A5007348712- Fusion materials and technologies
- Superconducting Materials and Applications
- Magnetic confinement fusion research
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Magnetic Properties and Applications
- Electromagnetic Launch and Propulsion Technology
- Particle accelerators and beam dynamics
- Non-Destructive Testing Techniques
- Microstructure and Mechanical Properties of Steels
- Magnetic properties of thin films
- Liquid Crystal Research Advancements
- Silicon and Solar Cell Technologies
- Advancements in Photolithography Techniques
- Nonlinear Dynamics and Pattern Formation
- Electrical Contact Performance and Analysis
- Plant Reproductive Biology
- Laser-Plasma Interactions and Diagnostics
- Gas Dynamics and Kinetic Theory
- HVDC Systems and Fault Protection
- Vacuum and Plasma Arcs
- Rocket and propulsion systems research
- Numerical methods in inverse problems
- Graphite, nuclear technology, radiation studies
- Model Reduction and Neural Networks
Karlsruhe Institute of Technology
2015-2024
Kerntechnische Entsorgung Karlsruhe (Germany)
2011
University of Pisa
2004
In the framework of EUROfusion's Power Plant Physics and Technology, working package breeding blanket (BB) aims at investigating four different BB concepts for an EU demonstration fusion reactor (DEMO). One these is helium-cooled pebble bed (HCPB) BB, which based on use beds lithiated ternary compounds Be or beryllides as tritium breeder multiplier materials, respectively, EUROFER97 structural steel He coolant. This paper giving overview HCPB Research Development (R&D) being developed KIT,...
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...
• Description of blanket integration concept. Stress calculation breeding segments. Prediction Breeding deformation. Identification custom-machining concept and prediction achievable tolerances. Overview the various issues associated with design in-vessel components. The DEMO tokamak architecture is based on large vertical (BB) segments that are accessed from a maintenance hall above vertically replaced through upper ports vacuum vessel (VV). feasibility BB mechanical supports prerequisite...
Abstract Fusion systems codes (SCs) are deployed to produce the baseline of European fusion power reactor (DEMO) within its conceptual design. A DEMO is mostly defined by a radial/vertical sketch and major parameters, such as net electric power, magnetic fields, plasma burn time. shall also meet set prescribed requirements, constraints, architectural features. According design workflow implemented EU-DEMO programme, output from SC transferred detailed physics engineering codes....
The outcome of the electromagnetic (EM) analyses carried out during DEMO pre-conceptual phase demonstrated that EM loads are relevant for structural assessment breeding blanket (BB) and, in particular, definition boundary conditions at attachment system with vacuum vessel. However, within scope previous campaign, results obtained using simplified models only give a rough estimation inside BB structure. This kind data has been considered suitable preliminary segments, but it is not...
The aim of this paper is to evaluate the magnetic properties and losses Fe-9Cr steel under nonperiodic conditions field. A new approach combining an optimized linear problem classical Preisach theory adopted described. An experimental analysis carried out characterize quasi-static major loop dynamic cycles obtained at different rates driving field <i xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">H</i> . After a series loops, are defined in first...