interested party could reduce this radiological hazard were discussed.

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Matteo ZANETTI / POLIMI

Attached PhD student
Development of innovative methods for the control-oriented modelling of molten salt reactors
Completed in October 2013

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Manuele AUFIERO / POLIMI

Attached PhD student
Development and assessment of innovative simulation tools for circulating-fuel nuclear reactors
Completed in October 2013

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Boris HOMBOURGER / EPFL-ETHZ

MS study
Parametric Lattice Study for Conception of a Molten Salt Reactor in Closed Thorium Fuel Cycle
Completed in June 2013

My Master’s thesis presents a static neutronics study or the core of a thermal (moderated) Molten Salts Reactor. The said study is a continuation of the preliminary work of a semester project, which concluded that two moderation levels were of interest for the design of a Molten Salts Reactor: the "thermal" region, around a 10–15% salt-to-graphite share, and the "fast" region corresponding to a graphite-free core. The present work focuses on the study of heterogeneity and fuel salt composition effects in the lattice, after a literature review and discussion of past and current MSR designs. For this purpose, a simplified equilibrium fuel cycle procedure, EQL0D, was developed on the basis of the PSI-developed EQL3D procedure. The obtained results show that heterogeneity effects can strongly influence the equilibrium fuel cycle composition and criticality.


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Ioannis SAMAROPOULOS / EPFL-ETHZ

MS study
Development of SERPENT based equilibrium fuel cycle procedure EQL0D
Completed in June 2013

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Yonghwy KIM / EPFL-ETHZ

Semester work
Preliminary Analysis of Neutronic Parameters of European Lead Cooled Training Reactor (ELECTRA)
Completed in December 2012

My semester project was focused on studying the neutronics of the European Lead Cooled Training Reactor (ELECTRA) concept. The SERPENT code was employed to develop the full-core and the infinite pin cell models of the ELECTRA and reactivity coefficients and kinetic parameters were calculated and processed by MATLAB. The results were compared with the results from the KTH (Sweden).

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Evzen LOSA / University of Prague

Attached PhD student
U-Pu and Th-U fuel cycle closure
Completed in December 2012

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Levon GHASABYAN / KTH Sweden

MS study
Comparative evaluation of safety and performance parameters of the Gen-IV fast-spectrum cores with the SERPENT Monte-Carlo code
http://kth.diva-portal.org/smash/record.jsf?pid=diva2:604518
Completed in December 2012

In my MS thesis I developed a methodology and a wrapper code, which uses Serpent MC code for generating group constant database, compatible with U.S. NRC PARCS neutronics simulator. The database contains all necessary beginning-of-life (BOL) group constants and their derivatives necessary for transient analyses of fast spectrum reactors. The applicability of the methodology was tested on the European Sodium-cooled Fast Reactor (ESFR) design with an oxide fuel proposed by CEA (France). The results of steady-state and single-effect calculations of the PARCS/TRACE coupled system were compared with those of the Serpent MC code. The k-effective, power peaking factors and safety parameters (such as Doppler constant, coolant expansion coefficient, fuel axial expansion coefficient, diagrid expansion coefficients and control rod worth) calculated by PARCS/TRACE were compared with the Serpent MC calculation results. The comparison indicates overall reasonable agreement between conceptually different (deterministic and stochastic) codes. The new development makes it in principle possible to use Serpent for cross section generation for PARCS to perform transient analyses of fast reactors. The advantages and limitations of this methodology are discussed. The appendix contains Serpent input file of an SFR core, the Matlab code of S2P wrapper and the PARCS input file.

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Dominik HERMANN / ETHZ

MS study
Development of a new method for dynamic reactivity decomposition
Completed in September 2012

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Kaichao SUN / EPFL

PhD study
Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics
Completed in September 2012
http://dx.doi.org/10.5075/epfl-thesis-5480

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Vladimir BRANKOV / EPFL

MS study
Approaching the equilibrium closed fuel cycle in advanced fast reactors
Completed in July 2012

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Aurelia CHENU / EPFL

PhD study
Single- and Two-Phase Flow Modelling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors
Completed in October 2011
http://dx.doi.org/10.5075/epfl-thesis-5172

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Carlo FIORINA / POLIMI

Attached PhD student
Thorium-uranium equilibrium fuel cycle analysis for the Generation-IV Lead-cooled Fast Reactor with the EQL3D procedure
Completed in September 2011

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Mercedes ALONSO / EPFL

MS student
Development of a full-core ERANOS Model and neutronic analysis of the BN-600 Fast Reactor Core Mock-up at the BFS-2 zero-power facility
Co-supervision: Dr. G. Girardin (EPFL)
Completed in August 2011

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Maxime PEQUIGNOT / Grenoble INP PHELMA

Summer Internship
Analysis of the dynamic behaviour of the SUPERPHENIX core using the FAST code system
Completed in August 2011

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Leif MICHELSSON / EPFL

Semester work
Neutronic Analysis of the CROCUS Reactor at EPFL with the deterministic System ERANOS 2.2
Co-supervision: Dr. G. Girardin (EPFL)
Completed in June 2011

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Kristina YANCEY / Texas A&M University

Fulbright fellow study
Development of Comprehensive Model for Generation-IV Lead-cooled Fast Reactor
Completed in June 2011

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Joseph SALIBA / EPFL

MS study
Comparative decomposition analysis of reactivity effects for the main Gen-IV fast reactors
Completed in April 2011

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Robert ADAMS / ETHZ

MS study
Coupled Neutronic/Thermal-hydraulic Simulation of Selected PHENIX End-of-life Tests
Completed in September 2010

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Aaron EPINEY / EPFL

PhD study
Improvement of the Inherent and Passive Safety Characteristics of Generation IV Gas-cooled Fast Reactor
Completed in September 2010
http://dx.doi.org/10.5075/epfl-thesis-4792

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Claudia CODAU / Grenoble INP PHELMA

Summer internship
Comparative Analysis of Oxide and Carbide Fuelled Sodium-cooled Fast Reactor with ERANOS
Completed in June 2010

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Florian REITERER / ETHZ

Semester work
Uncertainty propagation in dynamic TRACE calculations for Gen-IV SFR
Completed in June 2010

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Arnau PONT RIBAS / ETHZ

MS study
Simulation of CABRI loss-of-flow experiments with the TRACE/FRED codes
Completed in March 2010

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Christine KLAUSER / EPFL

MS study
Neutronic Analysis of the European Gas-Cooled Fast Reactor Demonstrator ALLEGRO and its Validation via Monte Carlo TRIPOLI Calculations
Co-supervision: Dr. G. Girardin (EPFL)
Completed in March 2010

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Ondrej HUML / University of Prague

3-week internship
Development of MCNP Model for Sodium-cooled Fast Reactor
Completed in October 2009

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Bruno COLIN / Grenoble INP PHELMA

Summer internship
Development of the TRACE Model for Transient Analysis of the XADS System
Completed in August 2009

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Claudio FELICIANI / EPFL-ETHZ

Semester work
A TRACE Model of the SALSA Air Loop
Completed in May 2009

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Gaetan GIRARDIN / EPFL

PhD study
Development of the Control Assembly Pattern and Dynamic Analysis of the Generation IV Large Gas-cooled Fast Reactor (GFR)
Completed in May 2009
http://dx.doi.org/10.5075/epfl-thesis-4437

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Petr PETKEVICH / EPFL

PhD study
Development and Application of an Advanced Fuel Model for the Safety Analysis of the Generation IV Gas-cooled Fast Reactor
Completed in August 2008
http://dx.doi.org/10.5075/epfl-thesis-4180