Artūras Šmaižys

Nuclear Engineering Laboratory (14)
Chief research associate
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Scientific article


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.


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.
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.


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.


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.


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


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 2020

EURAD project logo

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


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)


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


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


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



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