A5038797943- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Radioactive element chemistry and processing
- Nuclear and radioactivity studies
- Nuclear Physics and Applications
- Heat transfer and supercritical fluids
- Fusion materials and technologies
- Metallurgical Processes and Thermodynamics
- Dark Matter and Cosmic Phenomena
- Atomic and Subatomic Physics Research
- Model Reduction and Neural Networks
- Radiation Detection and Scintillator Technologies
- Graphite, nuclear technology, radiation studies
- Molten salt chemistry and electrochemical processes
- Thermodynamic and Structural Properties of Metals and Alloys
- Nuclear materials and radiation effects
- Magnetic confinement fusion research
- Particle Detector Development and Performance
- Structural Response to Dynamic Loads
- Numerical methods for differential equations
- Real-time simulation and control systems
- Probabilistic and Robust Engineering Design
- Superconducting Materials and Applications
- Spacecraft and Cryogenic Technologies
Politecnico di Milano
2015-2024
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas
2023-2024
Centre National de la Recherche Scientifique
2023
Centre de physique des particules de Marseille
2023
Institut National de Physique Nucléaire et de Physique des Particules
2023
Istituto Nazionale di Fisica Nucleare, Sezione di Milano
2017-2021
This paper describes the neutronic benchmarks and results obtained by various participants of FP7 project EVOL ROSATOM MARS. The aim was two-fold: first to verify validate each code packages partners, adapted for liquid-fueled reactors, second check dependence core characteristics nuclear data set application on a molten salt fast reactor (MSFR). MSFR operates with thorium fuel cycle can be started 233 U-enriched U and/or TRU elements as initial fissile load. All three compositions were...
Bridging lower length-scale calculations with the engineering-scale simulations of fuel performance codes requires development dedicated intermediate-scale codes. In this work, we present SCIANTIX, an open source 0D stand-alone computer code designed to be included/coupled as a module in existing The models currently available SCIANTIX cover intra- and inter-granular inert gas behaviour UO2, high burnup structure formation well. Showcases validation both constant transient conditions are...
Minor actinides are the main contributors to medium- and long-term radiotoxicity heat production in spent nuclear fuels. Research efforts currently ongoing explore different options dispose of such radionuclides, e.g., their burning fast reactors within mixed-oxide The MYRRHA sub-critical reactor is one future facilities with envisaged transmutation capabilities. This work assesses thermal–mechanical performance a homogeneous Am-bearing fuel pin both In-Pile test Section position "Revision...
Compressible fluid dynamics is of great practical interest in many industrial applications, ranging from chemistry to aeronautical industry, and nuclear field as well. At the same time, modelling simulation compressible flows a very complex task, requiring development specific approaches, order describe effect pressure on velocity field. Compressibility effects become even more important study two-phase flows, due presence gaseous phase. In addition, compressibility also expected have...
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...
SCIANTIX is a 0D, open-source code designed to model inert gas behaviour within nuclear fuel at the scale of grain. The predominantly employs mechanistic approaches based on kinetic rate-theory models calculate engineering quantities, such as fission release and gaseous swelling. Since its release, has undergone significant improvements, including incorporation new modelling numerical capabilities. architecture been revamped, embracing an object-oriented structure improving overall...
The high-temperature phase diagram of the UO2–ThO2 system has been experimentally revisited in present study for first time since 1970, using a laser heating approach combined with fast pyrometry thermal arrest method. melting/solidification temperature, which is fundamental information reactor design was studied here. It found that low addition ThO2 to UO2 would result slight decrease solidification temperature. A minimum at 3098 K around composition 5 mol% ThO2. solid/liquid transition...
The Molten Salt Fast Reactor is a fast-spectrum molten salt reactor under development in the framework of European H2020 SAMOFAR Project (http://samofar.eu/). Among design peculiarities, this circulating fuel features helium bubbling system aimed at removing on-line gaseous fission products, and metallic particles as well. From modelling point view, presence bubbles core needs to be assessed both from neutronics thermal-hydraulics view. In paper, attention paid first aspect, analysing void...
The aim of this paper is the extension a multiphysics OpenFOAM solver for analysis Molten Salt Fast Reactor (MSFR), developed in previous works (Cervi et al., 2017, 2018). In particular, neutronics sub-solver improved by implementing new module based on SP3 approximation neutron transport equation. successfully tested against Monte Carlo model MSFR, order to assess its correct implementation. Then, MSFR carried out simplified axial-symmetric reactor. Particular focus devoted helium bubbling...