Constrained geometric optimization of immersed boundaries for thermal-hydraulic simulations of turbulent flow in a finite-volume approach
The technical issue underpinning this thesis topic is the mitigation of the consequences of a loss of primary coolant accident in a pressurized water reactor with loops. It is of the utmost importance to minimize the flow of water leaving the vessel and to manage the available cold water reserves for safety injections as effectively as possible, in order to prevent or delay core flooding, overheating, and possible core degradation. To this end, the use of passive devices operating on the principle of hydraulic diodes, such as vessel flow limiters or advanced accumulators, is being considered. The subject of this thesis is the geometric optimization of this type of device, described by an immersed boundary, in order to maximize its service efficiency.
Several recent theses have shown how to introduce the Penalized Direct Forcing (PDF) immersed boundary method into the TRUST/TrioCFD software, under various spatial discretizations and for laminar and turbulent regimes. Similarly, they have ruled on the possibilities of deterministic geometric optimization in the finite-element context during simulations, based on the use of the PDF method.
After a bibliographic study of this kind of method, we will focus on the possibilities of implementation in finite volume discretization, the consideration of constraints, and the comparison to reference calculations. The latter will be carried out on academic and industrial configurations (accumulators and flow limiters).
The doctoral student will work in a R&D unit on innovative nuclear system within the IRESNE Institute (CEA Cadarache. He will develop skills in fluid mechanics and numerical methods.
Experimental Investigation and DEM Simulation of Actinide Powder Segregation During Transfer Processes
The fabrication of nuclear fuels based on actinide oxides (UO2, PuO2) involves numerous powder-handling operations, during which segregation phenomena may occur. These phenomena—arising from differences in particle size, shape, density, or surface condition—directly affect the homogeneity of the mixtures and, consequently, the quality and consistency of the resulting fuel pellets. Controlling these effects is therefore a major industrial challenge to ensure both process robustness and final product conformity.
This PhD project aims to deepen the understanding of the mechanisms driving powder de-mixing of UO2 during transfer stages, particularly during vibratory conveyor transport and gravitational discharge. The main scientific objective is to establish the relationship between the physical and rheological properties of the powders, the process operating conditions, and the intensity of the observed segregation phenomena. The work will combine experimental studies and numerical simulations using the Discrete Element Method (DEM) to identify the material and process parameters influencing segregation. Experimental setups will be developed to characterize the powders and quantify the degree of de-mixing, while simulations will serve to validate and extrapolate the experimental observations.
Conducted at CEA Cadarache, within the Uranium Fuel Laboratory (LCU) of the Institute for Research on Nuclear Systems for Low-Carbon Energy Production (IRESNE), and in collaboration with the TIMR laboratory at UTC, this project will provide recommendations to limit segregation during industrial operations and improve the prediction of segregation tendencies in powder mixtures, particularly in cohesive actinide powders.
The PhD candidate will disseminate their findings through publications and conference presentations. They will also have the opportunity to learn and refine several transferable techniques applicable to a wide range of materials science and engineering contexts.In particular, the issues related to the physics of granular materials, which form the core of this thesis, are of significant industrial relevance and are shared by many other sectors handling powders, such as the pharmaceutical, food processing, and powder metallurgy industries.
Nucleate boiling within porous deposits: study of the coupling between coolant composition and capillary vaporization
In the search of the optimal combination of low-carbon energy sources to address the challenge of climate change, nuclear energy plays a crucial role alongside intermittent renewable energies. In this context, the performance and safety of Pressurized Water Reactors (PWRs), which make up the French nuclear fleet, remain an active and high-value research area.
In these reactors, a subcooled nucleate boiling regime can occur, particularly when the local temperature of the coolant exceeds its saturation temperature. This wall boiling promotes the formation of porous deposits of metallic oxides. Within the porosities of these deposits, gas nuclei can be trapped and lead to the onset of nucleate boiling on these surfaces. The vapor formed through a wick boiling or capillary vaporization mechanism then escapes through the chimneys of the deposit. The chemistry of the coolant affects not only the thermodynamic properties of the fluid (such as saturation temperature and latent heat) but, more importantly, its interfacial properties (surface tension and solid/liquid/gas contact angles). These interfacial properties directly control the capillary forces within the deposits, and thus the onset and dynamics of subcooled boiling. As of today, the influence of coolant chemistry on the initiation and development of subcooled nucleate boiling within porous heated surfaces remains poorly understood.
The objective of this PhD is therefore to systematically study the coupled influence of coolant composition and capillary vaporization on nucleate boiling within porous substrates heated by conduction.
The research will follow an experimental approach to investigate how coolant chemistry affects surface tension and contact angles, in order to characterize fluid wetting on idealized porous substrates. Subcooled convective boiling experiments will also be conducted, with the phenomena characterized by shadowgraphy and fiber-optic thermometry.
The PhD will take place within the Thermal Hydraulics of Core and Circuits Laboratory (LTHC) and the Contamination Control, Coolant Chemistry and Tritium Management Laboratory (LMCT) at CEA IRESNE (Cadarache, France). The work will be supervised by Prof. Benoît Stutz of the University of Savoie Mont Blanc. Throughout this project, the doctoral student will develop expertise in interfacial physico-chemistry and two-phase thermohydraulics through the observation, characterization, and modeling of complex multiphysics phenomena.
Three-Dimensional Fine Measurements of Boundary Layers in Turbulent Flows within PWR Fuel Assemblies
The production of electricity through nuclear energy is a key pillar of the energy transition due to its low carbon footprint. In a continuous effort to improve safety and performance, the development of new knowledge and tools is essential.
Fuel assemblies, which are components of a reactor core, face various challenges involving thermo-hydraulic phenomena. These include flow-induced vibrations, power transmission associated with critical fluxes, and fluid-structure interactions in cases of assembly deformation or seismic excitation. In all these situations, the behavior of the fluid near the wall plays a crucial role. The use of Computational Fluid Dynamics (CFD) allows for the simulation of these phenomena with the goal of obtaining predictive tools. The experimental validation needs required by today's simulations push classical measurement techniques to their limits. There is a strong need for refined experimental data in both time and space on complex geometries.
This doctoral project aims to address this need by leveraging the latest advancements in optical measurements for turbulent flows. By combining index matching techniques, panoramic cameras, and Particle Tracking Velocimetry (PTV), it is possible to measure the velocity field in a representative volume (approximately 1 cm³) with a spatial density of around 10 micrometers. This allows for the simultaneous measurement of flow in the boundary layer and the hydraulic channel.
The thesis will primarily be conducted at the Hydromechanics Laboratory (LETH) at the IRESNE Institute (CEA Cadarache) and will involve collaboration with the Thermo-Fluids Lab at George Washington University. Travel to the USA will be required.
Development of an autonomous module for glass alteration modeling and its coupling with reactive transport codes
In the context of the sustainable and safe use of nuclear energy within a carbon-free energy mix that addresses the climate emergency, managing radioactive waste inventory is a priority concern. The alteration of nuclear glass therefore directly affects the long-term assessment of the safety of geological storage of this waste. Understanding and simulating these processes is therefore a major scientific, industrial, and societal challenge. Existing models, such as GRAAL2 [1] developed at the CEA, capture the passivation mechanisms governing glass alteration, bridging nanometric processes to mesoscopic scale through mesoscopic-scale kinetic laws used in reactive transport codes (RTC).
This PhD aims to develop an autonomous glass module (GM) based on the GRAAL2 model, capable of computing glass alteration kinetics and interfacing with different reactive transport codes (HYTEC, CRUNCH…). The main objectives are: (i) to design and implement a kinetic module, (ii) to develop a coupling interface managing information exchange with RTC, (iii) to define and carry out numerical validation campaigns on reference test cases for both the GM and the coupler, and (iv) to perform sensitivity and uncertainty analyses to identify the key parameters controlling glass behavior in a multi-material context (glass, iron, clay).
The PhD will take place at the Laboratory for Environmental Transfer Modeling (LMTE), within the IRESNE Institute (CEA, Cadarache site, Saint-Paul-lès-Durance). The project will provide the PhD candidate with cross-disciplinary skills in geochemistry, multiphysics coupling, and scientific software development, opening career opportunities in both academic research and nuclear/environmental engineering.
References:
[1] M. Delcroix, P. Frugier, E. Geiger, C. Noiriel, The GRAAL2 glass alteration model: initial qualification on a simple chemical system, Npj Mater Degrad 9 (2025) 38. https://doi.org/10.1038/s41529-025-00589-4.
Proximal primal-dual method for joint estimation of the object and of unknown acquisition parameters in Computed Tomography.
As part of the sustainable and safe use of nuclear energy in the transition to a carbon-free energy future, the Jules Horowitz research reactor, currently under construction at the CEA Cadarache site, is a key tool for studying the behaviour of materials under irradiation. A tomographic imaging system will be exploited in support of experimental measures to obtain real-time images of sample degradation. This imaging system has extraordinary characteristics due to its geometry and to the size of the objects to be characterized. As a result, some acquisition parameters, which are essential to obtain a sufficient image reconstruction quality, are not known with precision. This can lead to a significant degradation of the final image.
The objective of this PhD thesis is to propose methods for the joint estimation of the object under study and of the unknown acquisition parameters. These methods will be based on modern convex optimization tools. This thesis will also explore machine learning methods in order to automate and optimize the choice of hyperparameters for the problem.
The thesis will be carried out in collaboration between the Marseille Institute of Mathematics (I2M CNRS UMR 7373, Aix-Marseille University, Saint Charles campus) and the Nuclear Measurement Laboratory of the IRESNE institute of the French Alternative Energies and Atomic Energy Commission (CEA Cadarache, Saint Paul les Durance). The doctoral student will work in a stimulating research environment focused on strategic questions related to non-destructive testing. He or she will also have the opportunity to promote his or her research work in France and abroad.
Modeling of Critical Heat Flux Using Lattice Boltzmann Methods: Application to the Experimental Devices of the RJH
LBM (Lattice Boltzmann Methods) are numerical techniques used to simulate transport phenomena in complex systems. They allow modeling fluid behavior in terms of particles moving on a discrete grid (a "lattice"). Unlike classical methods, which solve the differential equations of fluids directly, LBM simulate the evolution of the fluid particle distribution functions in a discrete space using propagation and collision rules.
The choice of lattice in LBM is a crucial step, as it directly affects the accuracy, efficiency, and stability of the simulations. The lattice determines how fluid particles interact and move through space, as well as how the discretization of space and time is performed.
LBM methods exhibit a natural parallelism because the computations at each grid point are relatively independent. Compared to classical CFD methods, LBM can better capture certain complex phenomena (such as multiphase, turbulent, or porous media flows) because they rely on a mesoscopic modeling of the fluid, directly derived from particle kinetics, rather than on a macroscopic resolution of the Navier–Stokes equations. This approach allows for a finer representation of interfaces, nonlinear effects, and local interactions, which are often difficult to model accurately using classical CFD methods. LBM therefore enables the capture of complex phenomena at a lower computational cost. Recent studies have notably shown that LBM can reproduce the Nukiyama boiling curve (pool boiling) and, consequently, accurately calculate the critical heat flux. This flux corresponds to a bulk boiling, known as a boiling crisis, which results in a sudden degradation of heat transfer.
The critical heat flux is a crucial issue for the experimental devices (DEX) of the Jules Horowitz Reactor, as they are cooled by water either via natural convection (fuel capsule-type devices) or forced convection (loop-type devices). Thus, to ensure the proper cooling of the DEX and reactor safety, it is essential to verify that the critical heat flux is not reached within the studied parameter range. It must therefore be determined with precision. Previous studies conducted on a fuel-capsule-type DEX using the NEPTUNE-CFD code (classical CFD methods) have shown that modeling is limited to regions far from the critical heat flux. In general, flows with high void fractions (greater than 10%) cannot be easily resolved using classical CFD approaches.
The student will first define a lattice to apply LBM to a RJH device under natural convection. They will consolidate the results obtained for the critical heat flux on this configuration by comparing them with available data. Finally, exploratory calculations under forced convection (laminar to turbulent regime) will be conducted.
The student will be hosted at the IRESNE institute.
Impact of the porosity on the MOX (U,Pu)O2 fuel
The nuclear fuel performances depend on their thermomecanical behaviors and, therefore, their thermal conductivity. This property varies significantly with high porsity levels especially in mixed oxided (composed of uranium and plutonium) used in fast ractors.
The aim of this thesis is to assess the impact of the pore qualities and shapes on the thermal conductivity on fissile materials and to propose a thermal conductivity law depending of the quantity, the length, the shape and the interconnectivity of its porosity. To reach this goal, recent measures on thermal properties are in progress by laser heating, allowing a better understanding of the fuel behavior in temperature ranges mostly unexplored like very high temperatures (until 2500°C), are in progress in the european research center (JRC) in Karlsruhe. These measures are performed on materials with different microstructures. These measures will be interpreted from thermograms and compared to simulation results (image analysis, converting 2D image in a 3D problem, TM-FFT)[1].
This thesis will take place in the French Institute for Research on Nuclear Systems for Low-Carbon Energy production (IRESNE) in the Expertise and Validation on multi-fuel Applications Laboratory (LEVA). LEVA is part of the Fuel Study and Simulation Department and its missions consist of :
- Answer to industrial demands by providing studies ;
- Validation of the Scientific Calculation Tools (OCS) of the PLEIADES plateform ;
- Enhance the fuel behavior understanding ;
- Manage the Fuel databases.
Finally, the collaboration with JRC Karlsuhe will be a chance to work within an international framework which also is a strenght of LEVA.
This work will be valorized through conferences participations and publications in peer-reviewed journals. Furthermore, the PhD student will have the possibility to acquire or strengthen some technical skills (experimental data interpretation, modelling) applicable in various fields of material science and engineering.
[1] This work forms a natural extension of the PHD thesis "The Thermal conductivity of mixed oxide fuel (MOX) : effect of temperature, elementary chemical composition, microstructure and burn-up in reactor" - TEL - Thèses en ligne.
Experimental study of the behavior of fission gases in Fast Neutron Reactor fuels irradiated at low power.
With the emergence of new start-ups in the nuclear field, it is essential to extend the validation basis for Fast Neutron Reactor (FNR) fuel performance codes to lower linear power operating regimes, an area that has yet to be fully explored.
Given the lower temperatures reached in the fuel, the microstructure induced by irradiation is completely different from what is typically observed at higher linear power (formation of a central hole, columnar grains, etc.). These lower operating temperatures also lead to a decrease in fission gas release (FGR), which can cause significant gas swelling of the fuel. At the same time, low operating temperatures can also lead to an increase in the density of defects (dislocations) induced during irradiation (lower defect annealing efficiency), resulting in an indirect increase in fuel swelling.
It is therefore important to determine the density of dislocations in the fuel, as their ambivalent role shows that they can slow down the release of gases by trapping them and promoting their storage in intragranular bubbles, while also facilitating their migration if they form a connected network.
In order to improve our understanding of the phenomena involved and the models of fuel swelling under irradiation, it is essential to have experimental results such as the densities and sizes of Fission Gas (FG) bubbles and the densities of dislocations in these operating regimes.
The Laboratory for Fuel Characterization and Property Studies (LCPC) within the Research Institute for Nuclear Systems for Low-Carbon Energy Production (IRESNE), to which the PhD student will be affiliated, is equipped with state-of-the-art instruments recently acquired (TEM, SEM-FIB, SIMS, EPMA, XRD) for the study of irradiated materials allowing him to develop advanced experimental skills within the specific context of a Basic Nuclear Installation. This work will be carried out in close collaboration with the teams responsible for developing the multiphysics scientific computing tools of the PLEIADES software platform. It is clear that the skills acquired during the thesis will be valuable in a future career in both academia and industry. The doctoral student will also be able to promote their work to the international academic community and the industrial world through oral presentations and peer-reviewed articles.
Modeling and dynamic studies of a space Nuclear Electric Propulsion system
Nuclear technology is key to enabling the establishment of scientific bases on the Moon or Mars, or for exploring deep space. Its use can take several forms (RTG, NTP among others), but this thesis focuses on Nuclear Electric Propulsion (NEP): heat produced by a nuclear reactor is converted into electricity to power an ionic propulsion engine. Various concepts have been studied in the past (PROMETHEUS, MEGAHIT and DEMOCRITOS, typically for Jupiter satellite exploration missions), while currently design studies are underway at CEA for a 100 kWe nuclear-electric NEP system.
The system of interest combines several specific design choices: uranium nitride fuel, direct gas cooling (helium-xenon mixture) and energy conversion system based on a Brayton cycle, as well as waste heat evacuation through thermal radiation. These choices address requirements to minimize mass and volume, and to ensure performance and reliability for the duration of the scientific mission. Analysis of the dynamic behavior of the nuclear-electric system is therefore crucial for project success. However, the issue of transient modeling of a complete spatial nuclear-electric system is very poorly addressed in the state of the art, especially for NEP.
The thesis objectives are therefore to research and develop physical models adapted to a NEP system, to propose an approach for their validation, and finally to implement them to analyze the dynamic behavior of the reactor and contribute to improving its design. Several mission phases will be studied: reactor startup in space, power variation transients for the ionic propulsion engine, reactor response in case of failure, and its potential shutdown with the problem of safe residual power evacuation.
The thesis will be conducted at IRESNE Institute (CEA Cadarache), in a stimulating scientific environment, and integrated into a team designing innovative nuclear reactors. CNES will also be involved in monitoring the work, particularly to define the ionic propulsion engine characteristics and exploration missions of interest for the nuclear-electric system. The thesis topic, combining modeling, fluid mechanics, thermodynamics, neutronics, and space mechanics, will lend itself to scientific communication and allow the development of key skills for an academic or industrial career.