Algirdas Kaliatka

2026

• Virginijus Vileiniškis, Tadas Kaliatka, Mindaugas Valinčius, Algirdas Kaliatka. Application of Uncertainty and Sensitivity Analysis in Assessing the Consequences of Severe Accidents , Nuclear Technology — DOI: 10.1080/00295450.2025.2526948

2022

• Kaliatka, A., Vaišnoras, M., Valinčius, M., Kaliatka, T.. Relap5 Application for Water Hammer Analysis in Different Thermal-Hydraulic Systems , SSRN
• Ragaišis, V., Kaliatka, T., Poškas, P., Kaliatka, A., Šmaižys, A., Janulionis, R., Narkūnas, E., Sirvydas, A., Babilas, E., Rimkevičius, S.. 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
• Kaliatka, A., Vaišnoras, M., Valinčius, M., Kaliatka, T.. RELAP5 application for water hammer analysis in different thermal-hydraulic systems , International Journal of Thermofluids — DOI: 10.1016/j.ijft.2022.100154
• Graževičius, A., Šeporaitis, M., Valinčius, M., Kaliatka, A.. Numerical investigation of two-component single-phase natural convection and thermal stratification phenomena in a rod bundle with axial heat flux profile , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2022.03.010

2020

• Graževičius, A., Kaliatka, A., Ušpuras, E.. Numerical investigation of two-phase natural convection and temperature stratification phenomena in a rectangular enclosure with conjugate heat transfer , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2019.06.022
• Augutis, J., Babilas, E., Dundulis, G., Kaliatka, A., Kaliatka, T., Krikštolaitis, R., Martišauskas, L., Rimkevičius, S., Pabarčius, R., Povilaitis, M., Stankunas, G., Urbonas, R., Urbonavičius, E.. Scientific inheritance of Eugenijus Ušpuras,Wissenschaftliches Erbe von Eugenijus Ušpuras , Kerntechnik — DOI: 10.3139/124.200005

2019

• Tonkūnas, A., Slavickas, A., Kaliatka, A.. The internship of Egyptian nuclear safety specialists at Lithuanian energy institute , Energetika
• Boucherit, H., Kaliatka, A., Lounis, A.. Integrity control of an RBMK-1500 fuel rod locally oxidized under a bounding reactivity-initiated accident , Nuclear Science and Techniques — DOI: 10.1007/s41365-018-0538-2
• Kaliatka, A., Ušpuras, E.. Heat removal from RBMK reactor core using non-regular means , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2019.110165

2018

• Coindreau, O., Jäckel, B., Rocchi, F., Alcaro, F., Angelova, D., Bandini, G., Barnak, M., Behler, M., Da Cruz, D.F., Dagan, R., Drai, P., Ederli, S., Herranz, L.E., Hollands, T., Horvath, G., Kaliatka, A., Kljenak, I., Kotsuba, O., Lind, T., López, C., Mancheva, K., Matejovic, P., Matkovič, M., Steinbrück, M., Stempniewicz, M., Thomas, R., Vileiniskis, V., Visser, D.C., Vokáč, P., Vorobyov, Y., Zhabin, O.. Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2018.06.043
• Kaliatka, T., Kaliatka, A., Hohorst, J.K., Allison, C.M.. Modelling of severe accidents in spent fuel pools, analysis of the heat-up of the fuel assemblies in the steam and air environment , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2018.07.016
• Valinčius, M., Vaišnoras, M., Kaliatka, A.. Study and demonstration of pressure wave-based leak detection in a district heating network , Structure and Infrastructure Engineering — DOI: 10.1080/15732479.2017.1330892
• Kaliatka, A., Kaliatka, T.. Experts from lithuanian energy institute trained algerian specialists in the field of severe accident analysis , Energetika — DOI: 10.6001/energetika.v64i2.3786
• Valinčius, M., Kaliatka, T., Kaliatka, A., Ušpuras, E.. Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor , Science and Technology of Nuclear Installations — DOI: 10.1155/2018/7162387

2017

• Kaliatka, T., Uspuras, E., Kaliatka, A.. Integrated assessment of thermal hydraulic processes in W7-X fusion experimental facility , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2016.08.004
• Kaliatka, T., Uspuras, E., Kaliatka, A.. Analysis of ingress of coolant accident to the vacuum vessel of the W7-X fusion experimental facility , Fusion Science and Technology — DOI: 10.1080/15361055.2017.1320496
• Graževičius, A., Kaliatka, A.. Modelling of the spent fuel heat-up in the spent fuel pools using one-dimensional system codes and CFD codes , Kerntechnik — DOI: 10.3139/124.110795
• Kaliatka, T., Kaliatka, A., Uspuras, E., Vaisnoras, M., Mochizuki, H., Van Rooijen, W.F.G.. Best estimate approach for the evaluation of critical heat flux phenomenon in the boiling water reactors , Kerntechnik — DOI: 10.3139/124.110785

2016

• Kaliatka, T., Uspuras, E., Kaliatka, A.. Modelling of pressure increase protection system for the vacuum vessel of W7-X device , Fusion Engineering and Design — DOI: 10.1016/j.fusengdes.2016.03.043
• Ammirabile, L., Tuček, K., Blanc, D., Pabarcius, R., Kaliatka, A., Mansani, L., Carluec, B., Dufour, P., Homann, C.. SARGEN-IV: Consideration on the possible content of the safety analysis report for innovative ESNII reactors , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2016.02.022
• Ušpuras, E., Rimkevičius, S., Urbonavičius, E., Kaliatka, A., Dundulis, G., Alzbutas, R., Stankūnas, G., Vaišnoras, M., Vileiniškis, V., Povilaitis, M., Kaliatka, T., Janulionis, R., Karalevičius, R., Voronov, R., Iešmantas, T., Kačegavičius, T.. Nuclear fusion research at Lithuanian energy institute,Branduolių sintezės tyrimai Lietuvos energetikos institute , Energetika — DOI: 10.6001/energetika.v62i3.3349
• Šeporaitis, M., Valinčius, M., Gasiūnas, S., Laurinavičius, D., Pabarčius, R., Kaliatka, A., Almenas, K.. Investigation of interfacial interaction and condensation,Tarpfazinės sąveikos ir kondensacijos tyrimai , Energetika — DOI: 10.6001/energetika.v62i3.3355
• Kaliatka, T., Kaliatka, A., Vileiniskis, V.. Application of Best Estimate Approach for Modelling of QUENCH-03 and QUENCH-06 Experiments , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2015.12.011

2015

• Kaliatka, T., Uspuras, E., Kaliatka, A.. Modelling of Water Ingress into Vacuum Vessel Experiments Using RELAP5 Code , Journal of Fusion Energy — DOI: 10.1007/s10894-014-9790-6
• Kaliatka, T., Uspuras, E., Kaliatka, A.. Integrated assessment of thermal hydraulic processes in W7-X fusion experimental facility , International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
• Knoglinger, E., Wölfl, H., Kaliatka, A.. Heat transfer in the core graphite structures of RBMK nuclear power plants , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2015.07.008

2014

• Kaliatka, T., Ušpuras, E., Kaliatka, A.. Modelling of water ingress in to vacuum vessel , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE22-30865
• Fleurot, J., Lindholm, I., Kononen, N., Ederli, S., Jaeckel, B., Kaliatka, A., Duspiva, J., Steinbrueck, M., Hollands, T.. Synthesis of spent fuel pool accident assessments using severe accident codes , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2014.07.011
• Kaliatka, A., Vaišnoras, M., Valinčius, M.. Modelling of valve induced water hammer phenomena in a district heating system , Computers and Fluids — DOI: 10.1016/j.compfluid.2014.01.035
• Ognerubov, V., Kaliatka, A., Vileiniškis, V.. Features of modelling of processes in spent fuel pools using various system codes , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2014.06.021
• Šutas, A., Kaliatka, A., Vileiniškis, V.. Modelling of quench-3 experiment using astec code,QUENCH-3 eksperimento modeliavimas ASTEC programų paketu , Energetika — DOI: 10.6001/energetika.v60i4.3018
• Kaliatka, T., Kaliatka, A., Vileiniškis, V., Ušpuras, E.. Modelling of QUENCH-03 and QUENCH-06 experiments using RELAP/SCDAPSIM and ASTEC codes , Science and Technology of Nuclear Installations — DOI: 10.1155/2014/849480
• Valinčius, M., Šeporaitis, M., Kaliatka, A., Pabarčius, R., Gasiunas, S., Laurinavičius, D.. The concept and relap5 model of thermal-hydraulic system, employing a rapid condensation for coolant circulation , Heat Transfer Engineering — DOI: 10.1080/01457632.2013.810965
• Kaliatka, T., Kaliatka, A., Makarevicius, V.. Analysis of processes in RBMK-1500 fuel rods during the operation, short and intermediate term storage , Kerntechnik — DOI: 10.3139/124.110397

2013

• Kaliatka, A., Ognerubov, V., Vileiniškis, V., Ušpuras, E.. Analysis of the processes in spent fuel pools in case of loss of heat removal due to water leakage , Science and Technology of Nuclear Installations — DOI: 10.1155/2013/598975
• Kaliatka, T., Ušpuras, E., Kaliatka, A.. Modelling of QUENCH 03 and QUENCH 06 experiments using RELAP/SCDAPSIM code , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE21-15894
• Ušpuras, E., Kaliatka, A., Kaliatka, T.. Analysis of the accident with the coolant discharge into the plasma vessel of the W7-X fusion experimental facility , Fusion Engineering and Design — DOI: 10.1016/j.fusengdes.2013.03.012

2012

• Tarantola, S., Kopustinskas, V., Bolado-Lavin, R., Kaliatka, A., Ušpuras, E., Vaišnoras, M.. Sensitivity analysis using contribution to sample variance plot: Application to a water hammer model , Reliability Engineering and System Safety — DOI: 10.1016/j.ress.2011.10.007
• Kaliatka, A., Valinčius, M.. Modeling of pipe break accident in a district heating system using RELAP5 computer code , Energy — DOI: 10.1016/j.energy.2012.05.011
• Kaliatka, A., Uspuras, E., Kaliatka, T.. Pressure surge in Wendelstein 7-X experimental stellarator facility , Kerntechnik — DOI: 10.3139/124.110243
• Kaliatka, T., Povilaitis, M., Kaliatka, A., Urbonavicius, E.. 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
• Rimkevicius, S., Kaliatka, A., Valincius, M., Dundulis, G., Janulionis, R., Grybenas, A., Zutautaite, I.. Development of approach for reliability assessment of pipeline network systems , Applied Energy — DOI: 10.1016/j.apenergy.2012.01.015

2011

• Vileiniskis, V., Kaliatka, A.. Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module , Kerntechnik — DOI: 10.3139/124.110158
• Valinčius, M., Šeporaitis, M., Ušpuras, E., Kaliatka, A.. Experimental investigation and RELAP5 modeling of two-phase flow in horizontal rectangular channel , Heat Transfer Engineering — DOI: 10.1080/01457632.2011.556490
• Rimkevicius, S., Kaliatka, A., Valincius, M., Dundulis, G., Grybenas, A., Žutautaite-Šeputiene, I.. Development of methodology for assessment of reliability of pipeline networks , Proceedings of the IASTED International Conference on Power and Energy Systems, EuroPES 2011 — DOI: 10.2316/P.2011.714-129
• Kaliatka, T., Marao, A., Karalevičius, R., Ušpuras, E., Kaliatka, A.. Best estimate analysis of processes in RBMK fuel rods during the operation cycle , Mechanika — DOI: 10.5755/j01.mech.17.4.567
• Kaliatka, A., Uspuras, E., Vaisnoras, M.. Analysis of accidents leading to local flow stagnation in parallel fuel channels of RBMK-type reactors , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2011.08.060
• Uspuras, E., Kaliatka, A., Kopustinskas, V., Vaisnoras, M.. Use of the fast and CSM methods for analyzing uncertainties in hydraulic-shock modeling , Atomic Energy — DOI: 10.1007/s10512-011-9347-y

2010

• Marao, A., Kaliatka, T., Kaliatka, A., Ušpuras, E.. Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach , Kerntechnik — DOI: 10.3139/124.110069
• Kaliatka, A., Uspuras, E., Rimkevicius, S.. Best estimate analysis of station blackout case in RBMK-type reactors , International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
• Kaliatka, A., Vaisnoras, M., Uspuras, E.. Water hammer model sensitivity study by the FAST method , Procedia - Social and Behavioral Sciences — DOI: 10.1016/j.sbspro.2010.05.178
• Kaliatka, A., Uspuras, E., Vaisnoras, M., Krivoshein, G.. Analysis of decay heat removal from RBMK-1500 reactor in decommissioning phase by natural circulation of water and air , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2010.01.011
• Kaliatka, A., Ognerubov, V., Vileiniskis, V.. Analysis of the processes in spent fuel pools of Ignalina NPP in case of loss of heat removal , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2009.12.026
• Urbonas, R., Kaliatka, A., Kopustinskas, V.. Comparative sensitivity study of the RBMK-1500 reactor one group distribution header blockage accident model , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2010.06.004
• Urbonavičius, E., Kaliatka, A., Vileiniškis, V.. 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
• Pabarcius, R., Kaliatka, A., Marao, A.. Analysis of fuel rod behaviour during limiting RIA in RBMK plants , Kerntechnik — DOI: 10.3139/124.110105
• Kaliatka, A., Ušpuras, E., Vaišnoras, M., Krivoshein, G.. Removal of decay heat from shut-down RBMK-1500 reactor by natural circulation of water,Liekamosios branduolinio skilimo šilumos šalinimas sustabdytame RBMK-1500 reaktoriuje natūralios vandens cirkuliacijos būdu , Energetika
• Kaliatka, T., Kaliatka, A., Kačegavičius, T., Naujoks, D.. Analysis of the processes in the target cooling system of the W7-X fusion experiment , Kerntechnik — DOI: 10.3139/124.110094

2009

• Kaliatka, A., Kopustinskas, V., Vaišnoras, M.. Water hammer model sensitivity study by the FAST method,Hidraulinio smūgio modelio jautrumo tyrimas FAST metodu , Energetika
• Jusevičiute, A., Kaliatka, T., Kaliatka, A., Ušpuras, E.. The FEMAXI-6 code adaptation for modeling the processes in RBMK-1500 fuel rods,FEMAXI-6 programų paketo taikymas modeliuojant procesus, vykstančius RBMK-1500 šilumą išskiriančiuose elementuose , Energetika

2008

• Kaliatka, A., Uspuras, E., Rimkevicius, S.. Thermal hydraulic analysis of LOCA for justification of RBMK-1500 success criteria , Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
• Kaliatka, A., Urbonavicius, E., Uspuras, E.. Approach to accident management in RBMK-1500 , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2007.06.003
• Kaliatka, A., Ušpuras, E.. Specifics of RBMK core cooling in beyond design basis accidents , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2007.10.029
• Uspuras, E., Kaliatka, A.. Problems with cooling of overheated fuel channels in rbmk-type reactors , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE16-48266
• Kaliatka, A., Uspuras, E., Vileiniskis, V.. Deterministic analysis of natural circulation events at the ignalina NPP , Science and Technology of Nuclear Installations — DOI: 10.1155/2008/672519
• Kaliatka, A., Ušpuras, E., Vaišnoras, M.. Analysis of BDBA in RBMK-1500 reactor with long-term loss of heat removal from the core , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2008.09.002
• Kaliatka, A., Uspuras, E.. Development and testing of RBMK-1500 model for BDBA analysis employing RELAP/SCDAPSIM code , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2007.11.015
• Kaliatka, A., Uspuras, E., Vaisnoras, M.. Evaluation of heat removal from RBMK-1500 core using control rods cooling circuit , Science and Technology of Nuclear Installations — DOI: 10.1155/2008/430768
• Babilas, E., Urbonavicius, E., Rimkevicius, S., Kaliatka, A.. Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant , Kerntechnik — DOI: 10.3139/124.100540
• Kaliatka, A., Valinčius, M., Augutis, J., Krikštolaitis, R., Rimkevičius, S., Dundulis, G., Bakas, R.. Reliability assessment method of district heating network,Centralizuotu̧ šilumos tinklu̧ patikimumo vertinimo metodika , Energetika
• Uspuras, E., Rimkevicius, S., Kaliatka, A.. Ignalina Nuclear Power Plant safety issues , ISARC 2008 - Proceedings from the 25th International Symposium on Automation and Robotics in Construction
• Kaliatka, A., Ognerubov, V., Vaisnoras, M., Uspuras, E., Trambauer, K.. Analysis of beyond design basis accidents in spent fuel pools of the ignalina NPP , International Conference on Advances in Nuclear Power Plants, ICAPP 2008
• Jusevičiute, A., Kaliatka, A., Pabarčius, R., Ušpuras, E.. Analysis of RBMK-1500 fuel rod behaviour in case of reactivity initiating accidents , International Conference on the Physics of Reactors 2008, PHYSOR 08
• D'Auria, F., Gabaraev, B., Radkevitch, V., Moskalev, A., Uspuras, E., Kaliatka, A., Parisi, C., Cherubini, M., Pierro, F.. Thermal-hydraulic performance of primary system of RBMK in case of accidents , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2007.03.005
• Jusevičiuté, A., Kaliatka, A., Urbonavičius, E., DuŠkesas, G., Juodis, L., Sonnenburg, H.G.. Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500 , Kerntechnik — DOI: 10.3139/124.100558

2007

• Uspuras, E., Kaliatka, A., Urbonas, R.. Evaluation of non-regular means for heat removal from RBMK reactor core in case of BDBA , Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
• Jusevičiute, A., Kaliatka, A., Urbonavičius, E.. Processes in the fuel elements of nuclear power plants and their modeling,RBMK-1500 šiluma̧ işskiriančiuose elementuose vykstančiu̧ procesu̧ modeliavimas , Energetika
• Uspuras, E., Kaliatka, A.. Evaluation of weak heat conduction mechanism model for long-term LOCAs in RBMK-1500 , Nuclear Technology — DOI: 10.13182/NT07-A3821
• Kaliatka, A., Uspuras, E., Vaisnoras, M.. Benchmarking analysis of water hammer effects using RELAP5 code and development of RBMK-1500 reactor main circulation circuit model , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2006.11.010
• Ušpuras, E., Kaliatka, A., Augutis, J., Rimkevičius, S., Urbonavičius, E., Kopustinskas, V.. Safety analysis of beyond design basis accidents in RBMK-1500 reactors , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2007.01.011
• Vlaskin, V., Kryvošein, G., Dizik, B., Stebenev, V., Kaliatka, A., Urbanavičius, E.. Development of beyond-design-basis accident management guidelines for RBMK-1500 reactors of the INPP , Energetika

2006

• Ušpuras, E., Kaliatka, A., Augutis, J., Rimkevičius, S., Urbonavičius, E., Kopustinskas, V.. Probabilistic and deterministic analysis of BDBA in RBMK-1500 , Energetika
• Kaliatka, A., Uspuras, E., Vaisnoras, M.. Uncertainty and sensitivity analysis of parameters affecting water hammer pressure wave behaviour , Kerntechnik
• Uspuras, E., Kaliatka, A., Vileiniskis, V.. Development of accident management measures for RBMK-1500 in the case of loss of long-term core cooling , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2005.06.009
• Gailiušis, B., Kriaučiuniene, J., Ušpuras, E., Kaliatka, A., Vileiniškis, V.. Calibration of the hydrodynamic model of the Kaunas reservoir in accordance with analysis of uncertainty,Kauno HE tvenkinio hidrodinaminio modelio kalibravimas remiantis neapibrėžtumo analize , Energetika
• Uspuras, E., Urbonavicius, E., Kaliatka, A.. The specifics of RBMK core cooling at overheated conditions , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE14-89337
• Urbonavicius, E., Uspuras, E., Rimkevicius, S., Kaliatka, A.. 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
• Miškinis, V., Konstantinavičiute, I., Ušpuras, E., Kaliatka, A., Kopustinskas, V.. Application of the analysis of uncertainty to one-dimensional models of energy economy,Neapibrėžtumo analizės taikymas energetikos ekonomikos vienmačiu̧ modeliu̧ uždaviniams , Energetika
• Kaliatka, A., Rimkevicius, S., Uspuras, E., Urbonavicius, E.. Analyses of severe accident scenarios in RBMK-1500 , Kerntechnik — DOI: 10.3139/124.100298

2005

• Urbonavicius, E., Kaliatka, A.. 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
• Kaliatka, A., Vaisnoras, M., Vileiniskis, V.. Best estimate analysis of group distribution header blockage events in RBMK-1500 reactors , Kerntechnik — DOI: 10.3139/124.100255
• Kopustinskas, V., Urbonavičius, E., Kaliatka, A., Rimkevičius, S., Ušpuras, E., Bagdonas, A., Hellström, P., Johanson, G.. 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
• Kopustinskas, V., Urbonas, R., Kaliatka, A., Bolado-Lavín, R.. Input parameters distribution sensitivity study of RBMK-1500 reactor one group distribution header complete blockage scenario , Advances in Safety and Reliability - Proceedings of the European Safety and Reliability Conference, ESREL 2005

2004

• Bubelis, E., Kaliatka, A., Uspuras, E.. Development and validation of RELAP5-3D RBMK-1500 reactor model , Proceedings - International Meeting on Updates in Best Estimate Methods in Nuclear Installation Safety Analysis, BE-2004
• Uspuras, E., Kaliatka, A., Bubelis, E.. Modeling of void, fast power and graphite temperature reactivity coefficients measurements for the validation of RELAP5-3D RBMK-1500 reactor model , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2004.04.006
• Bubelis, E., Kaliatka, A., Uspuras, E.. RELAP5-3D code validation for RBMK-1500 reactors , Proceedings of the International Conference on Nuclear Engineering (ICONE12)
• Urbonas, R., Kaliatka, A., Uspuras, E., Vileiniskis, V.. RBMK-1500 accident analysis using BE approach , Proceedings - International Meeting on Updates in Best Estimate Methods in Nuclear Installation Safety Analysis, BE-2004
• Uspuras, E., Kaliatka, A.. Evaluation of "weak heat conduction mechanism" model for long-term LOCAs in RBMK-1500 , Proceedings - International Meeting on Updates in Best Estimate Methods in Nuclear Installation Safety Analysis, BE-2004
• Urbonas, R., Kaliatka, A., Ušpuras, E.. Comparison of two modern approaches for MBDA calculations of RBMK-type reactors , Kerntechnik — DOI: 10.3139/124.100195
• Uspuras, E., Kaliatka, A., Bubelis, E.. Validation of RELAP5-3D RBMK-1500 reactor model , Nuclear Energy — DOI: 10.1680/nuen.43.5.257.53136
• Uspuras, E., Kaliatka, A., Bubelis, E.. Validation of coupled neutronic/thermal-hydraulic code RELAP5-3D for RBMK-1500 reactor analysis application , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2004.06.002

2003

• Urbonas, R., Uspuras, E., Kaliatka, A.. State-of-the-art computer code RELAP5 validation with RBMK-related separate phenomena data , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(03)00150-X
• Dundulis, G., Kaliatka, A., Rimkevicius, S.. Ignalina accident localisation system response to maximum design basis accident , Nuclear Energy — DOI: 10.1680/nuen.42.2.105.37608
• Uspuras, E., Kaliatka, A., Bubelis, E.. Development of Ignalina NPP RBMK-1500 reactor RELAP5-3D model , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(02)00324-2
• Vileiniskis, V., Kaliatka, A.. Uncertainty and sensitivity analysis of MCPs' trip events at Ignalina NPP , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(03)00103-1

2002

• Urbonas, R., Kaliatka, A., Liaukonis, M.. Uncertainty analysis of RBMK-related experimental data , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE10-22490
• Bubelis, E., Kaliatka, A., Uspuras, E.. Relap5-3D code application for RBMK-1500 reactor core analysis , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE10-22450
• Kaliatka, A., Uspuras, E.. Thermal-hydraulic analysis of accidents leading to local coolant flow decrease in the main circulation circuit of RBMK-1500 , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(02)00153-X
• Kaliatka, A., Uspuras, E.. Development and evaluation of additional shutdown system at the Ignalina NPP by employing RELAP5 code , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(02)00208-X

2001

• Uspuras, E., Kaliatka, A., Dundulis, G.. Analysis of potential waterhammer at the Ignalina NPP using thermal-hydraulic and structural analysis codes , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(00)00292-2

2000

• Rimkevicius, S., Kaliatka, A., Urbonavicius, E.. Thermal-hydraulic evaluation of Ignalina NPP response to steam-line rupture , Nuclear Energy
• Kaliatka, A., Uspuras, E.. Benchmark analysis of main circulation pump trip events at the Ignalina NPP using RELAP5 code , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(00)00283-1

1999

• Almenas, K., Cesna, B., Kaliatka, A., Rimkevicius, S., Uspuras, E., Zvinys, E.. Thermal-hydraulic evaluation of the RBMK-1500 Accident Confinement System using CONTAIN 11AF , Nuclear Engineering and Design — DOI: 10.1016/S0029-5493(99)00055-2

1995

• Uspuras, Eugenijus, Kaliatka, Algirdas. Investigation of natural circulation phenomena in the main circulation circuit of the Ignalina NPP , Advances in Engineering Heat Transfer
• Ušpuras, E., Kaliatka, A., Almenas, K.. Verification of design characteristics of the RBMK-1500 accident confinement system , Nuclear Engineering and Design — DOI: 10.1016/0029-5493(95)01008-6