A5043114110- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Radioactive element chemistry and processing
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Fusion materials and technologies
- Nuclear Physics and Applications
- Thermodynamic and Structural Properties of Metals and Alloys
- Graphite, nuclear technology, radiation studies
- Heat transfer and supercritical fluids
- Nuclear materials and radiation effects
- Chemical Looping and Thermochemical Processes
- Risk and Safety Analysis
- Advanced Combustion Engine Technologies
- Rare-earth and actinide compounds
- Gas Dynamics and Kinetic Theory
- Combustion and Detonation Processes
- High Temperature Alloys and Creep
- Microstructure and mechanical properties
- Spacecraft and Cryogenic Technologies
- Thermal properties of materials
- Computational Fluid Dynamics and Aerodynamics
- Geothermal Energy Systems and Applications
- Metallurgy and Material Forming
- Fatigue and fracture mechanics
Joint Research Centre
2015-2024
European Commission
2011-2020
Belgonucleaire (Belgium)
2007
Belgian Nuclear Research Centre
2000-2003
Joint Research Center
1993
We review the state of modeling and simulation nuclear fuels with emphasis on most widely used fuel, UO2. The hierarchical scheme presented represents a science-based approach to by progressively passing information in several stages from electronic structure calculations continuum level simulations. Such an is essential overcome challenges posed radioactive materials handling, experimental limitations extreme conditions accident scenarios, small time distance scales fundamental processes....
Values are reported of specific heat, thermal conductivity and diffusivity UO2 from 1500 K to 2900 based on laser flash measurements. Experiment is complemented by the development solid state physics models that aid in interpretation results. Specific heat shown exhibit a smooth maximum at 2715 ± 100 K, consistent with competition between two processes - oxygen defect interactions (net attraction) saturation interstitial sites. The model measurements show, for first time gradual pre-melting...
The description of intra-granular fission gas behaviour is a fundamental part any model for the prediction release and swelling in nuclear fuel. In this work we present describing evolution bubbles terms bubble number density average size, coupled to grain boundaries. considers processes single atom diffusion, nucleation, re-solution trapping at bubbles. derived from detailed cluster dynamics formulation, yet it consists only three differential equations its final form; hence, can be...
Among the applications of multiscale modelling approach in nuclear fuel rod performance, coupling integral thermo-mechanical performance codes with lower-length meso-scale modules is great interest. This strategy allows to overcome correlation-based approaches mechanistic ones and test their application accidental conditions. In this work, we explore between TRANSURANUS code two for fission gas/product behaviour: MFPR-F SCIANTIX. These modules, coupled within TRANSURANUS, are assessed...
Small Modular Reactors (SMRs) offer modularisation, standardisation, and factory fabrication, reducing capital costs enhancing passive safety. However, their lower power density compared to commercial Light Water (LWRs) limits competitiveness. Deploying Advanced Technology Fuels (ATFs) can improve SMR performance. This study evaluates short-term ATF solutions in a soluble boron-free (SBF) inspired by Rolls Royce's design, using advanced nuclear modelling tools (WIMS, PANTHER, TRANSURANUS)...
A new methodology is introduced to analyse porosity data in the high burnup structure. Image analysis coupled with adaptive kernel density estimator obtain a detailed characterisation of pore size distribution, without a-priori assumption on functional form distribution. Subsequently, stereological carried out. The method shows advantages compared classical approach based histogram terms detail description and accuracy within experimental limits. Results are approximation log-normal In...
Abstract The formation of the high burnup structure (HBS) is possibly most significant example restructuring processes affecting commercial nuclear fuel in-pile. HBS forms at relatively cold outer rim pellet, where local 2–3 times higher than average pellet burnup, under combined effects irradiation and thermo-mechanical conditions determined by power regime rod configuration. main features transformation are subdivision original grains into new sub-micron grains, relocation fission gas...
Vickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-up ≥60 GWd/tHM are presented. Their ratio HV0.1/E was found constant in the range 60–110 GWd/tHM. From values vs porosity, dependence on porosity derived extended to full radial profile, including high structure (HBS). The is well represented by a linear correlation. data were compared performance codes correlations. A dependent factor introduced expression. modifications extend experimental validation...
We propose a model describing the HBS formation and progressive intra-granular xenon depletion in UO2. The is modeled employing Kolmogorov-Johnson-Mehl-Avrami (KJMA) formalism for phase transformations, which has been fitted to experimental data on restructured volumetric fraction as function of local effective burnup. To this end, we employed available novel extracted work. coupled description fission gas behavior, allowing estimate evolution retained order consistently compute retention...
This work presents the detailed fuel rod simulation with new TRANSURANUS code in combination a high fidelity neutronic analysis of an innovative British advanced gas cooled type reactor materials by means Serpent. The Hastelloy cladding material and molten salt properties have been assessed implemented our previous work. In this paper, we evaluate effect uncertainties on hottest assembly sample AGR. For purpose, limiting criterion based Larson Miller Parameter are also introduced to...
Increasing the average grain size of fuel pellets by doping them with chromium oxide is one strategy to improve nuclear fuels performance. The promoted fission gas retention thought performance at high burnup. In this work, we review models for solubility in UO2, and evolution phases matrix during irradiation. These are implemented SCIANTIX, an open-source mesoscale code describing inert behaviour fuel. We adjusted model keeping each parameter within its range compatibility experimental...