Virginijus Vileiniškis

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

2024

• F. Mascari, A. Bersano, M. Massone, G. Agnello, O. Coindreau, S. Beck, L. Tiborcz, S. Paci, M. Angelucci, L.E. Herranz, R. Bocanegra, Y. Pontillon, M. Berdai, O. Cherednichenko, A. Iskra, M. Nudi, P. Groudev, P. Petrova, F. Kretzschmar, F. Gabrielli, Z. Kanglong, V. Vileiniškis, T. Kaliatka, J. Kalilainen, M. Malicki, D. Gumenyuk, Y. Vorobyov, O. Kotsuba, P. Dejardin, M. Di Giuli, R. Thomas, I.V. Ivanov, F. Giannetti, M. D'Onorio, G. Caruso, M. Salay, T. Sevon. Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2023.110205

2023

• O. Coindreau, L.E. Herranz, R. Bocanegra, S. Ederli, P. Maccari, F. Mascari, O. Cherednichenko, A. Iskra, P. Groudev, P. Vryashkova, P. Petrova, A. Kaliatka, V. Vileiniškis, M. Malicki, T. Lind, O. Kotsuba, I. Ivanov, F. Giannetti, M. D'Onorio, P. Ou, L. Feiye, P. Piluso, Y. Pontillon, M. Nudi. Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2023.109796

2019

• Vileiniškis, V., Kaliatka, A., Ušpuras, E., Merrouche, D.. Uncertainty analysis of severe accident in the spent fuel pool , 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019

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

2016

• 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
• 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

2014

• 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
• Ognerubov, V., Kaliatka, A., Vileiniškis, V.. Features of modelling of processes in spent fuel pools using various system codes — DOI: 10.1016/j.anucene.2014.06.021

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 — DOI: 10.1155/2013/598975

2012

• Kaliatka, T., Ušpuras, E., Vileiniškis, V.. Best estimate analysis of PHEBUS FPT1 test using RELAP/SCDAPSIM code — DOI: 10.1115/ICONE20-POWER2012-54693

2011

• Vileiniskis, V., Kaliatka, A.. Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module

2010

• Urbonavičius, E., Kaliatka, A., Vileiniškis, V.. Integral analysis of large LOCA beyond design basis accident scenario in RBMK-1500 — DOI: 10.1016/j.nucengdes.2009.10.016
• Kaliatka, A., Ognerubov, V., Vileiniskis, V.. Analysis of the processes in spent fuel pools of Ignalina NPP in case of loss of heat removal — DOI: 10.1016/j.nucengdes.2009.12.026

2008

• Kaliatka, A., Uspuras, E., Vileiniskis, V.. Deterministic analysis of natural circulation events at the ignalina NPP — DOI: 10.1155/2008/672519

2006

• Uspuras, E., Kaliatka, A., Vileiniskis, V.. Development of accident management measures for RBMK-1500 in the case of loss of long-term core cooling — 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

2005

• Kaliatka, A., Vaisnoras, M., Vileiniskis, V.. Best estimate analysis of group distribution header blockage events in RBMK-1500 reactors

2004

• Urbonas, R., Kaliatka, A., Uspuras, E., Vileiniskis, V.. RBMK-1500 accident analysis using BE approach

2003

• Vileiniskis, V., Kaliatka, A.. Uncertainty and sensitivity analysis of MCPs' trip events at Ignalina NPP — DOI: 10.1016/S0029-5493(03)00103-1

2001

• Sapagovas, M., Vileiniškis, V.. The Solution of Two-Dimensional Neutron Diffusion Equation with Delayed Neutrons