A5011169218- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear materials and radiation effects
- Superconducting Materials and Applications
- Muon and positron interactions and applications
- Nuclear reactor physics and engineering
- Solid-state spectroscopy and crystallography
- Diamond and Carbon-based Materials Research
- Advanced Battery Materials and Technologies
- Corrosion Behavior and Inhibition
- Crystallization and Solubility Studies
- Electrocatalysts for Energy Conversion
- Hydrogen Storage and Materials
- Advancements in Solid Oxide Fuel Cells
- Fault Detection and Control Systems
- High-Energy Particle Collisions Research
- Nuclear Physics and Applications
- Thermal and Kinetic Analysis
- Ion-surface interactions and analysis
- Ionosphere and magnetosphere dynamics
- Advanced ceramic materials synthesis
- Molten salt chemistry and electrochemical processes
- Radioactive element chemistry and processing
- Anomaly Detection Techniques and Applications
University of Latvia
2009-2024
Royal Military Academy
2020
Tritium depth profile and its temperature programmed desorption rate were determined for selected samples cut out of beryllium tiles removed from the Joint European Torus vacuum vessel during 2012 shut down. A dissolution method under controlled conditions was used to determine tritium in samples, whereas experiments performed assess release pattern. Released measured using a proportional gas flow detector. Prior experiments, plasma-facing surfaces studied by scanning electron microscopy...
The ITER-Like-Wall project has been carried out at the Joint European Torus (JET) to test plasma facing materials relevant ITER. Materials being tested include both bulk metals (Be and W) coatings. Tritium accumulation mechanisms release properties depend on wall components, their location in vacuum vessel, conditions of exposure material itself. In this study, beryllium limiter tiles, plasma-facing coated Inconel components from main chamber, tungsten carbon fibre composite divertor tiles...
ITER-Like-Wall (ILW) project has been carried out at Joint European Torus (JET) to test plasma facing materials relevant International Thermonuclear Experimental Reactor – ITER [1]. Limiters and an upper dump plate of the vacuum vessel are made bulk beryllium tiles, whereas for divertor tungsten tungsten-coated carbon fibre (CFC) composite tiles used. During shutdowns in ILW1 (2012), ILW2 (2014) ILW3 (2016), selected were removed from vessel. In this study, three positions analysed, analysis...
The effects of temperature, magnetic field (MF), and ionizing radiation on the release tritium from Be pebbles irradiated in BERYLLIUM experiment 1994 Petten, Netherlands (irradiation neutron fluence 1.24 × 1025 m-2, irradiation temperature 780 K, 3H content 7 appm) were investigated this study. Simultaneous action these factors corresponds to real operating conditions blanket a fusion reactor. total amount separate pebble, chemical forms localized (T0, T2, T+), distribution pebble volume...
In this paper, we present results on tritium release from the beryllium pebbles irradiated for 294 full power days 17 April 2003 to November 2004 neutron fluence of 1.5-2 × 1025 m-2 (E>1 MeV) at temperature 523-773 K in pebble-bed assemblies (PBA) experiment high flux reactor (HFR) Petten, Netherlands. Stages gradual and burst are evident PBA Be a ramp 2.3-4.8 K/min room 1310-1520 K. These two stages may be related by atomic diffusion bubble venting respectively. The main maximum rate was...
An original complex device has been designed and created specially for this research. Some of tritium sorption thermal desorption in liquid lithium experiments successfully done already. First experiment series were carried out under reduced pressure (vacuum) to rule other operating gases (like Ar) that may squeeze from lithium. Experiments showed good which highly depends on the temperature. A proportional gas counter monitor was used collect data experiments.