A5102853665- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Nuclear and radioactivity studies
- Modeling and Simulation Systems
- Spacecraft and Cryogenic Technologies
- Nuclear Physics and Applications
- Rocket and propulsion systems research
- Probabilistic and Robust Engineering Design
- Gas Dynamics and Kinetic Theory
- Vacuum and Plasma Arcs
- EU Law and Policy Analysis
- Refrigeration and Air Conditioning Technologies
- Combustion and flame dynamics
- Medical Image Segmentation Techniques
- Cleft Lip and Palate Research
- Fluid Dynamics and Turbulent Flows
- Face recognition and analysis
- Solar Energy Systems and Technologies
- Solar Thermal and Photovoltaic Systems
- Radioactive contamination and transfer
Polytechnic University of Turin
2015-2024
University of Turin
2016
The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become driver EU-DEMO reactor. design was enacted with a holistic approach. influence that neutronics, thermal-hydraulics (TH), thermo-mechanics (TM) and magneto-hydro-dynamics (MHD) may have on were considered at same time. This new approach allowed for team create WCLL BB layout able comply different foreseen requirements in terms integration, tritium self-sufficiency, TH TM needs. In...
The Pre-Concept Design (PCD) of the Balance Plant (BoP) systems EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely Water Cooled Lithium Lead (WCLL) BB and Helium Pebble Bed (HCPB) BB. Moreover, results a preliminary evaluation number BoP variants are discussed. This outlines steps design development, highlighting project objectives strategy their achievement very challenging requirements which include, among others, intermittent...
Currently, for the EU DEMO, two Breeding Blankets (BBs) have been selected as potential candidates integration in reactor. They are Water Cooled Lithium Lead and Helium Pebble Bed BB concepts. The variants together with associated ancillary systems drive design of overall plant. Therefore, a holistic investigation issues derived by installation its has performed. related to water activation due 16N 17N isotopes impact on primary heat transfer investigated providing guidelines dedicated...
A global thermal-hydraulic model of the EU DEMO tokamak, based on an object-oriented approach using Modelica language, is currently under development at Politecnico di Torino. The first module will simulate dynamics blanket cooling system and it be able to investigate different coolant options schemes, adapted systems in Breeding Blanket project. Following related Helium-Cooled Pebble Bed blanket, this paper presents dynamic Water-Cooled Lithium Lead (WCLL) designed ENEA Brasimone, together...
AbstractIt is widely recognized that the safe and robust design of a nuclear system requires an uncertainty propagation analysis concerning various data used as input parameters, especially in view most recent methodologies like best-estimate plus approach. The evaluation uncertainties their to parameters interest particularly important case fusion machines, such Affordable Robust Compact (ARC) reactor, which features presence uncommon isotopes engineering field, fluorine, beryllium,...
The EU DEMO reactor aims at producing electricity from nuclear fusion, and its conceptual design is currently ongoing within the EUROfusion consortium. In this phase, analyses of faults are key importance. Among them, some most critical involving magnet system characterized by a quick abnormal evolution current in coils; therefore, correct prediction actual crucial to get reliable results transient simulations these accidents. work, model coil power supply circuit has been developed provide...
The EU-DEMO first wall protection relies on a system of limiters. Although they are primarily designed for facing the energy released by limited plasma during transients, their design should safely withstand combination loads relevant in-vessel components (IVCs) steady-state operation. They not meant to breed tritium, nor provide stability. However, sitting in place blanket portions, ensure an adequate shielding function vacuum vessel and magnets while withstanding both dead weight...
This paper introduces a multiphysics code, named nemoFoam, designed within the OpenFOAM environment to address coupling of neutron and photon transport with thermal-hydraulics in nuclear reactor simulations. The conceived both for fusion fission applications, employs modular approach where neutronic module is currently based on multi-group diffusion equations, including mono-kinetic treatment photons. thermal-hydraulic built standard solver. focuses presenting key features nemoFoam...
Ultrasound is by far the most adopted method for safe screening and diagnosis in prenatal phase, thanks to its non-harmful nature with respect radiation-based imaging techniques. The main drawback of ultrasound sensitivity scattering noise, which makes automatic tissues segmentation a tricky task, limiting possible range applications. An algorithm automatically extracting facial surface presented here. provides comprehensive process does not require any human intervention or training...
Accidental transients in fusion reactors, such as the in-vessel loss-of-coolant accident (LOCA) considered here, are generally analyzed using system-level codes. However, because of their lumped nature, tools cannot predict local pressure and temperature values, which instead interest to assess integrity vacuum vessel (VV) structures. It is then fundamental prove that tools' predictions at least conservative. In this work, we analyze helium flow inside VV following a LOCA helium-cooled...
Neutronic modeling of fusion machines requires a detailed representation their complex geometry in order to properly evaluate various parameters interest such as energy deposition and tritium production the breeding blanket. In this work, neutronics Affordable, Robust, Compact (ARC) reactor is modeled with Monte Carlo particle transport code Serpent developed at VTT Technical Research Centre Finland an alternative other, more established, tools community N-Particle Transport (MCNP) code. The...
The general tokamak thermal-hydraulic model (GETTHEM) has been updated to the most recent version of EU DEMO helium-cooled pebble bed breeding blanket (BB) design. GETTHEM results are first benchmarked in a controlled case against 3-D computational fluid-dynamics computations, showing an acceptable accuracy despite inherent simplifications model. is then applied evaluation poloidal hot spot temperature distribution entire BB segment, that maximum EUROFER structures overcomes design limit 550...
The Vacuum Vessel Pressure Suppression System (VVPSS) is the safety system devoted to mitigation of in-vessel Loss-Of-Coolant Accidents, which are considered among Design-Basis Accidents for tokamak fusion reactors. EUROfusion Consortium performing design this system, as part conceptual phase EU DEMO reactor, including in process its integration plant. This work reports first parametric calculations carried out evaluate VVPSS response a postulated double-ended guillotine rupture Breeding...