A5043375394- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Ion-surface interactions and analysis
- Nuclear Physics and Applications
- Advanced Materials Characterization Techniques
- Advanced materials and composites
- Nuclear materials and radiation effects
- Metal and Thin Film Mechanics
- Intermetallics and Advanced Alloy Properties
- Hydrogen Storage and Materials
- Hydrogen embrittlement and corrosion behaviors in metals
- Microstructure and mechanical properties
- Superconducting Materials and Applications
- High-Temperature Coating Behaviors
- Microstructure and Mechanical Properties of Steels
- Advanced ceramic materials synthesis
- Rare-earth and actinide compounds
- Muon and positron interactions and applications
- Advanced Chemical Physics Studies
- Magnetic confinement fusion research
- High Temperature Alloys and Creep
- Concrete Corrosion and Durability
- Structural Health Monitoring Techniques
- X-ray Spectroscopy and Fluorescence Analysis
Karlsruhe Institute of Technology
2015-2024
Kurchatov Institute
1997-2020
Applied Materials (Germany)
2015
Institute for Materials Research, Tohoku University
2012
FZI Research Center for Information Technology
2002-2010
FIZ Karlsruhe – Leibniz Institute for Information Infrastructure
2005
The scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for EU DEMO reactor; this includes segments inside Vacuum Vessel and related Tritium Extraction/Removal Systems. In Pre-Concept Design (PCD) Phase, two concepts have been selected as candidates; solid liquid breeder cooled with helium water, respectively. design these systems has adapted plant developed in PCD Phase performances assessed. A large R&D programme implemented evaluate different technologies...
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 helium-cooled pebble bed (HCPB) blanket is one of the two concepts proposed as a driver for European Union Demonstration Fusion Power Reactor (EU DEMO). In contrast to past conceptual design studies, in frame current Plant Physics and Technology EUROfusion Consortium, ongoing EU DEMO preconceptual activities have adopted holistic integrated (i.e., systems engineering) approach. As consequence this new approach, many interfaces requirements been identified, some them driving blankets....
Excellent mechanical properties of ODS steels are directly related to the high density homogeneously distributed, well-formed oxide particles (such as Y2O3, or Y-Ti-O). However, atom probe tomography study revealed that in addition they contain almost a hundred times more nanoclusters enriched Y, O and V/Ti (if present alloy composition) than larger particles. In this work, we carried out (APT) transmission electron microscopy (TEM) studies three different produced by alloying: Eurofer,...
Beryllium is a promising functional material for several breeder system concepts to be tested within the experimental fusion reactor ITER and, later, implemented in first commercial demonstration power plant DEMO. For these applications its resistance neutron irradiation and detrimental effects of radiogenic gases (helium tritium) crucial safety, subsequent waste management recycling. A reliable prediction beryllium behavior under conditions requires both dedicated experiments advanced...
Ulba Metallurgical Plant JSC has been leading several research and development programs aimed at producing beryllides for both structural fusion applications. The main focus on the of tantalum beryllide as a high-temperature material, chromium titanium neutron multipliers EU DEMO. Utilizing vacuum hot pressing, billets tantalum, chromium, were successfully produced, with their key properties such density, phase composition, microstructure extensively analyzed. These results show promising...
Abstract The microstructural response of beryllium after neutron irradiation at various temperatures (643–923 K) was systematically studied using analytical transmission electron microscope that together with outcomes from advanced atomistic modelling provides new insights in the mechanisms changes this material. most prominent feature modification is formation gas bubbles, which revealed all temperatures. Except for lowest temperature, bubbles have shape thin hexagonal prisms average height...
Even though hydrogen-metal surface interactions play an important role in energy technologies and metal corrosion, a thorough understanding of these at the nanoscale remains elusive due to obstructive detection limits instrumentation volatility pure hydrogen. In present paper we use analytical spectroscopy TEM show that hydrogen adsorbs directly (0001) surfaces hexagonal helium bubbles within neutron irradiated beryllium. addition hydrogen, also found Al, Si Mg beryllium-bubble interfaces....