Publications
https://orcid.org/0000-0001-9042-0110
2026
- Impact of Hyperparameters on Surrogate Model Performance: Calcite Dissolution Under Geological Disposal Conditions , Applied Sciences — DOI: 10.3390/app16094252
2024
- THC Modelling of Bentonite Barrier of Geological Repository in Granite and Its Impact on Long-Term Safety , Applied Sciences — DOI: 10.3390/app14177851
2023
- Modelling of the Corrosion-Induced Gas Impact on Hydraulic and Radionuclide Transport Properties of Geological Repository Barriers , Minerals — DOI: 10.3390/min14010004
2022
- THM Response in the Near Field of an HLW Disposal Tunnel in the Callovo-Oxfordian Clay Host Rock Caused by the Imposed Heat Flux at Different Water Drainage Conditions , Minerals — DOI: 10.3390/min12101187
- Preliminary Study on Oxidation of Nuclear Grade Graphite , Chemical Engineering Transactions — DOI: 10.3303/CET2291072
2021
- Evaluation of the shielding properties of a new increased capacity storage cask for RBMK-1500 used fuel , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2021.103986
- Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage , Applied Sciences — DOI: 10.3390/app11167362
2019
- Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings , Science and Technology of Nuclear Installations — DOI: 10.1155/2019/8736173
- Impact of shield elements on the WWER-440 reactor pressure vessel activation , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2019.03.008
2018
- Estimation of the radiation doses during the dismantling of the equipment in Building 117/1 at the Ignalina NPP , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2018.07.018
2015
- Analysis of the radiological contamination of the RBMK-1500 reactor low salted water system , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2015.09.005
- Modeling of the radiation doses during dismantling of RBMK-1500 reactor emergency core cooling system large diameter pipes , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2015.04.034
2014
- Modelling of the radiological contamination of the RBMK-1500 reactor water purification and cooling system , Science and Technology of Nuclear Installations — DOI: 10.1155/2014/293158
2013
- Radiological characterization of the purification and cooling system of the 1st unit at ignalina npp,Ignalinos AE 1-ojo bloko vandens valymo ir aušinimo sistemos radiologinio užterštumo tyrimas , Energetika
- Prediction of radiation doses during the dismantling of the pressurized tank from emergency core cooling system of RBMK-1500 reactor , Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM — DOI: 10.1115/ICEM2013-96220
- Analysis of radwaste management alternatives during dismantling of Ignalina NPP systems with low level contamination , Kerntechnik — DOI: 10.3139/124.110396
International projects
Horizon Europe
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
The project aims to establish and clarify the benefits and added value of more aligned and harmonised regulations and standards for prioritised topics related to decommissioning and iMore
Horizon 2020
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
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
According to the projections based on likely remaining life-times of the World’s legacy nuclear fleet, the workload and budgets to be dedicated for nuclear decommissioning is going toMore
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
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
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)
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
SITEX aims at identifying the efficient means that should be developed through the establisment of a sustainable expertise function network within a European framework with the view tMore
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
Projects in Lithuania
EU Structural Funds
Some of the problems identified and tackled by the measure No 12-001-01-02-01 of Lithuania's Science Development Programme of the Ministry of Education, Science and Sport ofMore
On 7 February 2018, the Lithuanian Energy Institute (LEI) and the public institution Central Project Management Agency (CPVA) signed a contract for the implementation of the projeMore