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    • Artūras Šmaižys

    Nuclear Engineering Laboratory (14)
    Position:
    Chief research associate
    ORCID:
    https://orcid.org/0000-0003-0384-3022
    Room number:
    54-BRK
    Phone number:
    +37037401890
    Email:
    Arturas.Smaizys@lei.lt

    Publications

    Scientific article

    2022

    Narkūnas E. [LEI], Šmaižys A. [LEI], Poškas P. [LEI], Šimonis A. [LEI], Naumov V., Ekaterinichev D.. Gamma Radiation Shielding Assessment Using Stochastic, Deterministic, and Experimental Methods for RBMK-1500 SNF Storage Cask In: Nuclear Technology . Philadelphia: American Nuclear Society, 2022, Vol. 208, Iss. 12, p. 1876-1889. Scopus . ISSN 0029-5450 , eISSN 1943-7471.
    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

    Šmaižys A. [LEI], Narkūnas E. [LEI], Poškas G. [LEI], Naumov V., Ekaterinichev D.. Evaluation of the shielding properties of a new increased capacity storage cask for RBMK-1500 used fuel In: Progress in Nuclear Energy. Oxford: Elsevier, 2021, Vol. 141, 103986, p. 1-11. ISSN 0149-1970, eISSN 1878-4224.
    Šmaižys A. [LEI], Narkūnas E. [LEI], Poškas G. [LEI], Poškas P. [LEI]. Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage In: Applied sciences. Basel: MDPI, 2021, Vol. 11, Iss. 16, 7362, p. 1-10. Scopus..
    Narkūnas E. [LEI], Šmaižys A. [LEI], Poškas P. [LEI], Naumov V., Ekaterinichev D.. Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel In: Nuclear Engineering and Technology. Daejeon: Elsevier, 2021, Vol. 53, p. 1869-1877. ISSN 1738-5733.

    2019

    Narkūnas E. [LEI], Poškas G. [LEI], Šmaižys A. [LEI]. Impact of shield elements on the WWER-440 reactor pressure vessel activation In: Annals of Nuclear Energy. Oxford: Elsevier, 2019, Vol. 130, p. 394-401. ISSN 0306-4549.
    Šmaižys A. [LEI], Narkūnas E. [LEI], Rudychev V., Rudychev Y.. Analysis of Some Computer Codes Used for Evaluation of Spent Nuclear Fuel Radiation Parameters In: Nuclear and Radiation Sofety. 2019, Vol. 3, No. 83, p. 44-50. ISSN 2073-6231.

    2017

    Šmaižys A. [LEI], Poškas P. [LEI], Narkūnas E. [LEI]. Evaluation of dose rate variation during very long term storage of RBMK-1500 reactor used fuel In: Annals of Nuclear Energy. 2017, Vol. 109, p. 192-198. ISSN 0306-4549.

    2016

    Narkūnas E. [LEI], Šmaižys A. [LEI], Poškas P. [LEI], Bartkus G. [LEI]. Modelling of the spatial distribution of the induced activities in the RBMK-1500 reactor graphite blocks and rings/sleeves In: Progress in Nuclear Energy. Oxford, England: Elsevier, 2016, Vol. 91, p. 265-276. ISSN 0149-1970.
    Narkūnas E. [LEI], Šmaižys A. [LEI], Poškas P. [LEI], Ragaišis V. [LEI]. Modelling of RBMK-1500 SNF storage casks activation during very long term storage In: Applied Radiation and Isotopes. Netherlands: Elsevier, 2016, Vol. 115, p. 100-108. ISSN 0969-8043.

    Conference paper

    2020

    Narkūnas E. [LEI], Šmaižys A. [LEI], Poškas P. [LEI]. Preliminary inventory of C-14 in irradiated graphite of Ignalina NPP unit 1 RBMK-1500 reactor In: EURADWASTE ’19 Conference Proceedings 9th European Commission Conference on EURATOM Research and Training in Radioactive Waste Management 4-7 June, 2019 Pitesti, Romania . Luxembourg: European Union, 2020, p. 682. ISBN 978-92-79-98750-2.

    International projects

    Horizon Europe

    1
    European Partnership on Radioactive Waste Management – 2 (EURAD-2)
    https://www.ejp-eurad.eu/
    Ongoing
    01.10.2024 - 30.09.2029

    EURAD-2 builds upon EURAD-1 and PREDIS to further implement a joint strategic programme of research, development and knowledge management activities at the European level, bringing toMore

    Horizon 2020

    1
    EURAD project logo
    European Joint Programme on Radioactive Waste Management (EURAD)
    https://www.ejp-eurad.eu/
    Completed
    01.06.2019 - 31.05.2024

    Following decades of RD&D in support of the safe management and disposal of radioactive waste, and building on the preparatory work of the recent EC JOPRAD project, a European JoiMore

    2
    Bentonite mechanical evolution (BEACON)
    http://www.beacon-h2020.eu/
    Completed
    01.06.2017 - 31.05.2022

    The overall objective of the project is to develop and test the tools necessary for the assessment of the hydro-mechanical evolution of an installed bentonite barrier and its resultinMore

    Seventh Framework Programme (FP7)

    1
    Assessment of Regional CApabilities for new reactors Development through an Integrated Approach (ARCADIA)
    http://www.projectarcadia.eu
    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
    New MS Linking for an AdvaNced Cohesion in Euratom Research (NEWLANCER)
    Completed
    01.11.2011 - 31.10.2013

    NEWLANCER project proposes to identify and implement effective and efficient actual solutions leading to enlarged NMS involvement in future Euratom Framework Programmes by strengtheniMore

    3
    Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste (CARBOWASTE)
    http://www.carbowaste.eu/
    Completed
    01.04.2008 - 31.03.2013

    Gas-Cooled Reactors (GCR), RBMK and some Material Test Reactors (MTR) make use of graphite as moderator of the fuel, structures of the core and/or thermal columns. During operation, tMore

    IAEA

    1
    Investigation of RBMK-1500 Spent Nuclear Fuel and Storage Casks Performance during Very Long Term Storage (IAEA No. 17275)
    Completed
    25.06.2012 - 20.06.2016

    The present spent nuclear fuel (SNF) management concept in the Lithuania foresees dry storage of SNF for 50 years. During this time the final SNF management concept shall be developedMore