Position:
Chief research associate
Room number:
415-AK
Phone number:
+37037401911
Email:
Publications
Scientific article
2022
Kaliatka A. [LEI], Vaišnoras M. [LEI], Valinčius M. [LEI], Kaliatka T. [LEI].
RELAP5 application for water hammer analysis in different thermal-hydraulic systems
In: International Journal of Thermofluids . Oxford: Elsevier, 2022, Vol. 14, 100154, p. 1-13. Scopus ..
Ragaišis V. [LEI], Kaliatka T. [LEI], Poškas P. [LEI], Kaliatka A. [LEI], Šmaižys A. [LEI], Janulionis R. [LEI], Narkūnas E. [LEI], Sirvydas A. [LEI], Babilas E. [LEI], Rimkevičius S. [LEI].
A proposed approach for the evaluation of consequences of a large aircraft crash accident at an RBMK type reactor site during decommissioning
In: Progress in Nuclear Energy. Oxford: Elsevier, 2022, Vol. 145, 104135, p. 1-15. ISSN 0149-1970, eISSN 1878-4224.
2021
Elsalamouny N. [LEI], Kaliatka T. [LEI].
Uncertainty Quantification of the PHEBUS FPT-1 Test Modelling Results
In: Energies. Basel: MDPI, 2021, Vol. 14, 7320, p. 1-17. ISSN 1996-1073.
2019
Mazzini G., Kaliatka T. [LEI], Porfiri M. T..
Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios
In: Journal of Nuclear Engineering and Radiation Science. ASME, 2019, Vol. 5, No. 3, 030916, p. 1-7. ISSN 2332-8983, eISSN 2332-8975.
Mazzini G., Kaliatka T. [LEI], Porfiri M. T..
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts
In: Fusion Engineering and Design. Elsevier, 2019, Vol. 146, p. 510-513. ISSN 0920-3796.
Abramovic I., Pavone A., Moseev D., Lopes Cardozo N. J., Salewski M., and W7-X Team, Alzbutas R. [LEI], Dundulis G. [LEI], Kaliatka T. [LEI], Karalevičius R. [LEI], Povilaitis M. [LEI], Rimkevičius S. [LEI], Urbonavičius E. [LEI].
Forward modeling of collective Thomson scattering for Wendelstein 7-X plasmas: Electrostatic approximation
In: Review of Scientific Instruments. AIP, 2019, Vol. 90, No. 2, p. 1-12. ISSN 0034-6748.
Kaliatka T. [LEI].
Experience in Simulation of Severe accidents in Water Cooled Reactors
In: Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors. IAEA TECDOC. Vienna: IAEA, 2019, p. 38-52. ISSN 1011–4289 ISBN 978–92–0–102919–5.
2018
Pisano F., Cannas B., Jakubiwski M. W., Niemann H., Sitjes A. P., Wurden G. A., Alzbutas R. [LEI], Dundulis G. [LEI], Kaliatka T. [LEI], Karalevičius R. [LEI], Povilaitis M. [LEI], Rimkevičius S. [LEI], Urbonavičius E. [LEI].
Towards a new image processing system at Wendelstein 7-X: From spatial calibration to characterization of thermal events
In: Review of Scientific Instruments. Melville: AIP Publishing, 2018, Vol. 89, 123503, p. 1-10. ISSN 0034-6748, eISSN 1089-7623.
Dinklage A., Beidler C. D., Helander P., Fuchert G., Maaßberg H., Rahbarnia K., Sunn Pedersen T., Turkin Y., Wolf R. C., Alonso A., Andreeva T., Blackwell B., Bozhenkov S., Buttenschön B., Czarnecka A., Effenberg F., Feng Y., Geiger J., Hirsch M., Höfel U., Jakubowski M., Klinger T., Knauer J., Kocsis G., Krämer-Flecken A., Kubkowska M., Langerberg A., Laqua H. P., Marushchenko N., Mollén A., Neuner U., Niemann H., Pasch E., Pablant N., Rudischhauser L., Smith H. M., Schmitz O., Stange T., Szepesi T., Weir G., Windisch T., Wurden G. A., Zhang D., and the W7-X Team, (.., Alzbutas R. [LEI], Dundulis G. [LEI], Kaliatka T. [LEI], Karalevičius R. [LEI], Povilaitis M. [LEI], Rimkevičius S. [LEI], Urbonavičius E. [LEI], ...).
Magnetic configuration effects on the Wendelstein 7-X stellarator
In: Nature physics. London, England: 2018, Vol. 14, p. 855-860. ISSN 1745-2473.
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.
Conference paper
2021
Elsalamouny N. [LEI], Kaliatka T. [LEI].
Uncertainty and sensitivity analysis of the phebus fpt1 test simulation results
In: The 17th International Conference of Young Scientists on Energy and Natural Sciences Issues (CYSENI 2021) Kaunas, Lithuania, May 24-28, 2021. Kaunas: Lietuvos energetikos institutas, 2021, p. 448-449. ISSN 1822-7554.
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 .
2018
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..
2017
Kaliatka T. [LEI].
Implementation of QUENCH-10 experiment modelling experience for the modelling of severe accidents in spent fuel pools
In: Proceedings 23rd International QUENCH Workshop Karlsruhe Institute of Technology, October 17-19, 2017, Germany. Karlsruhe Institute of Technology: IAEA, 2017, p. 366-395..
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 T. [LEI], Ušpuras E. [LEI], Kaliatka A. [LEI].
Application of BE approach for the different nuclear fission and fusion facilities
In: 17th International Topical Meeting on Nuclear Reactor Thermalhydraulics” (NURETH-17) September 3-8, 2017. Kinija. Sianas: 2017, p. 1-1..
Kaliatka T. [LEI], Ušpuras E. [LEI], Allison Ch. M..
Modeling of quench 10 experiment on air ingress using relap/scdapsim mod 3.5
In: Proceedings of the 2017 25th International Conference on Nuclear Engineering ICONE25 July 2-6, 2017(ICONE25-66135), China.. Shanghai: ASME (The American Society of Mechanical Engineers), 2017, p. 1-7..
2016
Kaliatka T. [LEI], Mochizuki H..
Modeling of Station Blackout Accident in ABWR Reactor
In: Šilumos energetika ir technologijos-2016: konferencijos pranešimų medžiaga, Kauno technologijos universitetas, 2016 sausio 28-29. Kaunas: Lietuvos energetikos institutas, 2016, p. 89-97. ISSN 2335-2485.
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).
2015
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
2020
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.
2018
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.
2017
Kaliatka T. [LEI].
Alžyro branduolinės saugos specialistų stažuotė Lietuvos energetikos institute
In: Energetika (Kronika). Vilnius: Lietuvos moksl7 akademija, 2017, T. 63, Nr. 1, p. iii-iv. ISSN 0235-7208.
2016
Kaliatka T. [LEI].
Atomic energy researchers and research students acceptance program
In: Energetika (Kronika). Vilnius: Lietuvos mokslų akademija, 2016, T. 62, Nr. 1-2, p. 1-2. ISSN 0235-7208.
2015
Kaliatka T. [LEI].
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
In: Energetika. (Kronika)[EBSCO, IndexCopernicus, SCOPUS]. Vilnius: Lietuvos mokslų akademija, 2015, T. 61, Nr. 3-4, p. 1-2. ISSN 0235-7208.
International projects
Horizon 2020
1
Ongoing
01.06.2019 - 31.05.2023
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
Seventh Framework Programme (FP7)
1
Completed
01.11.2013 - 31.10.2016
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
2
Completed
01.10.2013 - 30.09.2015
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
3
Completed
01.09.2013 - 31.08.2016
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
4
Completed
01.04.2013 - 31.03.2017
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
5
Completed
01.06.2010 - 30.11.2010
Considering that the main objective of Researchers’ night is to bring researchers closer to the public at large in order to enhance researchers’ public recognition, the main aim of thMore
6
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
IAEA
1
Ongoing
12.08.2020 - 31.12.2024
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
2
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
3
Completed
29.10.2017 - 28.10.2020
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