Gas-cooled Fast Reactor (GFR) 

• Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor. –Aaron Simon Epiney, EPFL, Lausanne (2010) 

• Development of the control assembly pattern and dynamic analysis of the Generation IV large gas-cooled fast reactor (GFR), –Gaetan Girardin, EPFL, Lausanne (2009)

• Development and application of an advanced fuel model for the safety analysis of the Generation IV gas-cooled fast reactor. –Petr Petkevich, EPFL, Lausanne (2008)

Lead Cooled Fast Reactor (LFR)

• Improvement of performance of steel in liquid lead environment by use of coatings, K. Havlikova, CVUT, Prague, (2014).

• Benchmarking Thermal-hydraulic analysis code RELAP5/MOD3.2.2 beta for lead bismuth eutectic alloy on Nacie facility tests of natural and gas enhanced circulation, D.Balestri, PoliMi, (2014).

• CFD-based analysis of the pool design of a GEN-IV Lead-cooled Fast Reactor, .. Sormani, PoliMi, (2014).

• Behaviour of the steel T91 in liquid lead environment, J. Klečka, CVUT, Prague (2013).

• Application of advanced thermal hydraulic simulation codes for the analysis of heavy liquid metal flows in the ADS reactor concept MYRRHA, S. Palazzo, UniPisa (2013).

• CFD thermal hydraulic analysis of HLM cooled rod bundles, M. Scarpa, UniPisa (2013).

Molten Salt Reactor (MSR) 

• Etudes préliminaires de sûreté du réacteur à sels fondus MSFR, Mariya Brovchenko, Grenoble Institute of Technology, France (2013)

• Design of Complex Systems to Achieve Passive Safety: Natural Circulation Cooling of Liquid Salt Pebble Bed Reactors, R. Scarlat, University of California, Berkeley (2012)

• Influence du retraitement physico-chimique du sel combustible sur le comportement du MSFR et sur le dimensionnement de son unité de retraitement,  Xavier Doligez, Grenoble Institute of Technology, France (2010)

• Cycle Thorium et Réacteurs à Sel Fondu: Exploration du champ des Paramètres et des Contraintes définissant le Thorium Molten Salt Reactor,  Ludovic Mathieu, Grenoble Institute of Technology, France (2005)

Sodium-cooled fast reactor system (SFR)

• Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics, Kaichao Sun, EPFL, Lausanne (2012) 

• Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors, Aurélia Chenu, EPFL, Lausanne (2011)

Supercritical-Water cooled Reactor (SCWR)

• CFD-Simulationen turbulenter konvektiver Strömungen bei überkritischen Drücken, C. Kunik, Dissertation, Karlsruhe Institute of Technology  (2012)

• Thermohydraulische Auslegung des Zwischenüberhitzers eines High Performance Light Water Reactors, H. Herbell, Dissertation, Karlsruhe Institute of Technology, KIT Scientific Reports, KIT-SR 7595 (2011)

• Simulation des Dampf-Wasserkreislaufs und der Sicherheitssysteme eines High Performance Light Water Reactors, M. Schlagenhaufer, Dissertation, Karlsruhe Institute of Technology, KIT Scientific Reports, KIT-SR 7582 (2011)

• Modellierung des Strömungsverhaltens in einem HPLWR-Brennelement mit Drahtwendelabstandshaltern,S.R. Himmel, Dissertation, University of Stuttgart 2009, FZKA 7468 (2009)

• Fluid dynamic design of complex mixing chambers, A. Wank, Dissertation, University of Karlsruhe, Forschungszentrum Karlsruhe, FZKA 7520 (2009)

• Multi-scale, coupled reactor physics / thermal-hydraulic system and applications to the HPLWR 3 pass core, L. Monti, Dissertation, University of Karlsruhe, FZKA 7521 (2009)

• Design of a supercritical water-cooled reactor - pressure vessel and internals,K. Fischer, Dissertation, University of Stuttgart 2008, FZKA 7429 (2008)

• Wärmeübergang von Wasser in vertikalen Rohrströmungen bei überkritischem Druck, M.F. Loewenberg, Dissertation, University of Stuttgart, FZKA 7320 (2008)  
  

• Stability Analysis of the High Performance Light Water Reactor, T. Ortega Gomez, Dissertation, University of Karlsruhe, FZKA 7432 (2008)

• Analyse eines Druckwasserreaktors mit überkritischem Wasser als Kühlmittel, B. Vogt, Dissertation, University of Stuttgart, Forschungszentrum Karlsruhe, FZKA 7428 (2008)

• Auslegung eines Brennelements für einen Leichtwasserreaktor mit überkritischen Dampfzuständen, J. Hofmeister, Dissertation, University of Stuttgart, Forschungszentrum Karlsruhe FZKA 7248 (2006)

• Coupled neutronics / thermal-hydraulics analysis of a high performance light water reactor fuel assembly, C. Waata, Dissertation, University of Stuttgart, Forschungszentrum Karlsruhe. FZKA 7233 (2006)

Very-High-Temperature Reactor (VHTR)

• Thermal Hydraulic Analysis of an Experimental Reactor Cavity Cooling, System with Water: Performance and Stability, D. Lisowski, University of Wisconsin - Madison (2013) 

• Granular Dynamics in Pebble Bed Reactor Cores, M. Laufer, University of California, Berkeley (2013)

• Sustainability and Efficiency Improvements of Gas-Cooled High Temperature Reactors, A. Marmier, Technische Universiteit Delft (2012)

• Design, Fabrication, Performance Testing, and Modeling of Diffusion Bonded Compact Heat Exchangers in a High-Temperature Helium Test Facility, Sai K. Mylavarapu, Ohio State University (2011)

Full details: TEMpump postdoc-en