Gintautas Poškas

Nuclear Engineering Laboratory (14)
Position:
Senior research associate
Room number:
61-BRK
Phone number:
+37037401883
Email:
Gintautas.Poskas@lei.lt

Publications

Scientific article

2021

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..

2019

Poškas G. [LEI], Poškas P. [LEI], Šimonis A. [LEI]. Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings In: Science and Technology of Nuclear Installations. London: Hindawi, 2019, p. 1-8. ISSN 1687-6075, eISSN 1687-6083.
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.

2018

Šimonis A. [LEI], Poškas G. [LEI], Poškas P. [LEI]. Estimation of the radiation doses during the dismantling of the equipment in Building 117/1 at the Ignalina NPP In: Annals of Nuclear Energy. Oxford, England: Elsevier, 2018, 121, p. 29-35. ISSN 0306-4549.

2015

Poškas G. [LEI], Zujus R. [LEI]. Modelling of the Radiological Contamination of the RBMK-1500 reactor control and protection system channels’ cooling circuit (http://dx.doi.org/10.4236/wjet.2015.33C001) In: World Journal of Engineering and Technology. Scientific research publishing, 2015, p. 1-5. ISSN 2331-4222.
Poškas G. [LEI], Zujus R. [LEI], Poškas P. [LEI]. Analysis of the radiological contamination of the RBMK-1500 reactor low salted water system In: Progress in Nuclear Energy. Oxford: Elsevier, 2015, Vol. 85, p. 707-712. ISSN 0149-1970.
Šimonis A. [LEI], Poškas P. [LEI], Poškas G. [LEI], Grigaliūnienė D. [LEI]. Modeling of the radiation doses during dismantling of RBMK-1500 reactor emergency core cooling system large diameter pipes In: Annals of Nuclear Energy. Oxford: Elsevier, 2015, Vol. 85, p. 159-165. ISSN 0306-4549.

Conference paper

2016

Poškas G. [LEI]. Radiologinio užteršimo vertinimas RBMK-1500 reaktoriaus kontrolės ir apsaugos kanaluose In: Šilumos energetika ir technologijos-2016: konferencijos pranešimų medžiaga, Kauno technologijos universitetas, 2016 sausio 28-29. Kaunas: Lietuvos energetikos institutas, 2016, p. 98-103. ISSN 2335-2485.

2015

Poškas G. [LEI]. Sistemų komponentų paviršinio radioaktyviojo užterštumo neapibrėžtumo vertinimo aspektai In: Šilumos energetika ir technologijos - 2015: konferencijos pranešimų medžiaga, Kauno technologijos universitetas, 2015 sausio 29-30 . Kaunas: Kauno technologijos universitetas, 2015, p. 120-124. ISSN 2335-2485.
Poškas G. [LEI]. Derivation of the mass factors for decommissioning cost estimation of low contaminated auxiliary systems. In: International Conference ECED 2013 – Eastern and Central European Decommissioning June 23 - 25, 2015. . Trnava, Slovakia: 2015, p. 1-9. ISBN 978-80-971498-5-7.

International projects

Horizon 2020

1
INNOvative tools FOR dismantling of GRAPHite moderated nuclear reactors (INNO4GRAPH)
Ongoing
01.09.2020 - 31.08.2023

The decommissioning of closed graphite moderated nuclear reactors worldwide is still in its early stages with the majority of reactors in “safe store” condition. For these reactors, tMore

2
EURAD project logo
European Joint Programme on Radioactive Waste Management (EURAD)
https://www.ejp-eurad.eu/
Ongoing
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

3
Thermal treatment for radioactive waste minimisation and hazard reduction (THERAMIN)
http://www.theramin-h2020.eu/
Completed
01.06.2017 - 31.05.2020

Safe management of radioactive waste is challenging to waste producers and waste management organisations. Deployment of thermal treatment in an optimised waste management lifecycle cMore

4
SITEX-II
Sustainable network for Independent Technical EXpertise of radioactive waste disposal – Interactions and Implementation (SITEX-II)
http://sitexproject.eu/index_2.html
Completed
01.06.2015 - 30.11.2017

The coordination action SITEX-II aims at implementing in practice the activities along with the interaction modes issued by the FP7 program SITEX project (2012-2013), in view of develMore

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