Algirdas Kaliatka

Laboratory of Nuclear Installation Safety (17)
Chief researh associate
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Scientific article


Graževičius A. [LEI], Kaliatka A. [LEI], Ušpuras E. [LEI]. Numerical investigation of two-phase natural convection and temperature stratification phenomena in a rectangular enclosure with conjugate heat transfer In: Nuclear Engineering and Technology. Daejeon: Elsevier, 2020, Vol. 52, Iss. 1, p. 27-36. ISSN 1738-5733.


Kaliatka A. [LEI], Ušpuras E. [LEI]. Heat removal from RBMK reactor core using non-regular means In: Nuclear Engineering and Design. Elsevier, 2019, Vol. 354, 110165, p. 1-13. ISSN 0029-5493.
Boucherit H., Kaliatka A. [LEI], Lounis A. Integrity control of an RBMK-1500 fuel rod locally oxidized under a bounding reactivity-initiated accident In: Nuclear Science and Techniques. Springer, 2019, Vol. 30, No. 1, p. 1-17. ISSN 1001-8042, eISSN 2210-3147.


Valinčius M. [LEI], Kaliatka T. [LEI], Kaliatka A. [LEI], Ušpuras E. [LEI]. Modelling of severe accident and in-wessel melt retention possibilities in BWR type reactor In: Science and Technology of nuclear Installations. London, England: Hindawi, 2018, Vol. 2018, p. 1-14. ISSN 1687-6075.
Kaliatka T. [LEI], Kaliatka A. [LEI], Hohorst J.K., Allison Ch. M.. Modelling of severe accidents in spent fuel pools, analysis of the heat-up of the fuel assemblies in the steam and air environment In: Nuclear Engineering and Design. Lausanne, Switzerland: Elsevier, 2018, Vol. 337, p. 341-350. ISSN 0029-5493.
Coindreau O., Jackel 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. [LEI], Kljenak I., Kotsuba O., Lind T., Lopez C., Mancheva K., Matejovic P., Matkovič M., Steinbruck M., Stempniewicz M., Thomas R., Vileiniškis V. [LEI], Visser D.C., Vokač P., Vorobyov Y., Zhabin O.. Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool In: Annals of Nuclear Energy. Oxford, England: Elsevier, 2018, Vil. 120, p. 880-887. ISSN 0306-4549.


Ušpuras E. [LEI], Rimkevičius S. [LEI], Kaliatka A. [LEI]. Application of the Best–Estimate Approach for the NPP Licensing Process In: International Journal of Contemporary ENERGY. 2015, Vol. 1, No. 2, p. 1-12. ISSN 2363-6440 .
Knoglinger E., Wölfl H., Kaliatka A. [LEI]. Heat transfer in the core graphite structures of RBMK nuclear power plants In: Nuclear Engineering and Design. 2015, Vol. 293, p. 413-435. ISSN 0029-5493.
Kaliatka T. [LEI], Ušpuras E. [LEI], Kaliatka A. [LEI]. Modelling of Water Ingress into Vacuum Vessel Experiments Using RELAP5 Code In: Journal of Fusion Energy. New York: Springer, 2015, Vol. 34, No. 2, p. 216-224. ISSN 0164-0313.

Marao A., Kaliatka T. [LEI], Kaliatka A. [LEI], Ušpuras E. [LEI]. Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach In: Kerntechnik. Vol. 75, Iss. 3, p. 72-80. ISSN 0932-3902.

Conference paper


Kaliatka A. [LEI], Vaišnoras M. [LEI], Valinčius M. [LEI], Kaliatka T. [LEI]. RELAP5 application for water hammer analysis in different thermal-hydraulic systems In: Proceedings 15th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics (ATE-HEFAT2021), Virtual conference, 26-28 July 2021.. Amsterdam: American Society of Thermal and Fluids Engineers, 2021, p. 1921-1926. ISBN 978-1-77592-216-2 .
Rimkevičius S. [LEI], Kaliatka A. [LEI], Pabarčius R. [LEI]. Heat transfer in pebble bed with longitudinal cylinders In: Proceedings 15th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics (ATE-HEFAT2021), Virtual conference, 26-28 July 2021.. Amsterdam: American Society of Thermal and Fluids Engineers, 2021, p. 1121-1125. ISBN 978-1-77592-216-2 .


Valinčius M. [LEI], Kaliatka A. [LEI]. Numerical study of in-vessel corium retention in BWR reactor In: Proceedings of an International Conference 6–9 June 2017 Vienna, Austria. Topical issues in nuclear installation safety. Safety demonstration of advanced water cooled nuclear power plants. Vienna: International Atomic Energy Agency, 2018, Vol. 1, p. 40-44. ISSN 0074-1884 ISBN 978-92-0-104618-5.
Kaliatka A. [LEI], Kaliatka T. [LEI], Vileiniškis V. [LEI], Ušpuras E. [LEI]. Best Estimate Approach for the Simulation of Reactor Core Overheating and Quenching Experiments In: Best Estimate Plus Uncertainty International Conference. Multi-Physics Multi-Scale Simulations with Uncertainty (BEPU 2018) May 13-18, 2018. Lucca, Italy: 2018, p. 1-12..
Kaliatka A. [LEI], Ušpuras E. [LEI]. Application of the BE Approach for the Analysis of Design and Beyond Design Basis Accidents In: Best Estimate Plus Uncertainty International Conference. Multi-Physics Multi-Scale Simulations with Uncertainty (BEPU 2018) May 13-18, 2018 . Lucca, Italy: 2018, p. 1-12..


Benabid R., Bouhlal A., Alzbutas R. [LEI], Kaliatka A. [LEI]. Level 1 probabilistic safety analysis of a typical research reactor In: Proceeding of African Conference on Research Reactor Utilization and Safety, 18-20 December, Accra, Ghana. GAEC and IAEA (International Atomic Energy Agency). Ghana: IAEA, 2017, p. 1-10..
Kaliatka T. [LEI], Ušpuras E. [LEI], Kaliatka A. [LEI]. Analysis of Station Blackout Accident in ABWR Reactor In: 17th International Topical Meeting on Nuclear Reactor Thermalhydraulics” (NURETH-17) September 3-8, 2017 Kinija . Sianas: 2017, p. 1-1..


Kaliatka A. [LEI], Kaliatka T. [LEI], Ušpuras E. [LEI], Mochizuki H.. Modelling of critical heat flux phenomenon in the boiling water reactors In: Proceedings of the 11th International Conference of the Croatian Nuclear Society Zadar, Croatia, 5-8 June 2016. . Zagreb, Croatia: Croatian Nuclear Society, 2016, p. 1-10. ISBN 978-953-55224-8-5 (USB).


Kaliatka A. [LEI], Vileiniškis V. [LEI], Ušpuras E. [LEI]. Analysis of heat removal accidents during the wet storage phase in Ignalina nuclear power plant In: The 26th international symposium on transport phenomena . Leoben, Austria: 2015, p. 1-8..
Kaliatka T. [LEI], Ušpuras E. [LEI], Kaliatka A. [LEI]. Integrated assessment of thermal hydraulic processes in W7-X fusion experimental facility In: The 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). Chicago, IL, USA: 2015, p. 6517-6529..

Popular science article


Augutis J. [LEI], Babilas E. [LEI], Dundulis G. [LEI], Kaliatka A. [LEI], Kaliatka T. [LEI], Krikštolaitis R. [LEI], Martišauskas L. [LEI], Rimkevičius S. [LEI], Pabarčius R. [LEI], Povilaitis M. [LEI], Stankūnas G. [LEI], Urbonas R. [LEI], Urbonavičius E. [LEI]. Scientific inheritance of Eugenijus Ušpuras In: Kerntechnik. Munchen: Carl Hanser Verlag, 2020, Vol. 85, Iss. 2, p. 72-81. ISSN 0932-3902.
Rimkevičius S. [LEI], Kaliatka A. [LEI], Urbonas R. [LEI]. In memoriam of Eugenijus Ušpuras (1955–2019) In: Nuclear Engineering and Design. Lausanne: Elsevier, 2020, Vol. 361, 110628, p. 1. ISSN 0029-5493.


Tonkūnas A. [LEI], Slavickas A. [LEI], Kaliatka A. [LEI]. The internship of Egyptian nuclear safety specialists at Lithuanian Energy Institute In: Energetika (Kronika). 2019, Vol. 65, No. 4, p. 10-12. ISSN 0235-7208.


Kaliatka A. [LEI], Kaliatka T. [LEI]. Experts from Lithuanian Energy Institute trained algerian specialists in the field of severe accident analysis In: Energetika (Kronika). Vilnius: Lietuvos mokslų akademija, 2018, T. 64, Nr. 2, p. 4-5. ISSN 0235-7208.


Kaliatka A. [LEI]. LEI contribution to transfer of knowledge on nuclear safety In: EUROSAFE news May 2017., 2017, Intern. prieiga


Kaliatka A. [LEI]. Programos „Horizontas 2020“ projektas IVMR In: Energetika. (Kronika) [EBSCO, IndexCopernicus, SCOPUS]. Vilnius: Lietuvos mokslų akademija, 2015, T. 61, Nr. 3-4, p. 6-6. ISSN 0235-7208.

International projects

Horizon 2020

ELSMOR project logo

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

R2CA project logo

The Reduction of Radiological Consequences of design basis and extension Accidents (R2CA) is an EU H2020 project launched in September 2019. It will run for four years and is coordinaMore


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

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)


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



In order to assess the ability of spent fuel assemblies to meet the requirements for transition from one back end fuel cycle step to another, certain characteristics have to be known More

IAEA logo

The Coordinated Research Project (CRP) aims to progress the understanding and modelling and simulation of major physical phenomena occurring in the strategy of In-Vessel Melt RetentioMore


Investigations will be performed for the two types of passive systems: when the final heat sink is water, when the final heat sink is air. In the frame of this IAEA CoordinMore

Other international projects


Project participants: Aslan Avcı Döküm Sanayi ve Ticaret A.Ş., Turkey Lietuvos energetikos institutas, LithuaniaMore