A5072333903- Fatigue and fracture mechanics
- Nuclear and radioactivity studies
- Structural Response to Dynamic Loads
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Probabilistic and Robust Engineering Design
- High-Velocity Impact and Material Behavior
- Nuclear Engineering Thermal-Hydraulics
- High Temperature Alloys and Creep
- Graphite, nuclear technology, radiation studies
- Fire effects on concrete materials
- Material Properties and Failure Mechanisms
- Risk and Safety Analysis
- Seismic Performance and Analysis
- Structural Integrity and Reliability Analysis
- Fusion materials and technologies
- Structural Behavior of Reinforced Concrete
- Engineering Diagnostics and Reliability
- Structural Health Monitoring Techniques
- Particle accelerators and beam dynamics
- Geotechnical Engineering and Underground Structures
- Fluid Dynamics Simulations and Interactions
- Welding Techniques and Residual Stresses
- Transportation Safety and Impact Analysis
- Concrete Corrosion and Durability
Kaunas University of Technology
2007-2024
Lithuanian Energy Institute
2013-2024
Max Planck Institute for Plasma Physics
2016
Energy Institute
1999-2014
The next step in the Wendelstein stellarator line is large superconducting device 7-X, currently under construction Greifswald, Germany. Steady-state operation an intrinsic feature of stellarators, and one key element 7-X mission to demonstrate steady-state plasma conditions relevant for a fusion power plant. device, on hand, requires implementation special technologies, giving rise technical challenges during design, fabrication assembly such device. On other also physics development at...
The sudden increase in the operating pressure of nuclear power plants (NPPs) is due to water hammer phenomenon, which tends produce a whipping effect that causes serious damage pipes and their surroundings. mechanical response these pipelines under influence such fast fluid transients can be estimated using fluid–structure interaction (FSI) method. computational time expense are predominantly dependent on number finite elements developed model. Hence, an effective modeling technique with...
Abstract In order to ensure that nuclear power plant buildings are reliable and safe in case of external loading, it is very important evaluate uncertainties associated with loads, material properties, geometrical parameters, boundaries other parameters. Therefore, a probability-based analysis was developed as the integration deterministic probabilistic methods using existing state-of-the-art software. The subject this paper integrated building failure due impact by commercial aircraft....
A probability-based approach, combining deterministic and probabilistic methods, was developed for analyzing building component failures, which are especially crucial complex structures like nuclear power plants. This method links finite element software to assess structural integrity under static dynamic loads. study uses NEPTUNE software, is validated, a transient analysis ProFES models. In case study, analyses with varied random variables were transferred of piping failure wall damage....
Abstract Numerical fatigue process modelling is complex and still an open task. Discontinuity caused by cracks requires special finite element techniques based on additional parameters, the selection of which has a strong effect simulation results. Moreover, calculation life according to empirical material coefficients (e.g., Paris law) does not explain process, should be set from experimental testing, always possible. A new nonlocal continuum mechanics formulation without spatial derivative...
The combination of kinematic and isotropic hardening models makes it possible to model the behaviour cyclic elastic-plastic steel material, though estimation parameters catching influence those on material response is a challenging task. In current work, an approach for numerical simulation low-cycle fatigue AISI316L presented using finite element method study at different strain amplitudes operating temperatures. Fully reversed uniaxial LCF tests are performed Based test experimental...
In this paper the study of accident localisation system (ALS) Ignalina nuclear power plant (NPP) with RBMK-1500 reactors (large-power channel-type crater-cooled graphite-moderated reactor) wih regard to a maximum design basis (MDBA) is presented. The MDBA for NPP constitutes guillotine rupture diameter pipe. thermal-hydraulic and structural analyses were performed using RELAP5, CONTAIN ALGOR codes. coolant mass energy discharge source terms compartment established RELAP5 code. This was then...
The 3D thin‐walled finite element model of Ignalina NPP Unit 2 reactor building was developed aimed at the evaluation global dynamic behaviour with a focus on seismic response. comprises description monolithic structures, while prefabricated frame structures are ignored and replaced by external masses. Sensitivity study selected characteristics respect to data uncertainties is considered. Uncertainty considered in terms masses removed wall stiffness. Seismic input represented site specific...
A substantial amount of research effort has been applied to the field environmentally assisted fatigue (EAF) due requirement account for EAF behaviour metals existing and new build nuclear power plants. We present results European project INcreasing Safety in NPPs by Covering Gaps Environmental Fatigue Assessment (INCEFA-PLUS), during which sensitivities strain range, environment, surface roughness, mean hold times, as well their interactions on life austenitic steels characterized. The...