Stabilization of secondary phases in nanoreinforced ferritic steels: High-throughput screening approach of chemical compositions
Ferritic steels reinforced by oxide dispersion strengthening (ODS) are considered for use in 4th Generation and fusion nuclear reactors due to their excellent thermomechanical properties and stability under irradiation. However, these steels are weakened by secondary phases resulting from complex interactions between alloying elements and interstitials (C, N, O) introduced during their processing. Some alloying elements (such as Nb, V, Zr, Hf) could potentially stabilize these undesirable phases and mitigate their detrimental effects on the mechanical behavior of ODS steels. This thesis aims to develop a high-throughput screening method to identify optimal alloy compositions by combining rapid fabrication and characterization techniques. The PhD student will synthesize various compositions of ODS steels through powder metallurgy and carry out chemical, microstructural, and mechanical characterizations. This work will enhance the understanding of interstitial stabilization mechanisms and propose effective methodologies for characterizing new materials. The PhD student will gain in-depth knowledge in metallurgy and data processing, providing opportunities in industry, nuclear start-ups, and research.
Exploring the High-Frequency fast Electron-Driven Instabilities towards application to WEST
In current tokamaks, the electron distribution is heavily influenced by external heating systems, like Electron Cyclotron Resonance Heating (ECRH) or Lower Hybrid (LH) heating, which generate a large population of fast electrons. This is expected also in next-generation tokamaks, such as ITER, where a substantial part of input power is deposited on electrons. A significant population of fast electrons can destabilize high-frequency instabilities, including Alfvén Eigenmodes (AEs), as observed in various tokamaks. However, this phenomenon remains understudied, especially regarding the specific resonant electron population triggering these instabilities and the impact of electron-driven AEs on the multi-scale turbulence dynamics in the plasma complex environment.
The PhD project aims to explore the physics of high-frequency electron-driven AEs in realistic plasma conditions, applying insights to WEST experiments for in-depth characterization of these instabilities. The candidate will make use of advanced numerical codes, whose expertise is present at the IRFM laboratory, to analyze realistic plasma conditions with fast-electron-driven AE in previous experiments, to grasp the essential physics at play. Code development will also be necessary to capture key aspects of this physics. Once such a knowledge is established, predictive modeling for the WEST environment will guide experiments to observe these instabilities.
Based at CEA Cadarache, the student will collaborate with different teams, from the theory and modeling group to WEST experimental team, gaining diverse expertise in a stimulating environment. Collaborations with EUROfusion task forces will further provide an enriching international experience.
Enhanced Quantum-Radiofrequency Sensor
Through the Carnot SpectroRF exploratory project, CEA Leti is involved in radio-frequency sensor systems based on atomic optical spectroscopy. The idea behind the development is that these systems offer exceptional detection performance. These include high sensitivity´ (~nV.cm-1.Hz-0.5), very wide bandwidths (MHz- THz), wavelength-independent size (~cm) and no coupling with the environment. These advantages surpass the capabilities of conventional antenna-based receivers for RF signal detection.
The aim of this thesis is to investigate a hybrid approach to the reception of radio-frequency signals, combining atomic spectroscopy measurement based on Rydberg atoms with the design of a close environment based on metal and/or charged material for shaping and local amplification of the field, whether through the use of resonant or non-resonant structures, or focusing structures.
In this work, the main scientific question is to determine the opportunities and limits of this type of approach, by analytically formulating the field limits that can be imposed on Rydberg atoms, whether in absolute value, frequency or space, for a given structure. The analytical approach will be complemented by EM simulations to design and model the structure associated with the optical atomic spectroscopy bench. Final characterization will be based on measurements in a controlled electromagnetic environment (anechoic chamber).
The results obtained will enable a model-measurement comparison to be made. Analytical modelling and the resulting theoretical limits will give rise to publications on subjects that have not yet been investigated in the state of the art. The structures developed as part of this thesis may be the subject of patents directly exploitable by CEA.
Study and characterization of nucleate boiling in reactor conditions
In the context of the energy transition and the place of nuclear power in the energy mix, controlling safety and optimizing reactor performance represent imperative research areas with high added value. In this context, boiling at high pressure and temperature is a key issue for water reactors widely deployed in France and around the world.
The many works on this subject carried out in the past show their limitation in terms of representativeness and present certain gaps (e.g. the evolution of the topology of the flow at high pressure). The proposed subject therefore concerns the characterization of nucleate boiling for a wide range of pressure and temperature conditions, and more particularly the study of the coupling between the thermal properties of the wall and the flow (bubble sizes, detachment frequency, local void ratio, etc.). This work will also provide data relating to boiling models that can be used in CFD-type numerical calculation tools. Direct visualization of the flow using portholes (a process successfully implemented in the past), coupled with the use of stereological tools (in collaboration with the LRVE at CEA Marcoule) and associated with a measurement of the wall temperature, should make it possible to achieve the set objectives. These measurements carried out under representative reactor conditions (thermohydraulic conditions, real fluid, representative heating surface) make this study original compared to existing work.
After an initial critical literature review, the PhD student will design and test the experimental devices before implementing them through test campaigns on a dedicated installation. The results collected will be analyzed, interpreted, compared with existing models and may, if necessary, lead to the construction of new models. This thesis will take place on the POSEIDON experimental platform, dedicated to flows studies, and will allow the doctoral student to approach all phases of a research project, from the design of experimental devices to the interpretation of the results obtained.
Kinetics of segregation and precipitation in Fe-Cr-C alloys under irradiation : coupling magnetic, chemical and elastic effects
Ferritic steels are being considered as structural materials in future fission and fusion nuclear reactors. These alloys have highly original properties, due to the coupling between chemical, magnetic and elastic interactions that affect their thermodynamic properties, the diffusion of chemical species and the diffusion of point defects in the crystal. The aim of the thesis will be to model all of these effects at the atomic scale and to integrate them into Monte Carlo simulations in order to model the segregation and precipitation kinetics under irradiation, phenomena that can degrade their properties in use. The atomic approach is essential for these materials, which are subjected to permanent irradiation and for which the laws of equilibrium thermodynamics no longer apply.
The candidate should have a good background in statistical physics or materials science, and be interested in numerical simulations and computer programming. The thesis will be carried out at CEA Saclay's physical metallurgy laboratory (SRMP), in a research environment with recognised experience in multi-scale modelling of materials, with around fifteen theses and post-doctoral contracts in progress on these topics.
A Master 2 internship on the same subject is proposed for spring 2025 and is highly recommended.
Impact forces under flow : water gap effect on the dynamics of a nuclear component
In the framework of the contribution of nuclear power to a decarbonized energy mix, reactors safety is of paramount importance. In the event of an earthquake, dynamic loads experienced by a reactor core could lead to collisions between fuel assemblies. The presence of turbulent flow inside the core has a significant effect on the dynamic behaviour of the assemblies. Recent tests have revealed an additional effect of the flow on impact forces between structures, possibly caused by a high-speed fluid sheet phenomenon.
The objective of this thesis, divided into three parts, is to understand and characterise this high-speed fluid sheet phenomenon in the specific case of a fuel assembly geometry.
A first part will be dedicated to CFD simulations taking into account the deformation of the fluid domain mesh using the Arbitrary Lagrange-Euler (ALE) method [1]. In addition, ambitious experimental campaigns will allow measuring, as close as possible to the impact, the effect of structures displacement on flow velocity field (using optical methods such as Particle Image Velocimetry [2]) and the resulting impact forces. The findings will be translated into an analytical modelling of the phenomenon.
The candidate will be hosted by the laboratory leading work on fluid-structure interactions within CEA Cadarache research centre. He/she will be integrated into a research environment with international outreach (collaboration with George Washington University - USA), will publish his/her research outcomes in leading journals in the field, and will participate in international conferences.
[1] A computationally efficient dynamic grid motion approach for Arbitrary Lagrange-Euler simulations, A. Leprevost, V. Faucher, and M. A. Puscas, Fluids, 8(5), 2023.
[2] Longo, L., Capanna, R., Ricciardi, G., & Bardet, P. (2024). Threshold of Keulegan-Carpenter instability within a 6 × 6 rod bundle, Experimental Thermal and Fluid Science
Sub-Grid modelling of interfacial heat and mass transfers applied to condensation of bubble swarms
To assess the safety of nuclear power plants, the CEA develops and uses multi-scale thermohydraulic simulation tools. The application of CFD to two-phase flows is limited because it requires many models that are difficult to determine. Among our other tools, direct numerical simulations (DNS) with resolved interfaces provide reference data inaccessible by experimental means. This is for example the case of bubble swarms, where heat and mass transfers are influenced by complex collective effects.
In order to reduce the cost of these DNS simulations, we recently developed an approach [1] which shows promising results: it consists of coupling a fine resolution of thermal transfers at the liquid-vapor interfaces to a far field calculated on a less resolved mesh. To broaden the application of this method to more industrial cases, it is necessary to take into account collisions between bubbles and to adapt the model to the phase change.
During this thesis, we propose to start with this physical modeling work and its implementation in C++ in our open-source simulation code TRUST/TrioCFD [2]. Next, we will use this new capacity to carry out a parametric study and an in-depth physical analysis of the phenomena which would ultimately lead to an improvement in heat transfer models in industrial codes.
[1] M. Grosso, G. Bois, A. Toutant, Thermal boundary layer modelling for heat flux prediction of bubbles at saturation: A priori analysis based on fully-resolved simulations, International Journal of Heat and Mass Transfer, Vol 222, 2024, https://doi.org/10.1016/j.ijheatmasstransfer.2023.124980
[2] Trio_CFD webpage : http://triocfd.cea.fr/recherche/modelisation-physique/two-phase-flows
Elementary characterization by neutron activation for the circular economy
As part of the circular economy, a major objective is to facilitate the recycling of strategic materials needed by industry. This requires, first of all, the ability to accurately locate them in industrial components that are no longer in use. Non-destructive nuclear measurement meets this objective, based on prompt gamma neutron activation analysis (PGNAA). This approach involves interrogating the samples to be analyzed with an electrical generator emitting pulses of fast neutrons that thermalize in a polyethylene and graphite cell: between the pulses, radiative capture gamma rays are measured. The advantage of such an approach lies in the fact that high-value elements such as dysprosium or neodymium have a high radiative capture cross-section by thermal neutrons, and that the latter can probe deep into large volumes of matter (several liters).
A previous thesis demonstrated the feasibility of this technique and opened up promising avenues of research, with two complementary strands to make concrete progress towards practical recycling objectives. The first involves experimental and simulation studies of the performance of gamma cascade measurement on cases representative of industrial needs (size and composition of objects, measurement speed). The second will enrich and improve the exploitation of the vast amount of information available from gamma-ray cascade measurements.
In practice, the work will be carried out as part of a collaboration between CEA and the FZJ (ForschungsZentrum Jülich) institute in Germany. The first half of the thesis will be carried out at CEA IRESNE Nuclear Measurement Laboratory. The second half of the thesis will be carried out at the FZJ (Jülich Centre for Neutron Science, JCNS). The German part of the thesis will involve experiments with the FaNGaS device at the Heinz-Maier-Leibnitz Zentrum (MLZ) in Garching.
Flow rate measurement in a pipeline using thermal noise detection
Flow measurement is a key factor in process management, particularly in the nuclear and industrial sectors. However, current measurement methods require complex installations, especially in environments with strict regulations, such as in the nuclear sector. To address these challenges, the CEA has developed an innovative method for measuring flow in non-isothermal fluids, based on the analysis of thermal fluctuations. This technique, which uses two temperature sensors installed upstream and downstream on the pipeline, is simple to implement and involves minimal constraints. The temperature variations are carried by the flow from one sensor to the other, and by comparing the signals recorded by these sensors, it is possible to calculate the thermal transit time between them, which allows the flow velocity, and consequently, the flow rate, to be determined. The goal of this thesis is to optimize this method by enhancing its reliability. To achieve this, the propagation of thermal noise within the flow will be studied, and both the type and placement of the sensors will be optimized. This work will be carried out within the Core and Circuit Thermohydraulics Laboratory in collaboration with the Instrumentation, System and Method Laboratory, which has state-of-the-art experimental equipment. Numerical simulations will complement the experimental work to validate the obtained results. In parallel, artificial intelligence approaches will be explored to improve the processing of thermal signals. By the end of the thesis, the doctoral candidate will have acquired extensive skills in experimental and numerical work and will be able to leverage these in future endeavors.
A macroscale approach to evaluate the long-term degradation of concrete structures under irradiation
In nuclear power plants, the concrete biological shield (CBS) is designed to be very close of the reactor vessel. It is expected to absorb radiation and acts as a load-bearing structure. It is thus exposed during the lifetime of the plant to high level of radiations that can have consequences on the long term. These radiations may result especially in a decrease of the material and structural mechanical properties. Given its key role, it is thus necessary to develop tools and models, to predict the behaviors of such structures at the macroscopic scale.
Based on the results obtained at a lower scale - mesoscopic simulations, from which a better understanding of the irradiation effect can be achieved and experimental results which are expected to feed the simulation (material properties especially), it is thus proposed to develop a macroscopic methodology to be applied to the concrete biological shield. This approach will include different phenomena, among which radiation-induced volumetric expansion, induced creep, thermal defromations and Mechanical loading.
These physical phenomena will be developed within the frame of continuum damage mechanics to evaluate the mechanical degradation at the macroscopic scale in terms of displacements and damage especially. The main challenges of the numerical developments will be the proposition of adapted evolution laws, and particularly the coupling between microstructural damage and damage at the structural level due to the stresses applied on the structure.