Publications
https://orcid.org/0000-0001-7236-3423
2027
- Codes and standards and digital technology use - recommendations for innovative nuclear plants , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2026.104666
2026
- Exploring sustainability, societal perception, licensing and non-electric applications of new nuclear technologies: perspectives and achievements of ECOSENS, HARMONISE and SANE projects , EPJ Nuclear Sciences & Technologies — DOI: 10.1051/epjn/2026010
- Radiation dose analysis in the Lithium system rooms during beam-on and beam-off , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2026.104724
2024
- Map Determination of Code and Standard Needs to be Covered for Innovative Nuclear Reactors , 33RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE
2020
- Scientific inheritance of Eugenijus Ušpuras,Wissenschaftliches Erbe von Eugenijus Ušpuras , Kerntechnik — DOI: 10.3139/124.200005
- Safety assessment for EU DEMO - Achievements and open issues in view of a generic site safety report , FUSION ENGINEERING AND DESIGN — DOI: 10.1016/J.FUSENGDES.2020.111541
- Education, training and mobility: towards a common effort to assure a future workforce in Europe and abroad , EPJ NUCLEAR SCIENCES & TECHNOLOGIES — DOI: 10.1051/EPJN/2019018
2019
- Safety and environment studies for a European DEMO design concept , FUSION ENGINEERING AND DESIGN — DOI: 10.1016/J.FUSENGDES.2018.11.049
- Forward modeling of collective Thomson scattering for Wendelstein 7-X plasmas: Electrostatic approximation , REVIEW OF SCIENTIFIC INSTRUMENTS — DOI: 10.1063/1.5048361
2018
- Erratum to: Magnetic configuration effects on the Wendelstein 7-X stellarator (Nature Physics, (2018), 14, 8, (855-860), 10.1038/s41567-018-0141-9) , Nature Physics — DOI: 10.1038/s41567-018-0215-8
- Towards a new image processing system at Wendelstein 7-X: From spatial calibration to characterization of thermal events , REVIEW OF SCIENTIFIC INSTRUMENTS — DOI: 10.1063/1.5045560
- Magnetic configuration effects on the Wendelstein 7-X stellarator , NATURE PHYSICS — DOI: 10.1038/S41567-018-0141-9
- Post-benchmark simulation of the THAI plus facility TH27 experiment , JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY — DOI: 10.1080/00223131.2018.1432424
2017
- Resolving safety issues for a demonstration fusion power plant , FUSION ENGINEERING AND DESIGN — DOI: 10.1016/J.FUSENGDES.2017.02.018
- Major results from the first plasma campaign of the Wendelstein 7-X stellarator , NUCLEAR FUSION — DOI: 10.1088/1741-4326/AA770D
- The Generic Containment SB-LOCA accident simulation: Comparison of the parameter uncertainties and user-effect , ANNALS OF NUCLEAR ENERGY — DOI: 10.1016/J.ANUCENE.2017.03.037
2016
- Nuclear fusion research at Lithuanian energy institute,Branduolių sintezės tyrimai Lietuvos energetikos institute , Energetika — DOI: 10.6001/energetika.v62i3.3349
2015
- Uncertainty and sensitivity evaluation of aerosol deposition in PHEBUS containment during FPT-2 experiment , energetika — DOI: 10.6001/energetika.v61i1.3092
- Accession of Lithuanian energy institute to nuclear fusion researches , IREC2015 The Sixth International Renewable Energy Congress — DOI: 10.1109/irec.2015.7110864
- Assessment of W7-X plasma vessel pressurisation in case of LOCA taking into account in-vessel components , FUSION ENGINEERING AND DESIGN — DOI: 10.1016/J.FUSENGDES.2015.08.001
- Simulation of the ICE P1 test for a validation of COCOSYS and ASTEC codes , FUSION ENGINEERING AND DESIGN — DOI: 10.1016/J.FUSENGDES.2015.03.021
- Modelling of Ingress of Coolant Event into Vacuum Experiments with ASTEC Code , JOURNAL OF FUSION ENERGY — DOI: 10.1007/S10894-014-9804-4
- Uncertainty and Sensitivity Analysis of the Generic Containment SB-LOCA Accident , 24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015)
- ARCADIA Project Contribution to the Regional Cooperation on LFR Technology Development , 24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015)
- Accession of Lithuanian energy institute to nuclear fusion researches , 2015 6th International Renewable Energy Congress (IREC)
- Thermal-Hydraulic Assessment of W7-X Plasma Vessel Venting System in Case of 40 mm In-Vessel LOCA , SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS — DOI: 10.1155/2015/240368
2014
- The ARCADIA Project in Support of the ALFRED Concept , Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security — DOI: 10.1115/icone22-31109
- Validation of special nodalisation features for lumped-parameter injection modelling based on MISTRA facility tests from ISP-47 and SARNET , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2014.07.011
- THE ARCADIA PROJECT IN SUPPORT OF THE ALFRED CONCEPT , PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 3
2013
- Project design progress on plasma and outer vessel exhaust gas system based on LOCA safety analysis of W7-X stellarator , 2013 IEEE 25th Symposium on Fusion Engineering (SOFE) — DOI: 10.1109/sofe.2013.6635286
- Sensitivity and uncertainty analysis of atmosphere stratification modelling in MISTRA using lumped-parameter code COCOSYS , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2013.08.058
- Technical challenges in the construction of the steady-state stellarator Wendelstein 7-X , NUCLEAR FUSION — DOI: 10.1088/0029-5515/53/12/126001
2012
- Parametric Study of MISTRA M5 Test Using Lumped Parameter COCOSYS Code , Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles — DOI: 10.1115/icone20-power2012-55201
- Diffusive deposition of aerosols in phebus containment during FPT-2 test , International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012
- Simulation of Targets Feeding Pipe Rupture in Wendelstein 7-X Facility Using RELAP5 and COCOSYS Codes , JOURNAL OF FUSION ENERGY — DOI: 10.1007/S10894-011-9502-4
- COCOSYS analysis for deposition of aerosols and fission products in PHEBUS FPT-2 containment , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2012.02.015
- PARAMETRIC STUDY OF MISTRA M5 TEST USING LUMPED PARAMETER COCOSYS CODE , PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 5
2011
- Approach to Phebus containment nodalisation for lumped-parameter codes , International Congress on Advances in Nuclear Power Plants (ICAPP '11)
- Modeling of atmosphere stratification in containments of nuclear power plants using lumped-parameter code , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2011.05.030
- Sprays in containment: Final results of the SARNET spray benchmark , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2011.03.016
2010
- Accident Management for NPPS with RBMK Reactors
- Modeling of atmosphere stratification in containments of nuclear power plants,Stratifikuotos atmosferos susidarymo atominių elektrinių apsauginiuose kiautuose modeliavimas , Energetika
- Heat transfer to the building structures of the Ignalina NPP accident localisation system , KERNTECHNIK — DOI: 10.3139/124.110059
- Integral analysis of large LOCA beyond design basis accident scenario in RBMK-1500 , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2009.10.016
2009
- Simulation of hydrogen distribution at the Ignalina NPP confinement during BDBA,Vandenilio pasiskirstrstymo Ignalinos ae apsauginiame kiaute analize nepr ojektines avarijos metu , Energetika
- Analysis of aerosol deposition in PHEBUS containment during FPT-1 experiment , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2009.03.012
2008
- Simulation of MASP-n experiments performed in mistra test facility using code COCOSYS,MISTRA stende vykdytu̧ MASP-n eksperimentu̧ modeliavimas COCOSYS programu̧ paketu , Energetika
- Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500 , KERNTECHNIK — DOI: 10.3139/124.100558
- Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant , KERNTECHNIK — DOI: 10.3139/124.100540
- Approach to accident management in RBMK-1500 , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2007.06.003
- Simulation of MASPn Experiments in MISTRA Test Facility with COCOSYS Code , Science and Technology of Nuclear Installations — DOI: 10.1155/2008/896406
2007
- Influence of nodalisation and modelling parameters on the results of calculation of aerosol deposition in the phebus experimental facility,Skaičiavimo modelio ir modeliavimo parametru̧ i̧taka aerozoliu̧ nusėdimo skaičiavimams PHEBUS eksperimentu̧ stende , Energetika
- Processes in the fuel elements of nuclear power plants and their modeling,RBMK-1500 šiluma̧ işskiriančiuose elementuose vykstančiu̧ procesu̧ modeliavimas , Energetika
- Safety analysis of beyond design basis accidents in RBMK-1500 reactors , ANNALS OF NUCLEAR ENERGY — DOI: 10.1016/J.ANUCENE.2007.01.011
2006
- SARNET Spray Benchmark — DOI: 10.13140/RG.2.1.4787.3765
- The Specifics of RBMK Core Cooling at Overheated Conditions , Volume 2: Thermal Hydraulics — DOI: 10.1115/icone14-89337
- Simulation of Hydrogen Distribution in Ignalina NPP ALS Compartments During BDBA , Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition — DOI: 10.1115/icone14-89173
- Probabilistic and deterministic analysis of BDBA in RBMK-1500 , Energetika
- Application of RELAP/SCOAPSIM and COCOSYS codes for severe accident analysis in RBMK-1500 reactor , Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
- Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS , KERNTECHNIK — DOI: 10.3139/124.100300
- Analyses of severe accident scenarios in RBMK-1500 , KERNTECHNIK — DOI: 10.3139/124.100298
2005
- Simulation of the hydrogen distribution in the confinement of the Ignatina nuclear power plant , Kerntechnik
- Level 2 PSA approach for Ignalina RBMK-1500 reactor in Lithuania , Advances in Safety and Reliability - Proceedings of the European Safety and Reliability Conference, ESREL 2005
- Investigation of hydrogen control system effectiveness in RBMK-1500 containment , Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05
- Simulation of the hydrogen distribution in the confinement of the Ignalina nuclear power plant , KERNTECHNIK — DOI: 10.3139/124.100256
2004
- COCOSYS code validation against measured data during unintended single main safety valve opening at Ignalina NPP , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2004.06.002
- Reactor cavity and ALS thermal-hydraulic evaluation in the case of fuel channels ruptures at Ignalina NPP , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/J.NUCENGDES.2004.04.002
2003
- Sensitivity and Uncertainty Analysis for Ignalina NPP Confinement in Case of Loss of Coolant Accident , International Conference - Nuclear Energy for New Europe, Proceedings
- Benchmark analysis of unintended simultaneous opening of three main steam relief valves at Ignalina nuclear power plant , Kerntechnik
- Benchmark analysis of unintended simultaneous opening of three main steam relief valves at Ignalina nuclear power plant , KERNTECHNIK
- Heat transfer to the building structures of ignalina NPP accident localization system , Advances in Heat Transfer Engineering, Proceedings
2002
- Mass/energy release influence to thermal hydraulics of accident localisation system at Ignalina NPP in case of MDBA , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE10-22474
- Safety assessment and improvement of Ignalina NPP against downcomer ruptures outside accident localisation system , International Conference - Nuclear Energy for New Europe, Proceedings
- Simulation of Ignalina NPP accident localisation system behaviour employing the RALOC4 code in the case of group distribution header rupture , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/S0029-5493(02)00031-6
- RALOC4 code validation against measured data at Ignalina NPP during single Main Safety Valve opening , NUCLEAR ENGINEERING AND DESIGN — DOI: 10.1016/S0029-5493(02)00027-4
2000
- Thermal-hydraulic evaluation of Ignalina NPP response to steam-line rupture , Nuclear Energy
- Thermal-hydraulic evaluation of Ignalina NPP response to steam-line rupture , NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY
1999
International projects
Horizon Europe
The EASI-SMR project intends to address the safety issues related to the LW-SMR in order to provide advances that should support implementation of such technologies as soon as possiblMore
Small Modular Reactors (SMR) are one of the key options for the near-term deployment of new nuclear reactors. Currently in Europe there is a growing interest towards the deployment ofMore
LEI coordinated project "Towards harmonisation in licensing of future nuclear power technologies in Europe" (HARMONISE). Innovative fission and fusion installations encompass novelMore
EUROfusion’s updated Fusion Research Roadmap aims to acquire the necessary knowledge to start constructing a demonstration fusion power plant (DEMO) five years after ITER is in full-pMore
Horizon 2020
ELSMOR (towards European Lisencing of Small MOdular Reactors) aims to create methods and tools for the European stakeholders to assess and verify the safety of light water small modulMore
The overall objective of the MUSA project is to assess the capability of SA codes when modelling reactor and SFP accident scenarios of GEN II, GEN III and GEN III+ reactor designs. ToMore
The FASTNET project is a four-years European project funded by the Euratom Research and Training Programme 2014-2018. This project has received funding from the Euratom research and tMore
The region of the European Union around the Baltic sea especially the countries Estonia, Latvia and Lithuania are not adequately integrated to the European electricity grid. At the enMore
The goal of the project is an analysis of the applicability and technical feasibility of the IVMR strategy to high power reactors, both for existing ones (e.g. VVER 1000 type 320 unitMore
EUROfusion, the ‘European Consortium for the Development of Fusion Energy’, manages and funds European fusion research activities on behalf of Euratom. Thirty members*, representing More
Seventh Framework Programme (FP7)
The ARCADIA project has been conceived so as to provide a twofold support to the further development of nuclear research programs in the NMS, targeting two major areas included in theMore
The strategic objective of NC2I-R is to structure the European public and private R&D capabilities for delivering a nuclear cogeneration demonstrator fully meeting the market needMore
The objective of the NUGENIA+ project is to support the NUGENIA Association in its role to coordinate and integrate European research on safety of the Gen II and III nuclear installatMore
Since 2013, LEI participated in the Consortium, managed by the Institut de Radioprotection et de Sûreté Nucléaire (IRSN), by implementing EU Seventh Framework Programme project AdvancMore
The Fukushima accidents highlighted that both the in-depth understanding of such sequences and the development or improvement of adequate severe accident management measures is essentMore
The European Sustainable Nuclear Industrial Initiative was launched in November 2010 to anticipate the development a fleet of fast reactors with closed cycle. Three fast neutron technMore
Most of the actors involved in severe accident research in Europe, plus Canada, Korea and the United States (41 partners), will network in SARNET2 (Severe Accident Research NETwork ofMore
Today, about 80% of all energy produced comes from the fossil fuel (oil, carbon, and natural gas). European scientists are developing environmentally friendly, safe, and renewable eneMore
Sixth Framework Programme (FP6)
In 2006 scientists of LEI implemented a first ITER safety justification project, which was supported through the EC FP-6 program. The objective of the project was to investigate if hyMore
The Network of Competency SARNET – the project for the Integration and management of severe accidents phenomena in research in Europe – was launched in March, 2004. The SARNET projectMore
Nordic Energy Research Programme (NERP)
Establishment of Nordic-Baltic PhD and researcher mobility network in the field of the bioenergy (REMONET-Bioenergy) NERP (Nordic Energy Programme). Period of project implementatiMore