Publications
https://orcid.org/0000-0002-9723-502X
2026
- Assessment of Monel 400 corrosion in hydrofluoric–hydrochloric acid condensation environments for condensing heat exchangers , Thermal Science and Engineering Progress — DOI: 10.1016/j.tsep.2026.104642
2025
- The effect of storage conditions and computer model simplification on the thermal state of the RBMK-1500M2 cask , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2025.103729
- Modelling the Impact of Engineered Barrier Degradation on Radionuclide Release from a Lithuanian Near-Surface Repository , Applied Sciences — DOI: 10.3390/app152212253
2024
- Experimental investigation of water vapor condensation from hot humidified air in serpentine heat exchanger , International Journal of Heat and Mass Transfer — DOI: 10.1016/j.ijheatmasstransfer.2023.125068
- Experimental investigation of humidified air condensation in different rows of serpantine heat exchanger – Cooling water flow rate effect , Thermal Science and Engineering Progress — DOI: 10.1016/j.tsep.2024.102814
2022
- The Modeling of Laboratory Experiments on Granular MX-80 Bentonite with COMSOL Multiphysics , Minerals — DOI: 10.3390/min12030277
- Flue Gas Condensation in a Model of the Heat Exchanger: The Effect of the Cooling Water Flow Rate and Its Temperature on Local Heat Transfer , Applied Sciences — DOI: 10.3390/app122412650
- The modeling of transient phase changes of water droplets in flue gas flow in the range of temperatures characteristic of condensing economizer technologies , Energy — DOI: 10.1016/j.energy.2022.124719
- A proposed approach for the evaluation of consequences of a large aircraft crash accident at an RBMK type reactor site during decommissioning , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2022.104135
2021
- A numerical study of thermal behavior of CASTOR RBMK-1500 cask under fire conditions , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2021.111131
- An experimental investigation of water vapor condensation from biofuel flue gas in a model of condenser, (2) local heat transfer in a calorimetric tube with water injection , Processes — DOI: 10.3390/pr9081310
- Comparison of gamma and neutron dose rate variations with time for cast iron and metal—concrete casks used for RBMK-1500 spent fuel storage , Applied Sciences (Switzerland) — DOI: 10.3390/app11167362
- Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2020.11.022
- A review of uncertainties in the assessment of the radiological impact of liquid releases to the Ignalina NPP cooling pond lake Drūkšiai , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2021.108228
- An experimental investigation of water vapor condensation from biofuel flue gas in a model of condenser, (1) base case: Local heat transfer without water injection , Processes — DOI: 10.3390/pr9050844
- The influence of droplet dispersity on droplet vaporization in the high-temperaturewet gas flow in the case of combined heating , Sustainability (Switzerland) — DOI: 10.3390/su13073833
- The modeling of laboratory experiments with comsol multiphysics using simplified hydromechanical model , Minerals — DOI: 10.3390/min11070754
2020
- Modeling radionuclide migration from activated metallic waste disposal in a generic geological repository in Lithuania , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2020.110885
2019
- Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings , Science and Technology of Nuclear Installations — DOI: 10.1155/2019/8736173
- Disposal of very low-level radioactive waste: Lithuanian case on the approach and long-term safety aspects , Science of the Total Environment — DOI: 10.1016/j.scitotenv.2019.02.373
- Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel , Energy — DOI: 10.1016/j.energy.2018.12.217
- Uncertainty and sensitivity analysis at low value of determination coefficient of regression analysis: Case of i-129 release from rbmk-1500 snf under disposal conditions , Minerals — DOI: 10.3390/min9090521
2018
- Investigation of characteristics of solid particles from a mixture of sewage sludge and wood pellets synthetic gas and their clean-up , Waste Management — DOI: 10.1016/j.wasman.2018.05.025
- Investigation of warm gas clean-up of biofuel flue and producer gas using electrostatic precipitator , Energy — DOI: 10.1016/j.energy.2017.11.120
- Estimation of the inventory of <sup>14</sup> C and other key radionuclides in irradiated RBMK-1500 graphite based on limited measurements and full 3D core modeling , Radiocarbon — DOI: 10.1017/RDC.2018.122
- Preliminary investigation of <sup>14</sup> C migration from RBMK-1500 reactor graphite disposed of in a potential geological repository in crystalline rocks in Lithuania , Radiocarbon — DOI: 10.1017/RDC.2018.139
- Estimation of the radiation doses during the dismantling of the equipment in Building 117/1 at the Ignalina NPP , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2018.07.018
2017
- Investigation of the biofuel flue and producer gases cleaning efficiency using ESP , E3S Web of Conferences — DOI: 10.1051/e3sconf/20172200138
- Thermal analysis of CASTOR RBMK-1500 casks during long-term storage of spent nuclear fuel , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2016.09.031
- Investigation of the ESP cleaning efficiency of the flue gases in the wide range of Re numbers , Mechanika — DOI: 10.5755/j01.mech.23.1.14226
- Evaluation of dose rate variation during very long term storage of RBMK-1500 reactor used fuel , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2017.03.050
2016
- Modelling of RBMK-1500 SNF storage casks activation during very long term storage , Applied Radiation and Isotopes — DOI: 10.1016/j.apradiso.2016.06.015
- Modelling of the spatial distribution of the induced activities in the RBMK-1500 reactor graphite blocks and rings/sleeves , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2016.05.005
- Modeling of irradiated graphite <sup>14</sup>C transfer through engineered barriers of a generic geological repository in crystalline rocks , Science of the Total Environment — DOI: 10.1016/j.scitotenv.2016.06.186
- Progress in the implementation of the radwaste disposal facilities in Lithuania and their safety assessment,Pažanga įgyvendinant radioaktyviųjų atliekų atliekynus Lietuvoje ir jų saugos vertinimas , Energetika — DOI: 10.6001/energetika.v62i3.3353
- Updating of the public dose assessment approach for decommissioning related releases from the Ignalina NPP , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2016.02.028
- Gas migration modelling in geological repository module in clay formation and sensitivity analysis , Engineering Geology — DOI: 10.1016/j.enggeo.2016.09.007
2015
- Temperature and tortuosity effect on gas migration in a high-level waste disposal tunnel , Mineralogical Magazine — DOI: 10.1180/minmag.2015.079.6.07
- Uncertainty and sensitivity analysis of radionuclide migration through the engineered barriers of deep geological repository: Case of RBMK-1500 SNF , Reliability Engineering and System Safety — DOI: 10.1016/j.ress.2014.11.011
- Modeling of the radiation doses during dismantling of RBMK-1500 reactor emergency core cooling system large diameter pipes , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2015.04.034
- Methodology for the scoping assessment of radioactive releases during dismantling of RBMK-1500 reactor systems with low-level contamination , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2014.08.027
- Analysis of the radiological contamination of the RBMK-1500 reactor low salted water system , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2015.09.005
- Overview of the Lithuanian programme for disposal of RBMK-1500 spent nuclear fuel , Mineralogical Magazine — DOI: 10.1180/minmag.2015.079.6.33
2014
- Investigation of collection efficiency of electrostatic precipitator for small heating appliances , 9th International Conference on Environmental Engineering, ICEE 2014 — DOI: 10.3846/enviro.2014.044
- Investigation of Air Flow Distribution in Small-Scale Food Products Dryer , Drying Technology — DOI: 10.1080/07373937.2014.903411
- Comparison of radionuclide releases from a conceptual geological repository for RBMK-1500 and BWR spent nuclear fuel , Nuclear Technology — DOI: 10.13182/NT13-52
- Modelling of rbmk spent nuclear fuel characteristics , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE22-31005
- The environmental impact assessment process for nuclear facilities: A review of the Lithuanian practice and experience , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2014.01.014
- Numerical modelling of radionuclide inventory for RBMK irradiated nuclear fuel , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2014.06.014
- Modelling of the radiological contamination of the RBMK-1500 reactor water purification and cooling system , Science and Technology of Nuclear Installations — DOI: 10.1155/2014/293158
- Thermal analysis of reference repository for RBMK-1500 spent nuclear fuel in crystalline rocks , Journal of Thermal Analysis and Calorimetry — DOI: 10.1007/s10973-014-3919-8
2013
- Analysis of radionuclide release through EBS of conceptual repository for Lithuanian RBMK spent nuclear fuel disposal - case of canister with initial defect , Nukleonika
- Modeling of the radiation doses during dismantling of rbmk-1500 reactor pressurized tanks from emergency core cooling system , Science and Technology of Nuclear Installations — DOI: 10.1155/2013/576432
- Analysis of radwaste management alternatives during dismantling of Ignalina NPP systems with low level contamination , Kerntechnik — DOI: 10.3139/124.110396
- Prediction of radiation doses during the dismantling of the pressurized tank from emergency core cooling system of RBMK-1500 reactor , Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM — DOI: 10.1115/ICEM2013-96220
2012
- Impact of different factors on gas migration in the disposal cell of conceptual geological repository for high level radioactive waste , Mechanika — DOI: 10.5755/j01.mech.18.6.3172
- Heat transfer in the initial part of thermal stabilization of helical channels in air flow , Heat Transfer Research — DOI: 10.1615/HeatTransRes.v43.i5.40
- Enhancement of heat transfer and hydraulic drag in gas-cooled helical channels with artificial roughness on convex wall , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2012.01.026
- Progress of radioactive waste management in Lithuania , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2011.09.008
- Numerical investigation of the opposing mixed convection in an inclined flat channel using turbulence transition models , Journal of Physics: Conference Series — DOI: 10.1088/1742-6596/395/1/012098
2011
- Modelling of thermo-hydro-mechanical processes in a geological repository of spent nuclear fuel,Termo-hidro-mechaninių procesų panaudoto branduolinio kuro giluminiame kapinyne modeliavimas , Energetika
- Thermal analysis of new casks for spent nuclear fuel storage at the new ignalina NPP storage facility,Naujų panaudoto branduolinio kuro saugojimo konteinerių naujojoje Ignalinos AE saugykloje šiluminis įvertinimas , Energetika
- Modelling of radiation fields and radiation doses for the personnel during dismantling the RBMK-1500 reactor emergenc y core cooling system 2. dismantling hydro-accumulative tanks,Jonizuojančiosios spinduliuotės laukų ir apšvitos dozių darbuotojams modeliavimas išmontuojant RBMK-1500 reaktoriaus avarinio aušinimo sistemą 2. Hidroakumuliacinių balionų išmontavimas , Energetika
- Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant , Kerntechnik — DOI: 10.3139/124.110174
- Heat transfer in helical channels with two-sided heating in gas flow , International Journal of Heat and Mass Transfer — DOI: 10.1016/j.ijheatmasstransfer.2010.10.017
- Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning , Kerntechnik — DOI: 10.3139/124.110169
- Experimental investigation of opposing mixed convection hear transfer in the vertical flat channel in a laminar-turbulent transition region , International Journal of Heat and Mass Transfer — DOI: 10.1016/j.ijheatmasstransfer.2010.09.004
2010
- Evaluation of nuclear and radiation characteristics of steel disposal canister for RBMK-1500 spent nuclear fuel,RBMK-1500 panaudoto branduolinio kuro plieninio laidojimo konteinerio branduoliniu ir radiaciniu charakteristiku skaitinis vertinimas , Energetika
- Experimental investigation of the impact of air density stratification on mixed convection in the flat channel in the transition region: 1. Opposing mixed convection heat transfer in an inclined(Φ =-60°)channel,Oro tankio stratifikacijos itakos mišriai konvekcijai plokščiame kanale pereinamojo tekejimo zonoje eksperimentinis tyrimas , Energetika
- Modelling of radiation fields and radiation doses for the personnel during dismantling the RBMK-1500 reactor emergency core cooling system 1. dismantling of large diameter pipes,Jonizuojančiosios spinduliuotės laukų ir apšvitos dozių darbuotojams modeliavimas išmontuojant RBMK-1500 reaktoriaus avarinio aušinimo sistemą 1. didelio skersmens vamzdžių išmontavimas , Energetika
- Modelling of temperature variation in the reference geological repository of the RBMK-1500 spent nuclear fuel 2. Temperature va riation in the repository in crystalline rocks,Panaudoto RBMK-1500 branduolinio kuro, palaidoto konceptualiame kapinyne, temperatūros kitimo modeliavimas 2. Temperatūros kitimas kristalinėse uolienose įrengtame kapinyne , Energetika
- Numerical modelling of the impact of air density stratification on mixed convection in the flat channel 1. Opposing mixed convection heat transfer in the transition region of the inclined (φ = -60°) channel,Mišrios konvekcijos esant priešingų krypčių tėkmėms ir oro tankio stratifikacijos sąveikos skaitinis modeliavimas plokščiame kanale 1. Šilumos atidavimas ir hidrodinamika pereinamojo tekėjimo zonoje, kai kanalo polinkio kampas φ = -60° , Energetika
- Assessment of different mechanisms of C-14 production in irradiated graphite of RBMK-1500 reactors , Kerntechnik — DOI: 10.3139/124.110083
- Opposing mixed convection heat transfer in the inclined flat channel in a laminar-turbulent transition region , 2010 14th International Heat Transfer Conference, IHTC 14 — DOI: 10.1115/IHTC14-22871
2009
- Heat transfer in the initial part of thermal stabilization of helical channels in air flow,Šilumos atidavimas sraigtinių kanalų pradinėje šiluminės stabilizacijos dalyje oro sraute , Energetika
- Numerical modelling of neutron activation processes in reactor RBMK-1500 structural elements: 3. Modelling of neutron activation proceses in fuel chanels employing modeled Neutron fluxes,Reaktoriaus RBMK-1500 konstrukcinių elementų neutroninės aktyvacijos skaitinis vertinimas: 3. Kuro kanalų neutroninės aktyvacijos vertinimas naudojant sumodeliuotus neutronų srautus , Energetika
- Modelling of temperature variation in the reference geological repository of the RBMK-1500 spent nuclear fuel: 1. Temperature variation in the repository clay formations,Panaudoto RBMK-1500 branduolinio kuro, palaidoto konceptualiame kapinyne, temperaturos kitimo Modeliavimas: 1. temperatūros kitimas molingose uolienose įrengtame kapinyne , Energetika
- Neutron activation in the metal structures of an RBMK-1500 reactor , Nuclear Technology — DOI: 10.13182/NT09-A9239
- Numerical simulation of turbulent mixed convection heat transfer in a vertical flat channel for aiding flows , Heat Transfer Research — DOI: 10.1615/HeatTransRes.v40.i5.60
- Modeling of radionuclide releases from the geological repository for RBMK-1500 spent nuclear fuel in crystalline rocks in Lithuania , Proceedings of the ICEM2007 - 11th International Conference on Environmental Remediation and Radioactive Waste Management — DOI: 10.1115/ICEM2007-7272
- Mixed convection in channel flows , Heat Transfer Research — DOI: 10.1615/HeatTransRes.v40.i1.30
- Numerical simulation of turbulent mixed convection heat transfer variation along a vertical flat channel for aiding flows , Heat Transfer Research — DOI: 10.1615/HeatTransRes.v40.i5.70
- Environmental safety aspects of the new spent nuclear fuel management and storage system at Ignalina NPP , Proceedings of the ICEM2007 - 11th International Conference on Environmental Remediation and Radioactive Waste Management — DOI: 10.1115/ICEM2007-7248
- Modeling of radiation fields and estimation of doses during dismantling of RBMK-1500 reactor emergency core cooling system , Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM — DOI: 10.1115/ICEM2009-16247
2008
- Numerical modelling of neutron activation processes in the reactor RBMK-1500 structural elements 2. Numerical modelling of neutron activation processes in shielding and support plates,Reaktoriaus RBMK-1500 konstrukciniu̧ elementu̧ neutroninės aktyvacijos skaitinis vertinimas 2. Atraminiu̧ ir apsauginiu̧ plieno plokščiu̧ neutroninės aktyvacijos skaitinis vertinimas , Energetika
- Assessment of radionuclide migration from the near-surface repository planned in Lithuania 2. Apvardai site,Radionuklidu̧ sklaidos iš numatomo Lietuvoje paviršinio radioaktyviu̧ju̧ atlieku̧ kapinyno vertinimas 2. Apvardu̧ aikštelė , Energetika
- Temperature distribution assessment for spent nuclear fuel casks at the ignalina NPP storage facility,Ignalinos AE saugyklos panaudoto branduolinio kuro konteineriu̧ temperatūru̧ pasiskirstymo i̧vertinimas , Energetika
- Radionuclide migration from the geological repository of the RBMK-1500 spent nuclear fuel in crystalline rocks 4. Radionuclide release from the far field,Radionuklidu̧ sklaida iš kristalinėse uolienose i̧rengto geologinio kapinyno RBMK-1500 panaudotam branduoliniam kurui laidoti 4. Radionuklidu̧ sklaida tolimojo lauko aplinkoje , Energetika
- Experimental investigation of opposing turbulent mixed-convection heat transfer in an inclined flat channel with one-sided heating. 3. Investigations for an inclination angle ψ = 20° and generalization of the data , Heat Transfer Research — DOI: 10.1615/heattransres.v39.i8.100
- Impact of spatial heterogeneity of source term in near-surface repository on releases to groundwater pathway , Nuclear Technology — DOI: 10.13182/NT08-A3919
- Experimental investigation of opposing turbulent mixed-convection heat transfer in an inclined flat channel with one-sided heating. 2. Heat transfer variation along inclined flat channels , Heat Transfer Research — DOI: 10.1615/heattransres.v39.i8.90
2007
- Evaluation of potential sites for landfill-type radioactive waste repositories 1. Analysis of the radionuclide migration by water pathway,Landfill tipo radioaktyviu̧ju̧ atlieku̧ kapinynui numatytu̧ aikšteliu̧ i̧vertinimas 1. Radionuklidu̧ sklaidos vandens keliu analizė , Energetika
- Radionuclide migration from the geological repository of the RBMK-1500 spent nuclear fuel in crystalline rocks 3. Radionuclide release from the near field,Radionuklidu̧ sklaida iš kristalinėse uolienose i̧rengto geologinio kapinyno RBMK-1500 panaudotam branduoliniam kurui laidoti 3. Radionuklidu̧ sklaida artimojo lauko aplinkoje , Energetika
- Assessment of radionuclide migration from the near-surface repository planned in Lithuania 1. Galilaukė site,Radionuklidu̧ sklaidos iš numatomo Lietuvoje paviršinio radioaktyviu̧ju̧ atliekiu̧ kapinyno vertinimas 1. Galilaukės aikštelė , Energetika
2006
- Fire hazard analysis at the first unit of the Ignalina nuclear power plant 3. Detailed analysis and generalized results,Gaisru̧ pavojaus Ignalinos AE pirmajame bloke analizė 3. Išsami analizė ir apibendrinantys rezultatai , Energetika
- Analysis of the impact of heterogeneities in source distribution on radionuclide releases from near-surface repository to groundwater 2. Assessment of the impact of heterogeneities,Radioaktyviu̧ju̧ atlieku̧ heterogeniškumo i̧takos radionuklidu̧ sklaidai iš paviršinio kapinyno gruntiniais vandenimis analizė 2. Heterogeniškumo i̧takos i̧vertinimas , Energetika
- Investigations of mixed convection in channel flows,Mišrios konvekcijos tyrimai kanaluose , Energetika
- Numerical simulation of mixed convection in vertical flat channel in case of transitional region for aiding flows 1. Analysis of flow structure,Mišrios konvekcijos skaitiniai tyrimai vertikaliame plokščiame kanale pereinamojo tekėjimo zonoje esant vienkryptėms tėkmėms 1. Tėkmės struktūros analizė , Energetika
- Opposing flow turbulent mixed-convection heat transfer in a vertical flat channel with one-sided heating , Heat Transfer Research — DOI: 10.1615/HeatTransRes.v37.i1.20
- Experimental investigation of opposing turbulent mixed-convection heat transfer in an inclined flat channel with one-sided heating. 1. Method and investigations for an inclination angle φ = 6°0 , Heat Transfer Research — DOI: 10.1615/HeatTransRes.v37.i1.30
- Storage of spent nuclear fuel and perspectives for IT disposal,Panaudoto branduolinio kuro saugojimas ir jo laidojimo perspektyvos , Energetika
- Radionuclide migration from the geological repository of the RBMK-1500 spent nuclear fuel in crystalline rocks: 2. Identification of safety-relevant radionuclides for a geological repository,Radionuklidu̧ sklaida iš kristalinėse uolienose i̧rengto geologinio kapinyno RBMK-1500 panaudotam branduoliniam kurui laidoti: 2. Geologinio kapinyno saugos vertinimui svarbiu̧ radionuklidu̧ identifikavimas , Energetika
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant , Kerntechnik — DOI: 10.3139/124.100297
2005
- Safety aspects of the new liquid radioactive waste solidification system at Ignalina NPP , Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05
- Progress in preparation for Decommissioning at Ignalina NPP , Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05
- The development of the radioactive waste inventory for MAISIAGALA repository , Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05
- Local turbulent opposing mixed convection heat transfer in inclined flat channel for unstably stratified airflow , International Journal of Heat and Mass Transfer — DOI: 10.1016/j.ijheatmasstransfer.2004.09.025
- Modelling of the shielding capabilities of the existing solid radioactive waste storages at Ignalina NPP , Radiation Protection Dosimetry — DOI: 10.1093/rpd/nci212
- Fire hazard analysis at Ignalina Nuclear Power Plant , Kerntechnik — DOI: 10.3139/124.100246
- Modelling of activation processes for GR-280 graphite at Ignalina NPP , Radiation Protection Dosimetry — DOI: 10.1093/rpd/nci118
2004
- Turbulent mixed convection heat transfer in channels , Heat Transfer Research — DOI: 10.1615/HeatTransRes.v35.i78.60
2003
- Local turbulent opposing mixed convection heat transfer in inclined flat channel for stably stratified airflow , International Journal of Heat and Mass Transfer — DOI: 10.1016/S0017-9310(03)00232-1
- Management of institutional radioactive waste in Lithuania , Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM — DOI: 10.1115/ICEM2003-4877
- Experience from safety assessment of the existing storage facility for solid radwaste at Ignalina NPP , Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM — DOI: 10.1115/ICEM2003-4650
2002
- Experimental investigation of local heat transfer and skin friction in tube coils , Journal of Thermal Science — DOI: 10.1007/s11630-002-0060-y
2001
- Radwaste management activities in Lithuania in relation with preparation for decommissioning of Ignalina NPP Unit 1 , Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM
1996
- Turbulent mixed convection in channels for different orientations of them in space , Inzhenerno-Fizicheskii Zhurnal — DOI: 10.1007/bf02606108
1995
- Experimental investigation of turbulent mixed-convection heat transfer in a vertical tube for different pressure of air , Advances in Engineering Heat Transfer
1994
- Turbulent heat transfer in a flat channel with stable and unstable stratification in the flow , Nuclear Engineering and Design — DOI: 10.1016/0029-5493(94)90292-5
1993
- Turbulent heat transfer in tubes at low Reynolds numbers , Heat Transfer Research
- Heat transfer and flow in spiral channels and coils , Journal of Engineering Physics and Thermophysics — DOI: 10.1007/BF01089953
- Heat transfer and hydraulic drag in helical channels in gas flow , International Journal of Heat and Mass Transfer — DOI: 10.1016/S0017-9310(05)80079-1
1992
- Dynamics of transitional flow in a curved square duct , Fluid Mechanics Research
- Local heat transfer in a vertical gas-cooled tube with turbulent mixed convection and different heat fluxes , International Journal of Heat and Mass Transfer — DOI: 10.1016/0017-9310(92)90084-6
1991
- Coefficients of local heat transfer for the initial thermal stabilization zone of coiled tubes , Heat transfer. Soviet research
- Correlation of results on local coefficients of heat transfer in helical ducts , Heat transfer. Soviet research
- Numerical analysis of turbulent transport in combined (forced and free) convection in vertical channels , Heat transfer. Soviet research
- Effect of variability of the physical properties of the gas on combined (free and forced) convection heat transfer in vertical pipes , Heat transfer. Soviet research
- Heat transfer in transition flow of air at high heat fluxes [(4. correlation of data on combined (free and forced) convection in the case of constant physical properties of the flow)] , Heat transfer. Soviet research
1990
- Local heat transfer in coiled tubes at high heat fluxes (1. Experimental unit, technique and results of preliminary experiments) , Heat transfer. Soviet research
- Turbulent transport in helical ducts (1. Experimental unit, procedure and preliminary experiments , Fluid mechanics. Soviet research
- Enhancement of heat transfer in gas-cooled helical ducts , Fluid mechanics. Soviet research
- Correlations between turbulent velocity and temperature fluctuations in pipe flows of various coolants (2.Effects of Prandtl number) , Fluid mechanics. Soviet research
- Local shear stress on the wall of a coiled tube (3.Fluctuations of shear stress) , Fluid mechanics. Soviet research
- Local shear stress on the wall of a coiled tube (4. Inlet region) , Fluid mechanics. Soviet research
- Correlations of turbulent velocity and temperature fluctuations for pipe flow of different fluids. (1. Principal assumptions and equations and an experimental verification) , Fluid mechanics. Soviet research
- Investigation of heat transfer Prandtl number dependence by u′t′ and v′t′ solutions , International Journal of Heat and Fluid Flow — DOI: 10.1016/0142-727X(90)90020-C
1989
- Heat transfer to a transition-range gas flow in a pipe at high heat fluxes. (3. Effect of buoyancy on local heat transfer in forced turbulent flow) , Heat transfer. Soviet research
- Local shear in the flow at the wall of a coiled tube (2. Effect of coil curvature) , Heat transfer. Soviet research
- Thermohydraulic properties (coefficients of local heat transfer and hydraulic drag) of helical channels. (1. Experimental unit, procedure, and preliminary experiments) , Fluid mechanics. Soviet research
- Balance of the energy of turbulence of a gas flow in the inlet zone of a pipe , Fluid mechanics. Soviet research
- Thermohydraulics of helical ducts. (2. Effect of relative width and curvature) , Fluid mechanics. Soviet research
- Numerical analysis of turbulent momentum and heat transfer in mixed convection in vertical annuli , Heat transfer. Soviet research
- Heat transfer to a transition-range gas flow in a pipe at high heat fluxes. (2. Heat transfer in laminar to turbulent flow transition) , Heat transfer. Soviet research
1988
- Local shear stress on the wall of a coiled tube (1. Procedure and results for a coil with D/d = 13.3 in a stabilized air flow) , Heat transfer. Soviet research
1987
- HEAT TRANSFER TO A TRANSITION-RANGE GAS FLOW IN A PIPE AT HIGH HEAT FLUXES (1. EXPERIMENTAL EQUIPMENT AND RESULTS. PRELIMINARY EXPERIMENTS). , Heat transfer. Soviet research
- LOCAL HEAT TRANSFER COEFFICIENTS AND PRESSURE DROP IN AIR FLOW THROUGH HELICAL ANNULAR DUCTS. , Heat transfer. Soviet research
- NUMERICAL ANALYSIS OF MOMENTUM AND HEAT TRANSFER IN VERTICAL TUBES IN COMBINED (MIXED) TURBULENT CONVECTION. , Heat transfer. Soviet research
1986
- STUDY OF HEAT TRANSFER IN VERTICAL CHANNELS FOR HIGH HEAT LOADS IN THE TRANSITION REGION. , Heat Transfer, Proceedings of the International Heat Transfer Conference
1985
- SWIRLING FLOW IN NARROW ANNULI WITH TANGENTIAL AIR INLETS. , Fluid mechanics. Soviet research
1984
- CONVERSION OF DATA ON HEAT TRANSFER AND DRAG OF ANNULI WITH ROUGH INNER TUBE FOR PURPOSES OF PREDICTION OF HYDRAULIC AND THERMAL BEHAVIOR OF COMPLETELY ROUGH ANNULI AND TUBE BUNDLES. , Heat transfer. Soviet research
1983
- FLUCTUATIONS OF VELOCITY OF CROSS FLOW OF AIR IN THE SPACE BETWEEN TUBES IN BUNDLES. , Heat transfer. Soviet research
1979
- HYDRAULIC DRAG AND PATTERN OF AIR FLOW IN CROSSFLOW OVER DIFFERENT ROWS OF BUNDLES AT HIGH Re. , Fluid mechanics. Soviet research
International projects
Horizon Europe
EURAD-2 builds upon EURAD-1 and PREDIS to further implement a joint strategic programme of research, development and knowledge management activities at the European level, bringing toMore
The project aims to establish and clarify the benefits and added value of more aligned and harmonised regulations and standards for prioritised topics related to decommissioning and iMore
Horizon 2020
The European Green Deal, an ambitious growth strategy aligned with the Sustainable Development Goals (SDG), calls for the mobilization of the industry. Indeed, while important steps hMore
Following decades of RD&D in support of the safe management and disposal of radioactive waste, and building on the preparatory work of the recent EC JOPRAD project, a European JoiMore
According to the projections based on likely remaining life-times of the World’s legacy nuclear fleet, the workload and budgets to be dedicated for nuclear decommissioning is going toMore
Safe management of radioactive waste is challenging to waste producers and waste management organisations. Deployment of thermal treatment in an optimised waste management lifecycle cMore
The overall objective of the project is to develop and test the tools necessary for the assessment of the hydro-mechanical evolution of an installed bentonite barrier and its resultinMore
The coordination action SITEX-II aims at implementing in practice the activities along with the interaction modes issued by the FP7 program SITEX project (2012-2013), in view of develMore
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 CAST project (CArbon-14 Source Term) aims to develop understanding of the generation and release of 14C from radioactive waste materials under conditions relevant to waste packagiMore
The objective of PLATENSO is to provide a proposal towards establishing the legal base for a European Entity on Socio-Economic matters linked to nuclear technology and to develop recoMore
SITEX aims at identifying the efficient means that should be developed through the establisment of a sustainable expertise function network within a European framework with the view tMore
NEWLANCER project proposes to identify and implement effective and efficient actual solutions leading to enlarged NMS involvement in future Euratom Framework Programmes by strengtheniMore
The multiple barrier concept is the cornerstone of all proposed schemes for underground disposal of radioactive wastes. The concept invokes a series of barriers, both engineered and nMore
Gas-Cooled Reactors (GCR), RBMK and some Material Test Reactors (MTR) make use of graphite as moderator of the fuel, structures of the core and/or thermal columns. During operation, tMore
IAEA
The present spent nuclear fuel (SNF) management concept in the Lithuania foresees dry storage of SNF for 50 years. During this time the final SNF management concept shall be developedMore
Other international projects
The goal of this project is to prepare the setting up of a “Joint Programming on Radioactive Waste Disposal” that would be established to coordinate at the European level, national reMore
Projects in Lithuania
EU Structural Funds
Some of the problems identified and tackled by the measure No 12-001-01-02-01 of Lithuania's Science Development Programme of the Ministry of Education, Science and Sport ofMore
Research Council of Lithuania projects
Comprehensive research and application of "Rūkas" technology for biofuel smoke purification and waste heat recovery ID (LMT): P-MIP-20-2 Nr.: 14-1963.20.22 Coordinator: LitMore