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    • Virginijus Vileiniškis

    Laboratory of Nuclear Installation Safety (17)
    Position:
    Senior research associate
    ORCID:
    https://orcid.org/0000-0003-0106-6645
    Room number:
    251-AK
    Phone number:
    +37037401928
    Email:
    Virginijus.Vileiniskis@lei.lt

    Publications

    Scientific article

    2018

    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.

    2016

    Ušpuras E. [LEI], Rimkevičius S. [LEI], Urbonavičius E. [LEI], Kaliatka A. [LEI], Dundulis G. [LEI], Alzbutas R. [LEI], Stankūnas G. [LEI], Vaišnoras M. [LEI], Vileiniškis V. [LEI], Povilaitis M. [LEI], Kaliatka T. [LEI], Janulionis R. [LEI], Karalevičius R. [LEI], Voronov R. [LEI], Iešmantas T. [LEI], Kačegavičius T. [LEI]. Branduolių sintezės tyrimai Lietuvos energetikos institute In: Energetika. Vilnius: Lietuvos mokslų akademija, 2016, T. 62, Nr. 3, p. 102-123. ISSN 0235-7208.
    Kaliatka T. [LEI], Kaliatka A. [LEI], Vileiniškis V. [LEI]. Application of Best Estimate Approach for Modelling of QUENCH-03 and QUENCH-06 Experiments In: Nuclear Engineering and Technology. Korėja: Elsevier, 2016, Vol. 48, p. 419-433. ISSN 1738-5733.

    2014

    Kaliatka T. [LEI], Kaliatka A. [LEI], Vileiniškis V. [LEI], Ušpuras E. [LEI]. Modelling of QUENCH-03 and QUENCH-06 experiments using RELAP/SCDAPSIM and ASTEC codes In: Science and Technology of Nuclear Installations. 2014, Volume 2014, p. 1-13. ISSN 1687-6075.

    2013

    Kaliatka A. [LEI], Ognerubov V., Vileiniškis V. [LEI], Ušpuras E. [LEI]. Analysis of the processes in spent fuel pools in case of loss of heat removal due to water leakage In: Science and technology of nuclear installations. 2013, Vol. 2013, p. 1-7. ISSN 1687-6075.

    2010

    Kaliatka A. [LEI], Ognerubov V., Vileiniškis V. [LEI]. Analysis of the processes in spent fuel pools of Ignalina NPP in case of loss of heat removal In: Nuclear engineering and design. Elsevier, 2010, Vol. 240, iss. 5, p. 1073-1082. ISSN 0029-5493.

    Conference paper

    2022

    Coindreau O., Herranz L.E., Bocanegra R., Kaliatka A. [LEI], Vileiniškis V. [LEI], et al. Uncertainty quantification for a severe accident sequence in a sfp in the frame of the H-2020 project musa: first outcomes In: Proceedings of the 10th European Review Meeting on Severe Accidents Research (ERMSAR2022) May 16-19, 2022. Karlsruhe: Karlsruher Institut für Technologie (KIT), 2022, Log. No. 275, p. 1-12..

    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..

    2015

    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..
    Šutas A., Vileiniškis V. [LEI]. Uncertainty analysis of severe accident in the spent fuel pool In: 12th Annual international conference of young scientists on energy issues (CYSENI 2015), Kaunas, Lithuania, May 27–28, 2015. Kaunas: Lietuvos energetikos institutas, 2015, p. 418-427. ISSN 1822-7554.

    International projects

    Horizon 2020

    1
    R2CA project logo
    The Reduction of Radiological Consequences of design basis and extension Accidents (R2CA)
    Ongoing
    01.09.2019 - 31.08.2023

    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

    2
    MUSA project logo
    Management and Uncertainties of Severe Accidents (MUSA)
    http://musa-h2020.eu
    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
    NUGENIA+
    Preparing NUGENIA for HORIZON2020 (NUGENIA-PLUS)
    http://nugenia.org/about-nugenia/
    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

    2
    Advanced Safety Assessment: Extended PSA (ASAMPSA_E)
    http://asampsa.eu
    Completed
    01.07.2013 - 30.06.2016

    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

    3
    Code for European Severe Accident Management (CESAM)
    http://www.cesam-fp7.eu/
    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

    4
    European Fusion Development Agreement (EURATOM-LEI association)
    Completed
    01.01.2007 - 31.12.2013

    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
    IAEA logo
    Developing a Phenomena Identification and Ranking Table (PIRT) and a Validation Matrix, and Performing a Benchmark for In-Vessel Melt Retention (IAEA No J46002)
    https://www.iaea.org/projects/crp/j46002
    Ongoing
    01.07.2020 - 01.10.2024

    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

    2
    IAEA logo
    Advancing the State-of-Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water-Cooled Reactors (IAEA No i31033)
    https://www.iaea.org/projects/crp/i31033
    Ongoing
    07.06.2019 - 06.06.2024

    Description - Advanced understanding of the status and capabilities of multi-physics/multi-scale simulation tools in modeling propagation and consequences of severe accidents in advaMore