Publications
https://orcid.org/0000-0003-0384-3022
2025
- Investigation of nuclide inventory of cladding material irradiated in the Goesgen PWR core , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2024.111061
- Characterization of the Ignalina NPP RBMK-1500 reactors graphite: Review and summary of current situation and recent developments in respect to the reactor core dismantlement , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2025.105805
2024
- Investigation of Nuclide Inventory of Cladding Material Irradiated in the Goesgen Pwr — DOI: 10.2139/ssrn.4915314
2022
- A proposed approach for the evaluation of consequences of a large aircraft crash accident at an RBMK type reactor site during decommissioning , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2022.104135
- Gamma Radiation Shielding Assessment Using Stochastic, Deterministic, and Experimental Methods for RBMK-1500 SNF Storage Cask , Nuclear Technology — DOI: 10.1080/00295450.2022.2092367
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
- Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel , Nuclear Engineering and Technology — DOI: 10.1016/j.net.2020.11.022
- 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
- Impact of shield elements on the WWER-440 reactor pressure vessel activation , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2019.03.008
- Analysis of Some Computer Codes Used for Evaluation of Spent Nuclear Fuel Radiation Parameters , Nuclear and Radiation Safety — DOI: 10.32918/nrs.2019.3(83).05
2018
- Estimation of the inventory of <sup>14</sup> C and other key radionuclides in irradiated RBMK-1500 graphite based on limited measurements and full 3D core modeling , Radiocarbon — DOI: 10.1017/RDC.2018.122
2017
- Evaluation of dose rate variation during very long term storage of RBMK-1500 reactor used fuel , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2017.03.050
2016
- Modelling of RBMK-1500 SNF storage casks activation during very long term storage , Applied Radiation and Isotopes — DOI: 10.1016/j.apradiso.2016.06.015
- Modelling of the spatial distribution of the induced activities in the RBMK-1500 reactor graphite blocks and rings/sleeves , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2016.05.005
2014
- Modelling of rbmk spent nuclear fuel characteristics , International Conference on Nuclear Engineering, Proceedings, ICONE — DOI: 10.1115/ICONE22-31005
- The environmental impact assessment process for nuclear facilities: A review of the Lithuanian practice and experience , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2014.01.014
- Numerical modelling of radionuclide inventory for RBMK irradiated nuclear fuel , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2014.06.014
2013
- Thermal assessment of new Ignalina NPP casks for spent nuclear fuel storage at some abnormal conditions , Mechanika — DOI: 10.5755/j01.mech.19.2.4153
2012
- Progress of radioactive waste management in Lithuania , Progress in Nuclear Energy — DOI: 10.1016/j.pnucene.2011.09.008
2011
- Thermal analysis of new casks for spent nuclear fuel storage at the new ignalina NPP storage facility,Naujų panaudoto branduolinio kuro saugojimo konteinerių naujojoje Ignalinos AE saugykloje šiluminis įvertinimas , Energetika
- Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning , Kerntechnik — DOI: 10.3139/124.110169
- Experimental investigation of opposing mixed convection hear transfer in the vertical flat channel in a laminar-turbulent transition region , International Journal of Heat and Mass Transfer — DOI: 10.1016/j.ijheatmasstransfer.2010.09.004
- Naujų panaudoto branduolinio kuro saugojimo konteinerių naujojoje Ignalinos AE saugykloje šiluminis įvertinimas , Energetika — DOI: 10.6001/energetika.v57i3.2077
2010
- Evaluation of nuclear and radiation characteristics of steel disposal canister for RBMK-1500 spent nuclear fuel,RBMK-1500 panaudoto branduolinio kuro plieninio laidojimo konteinerio branduoliniu ir radiaciniu charakteristiku skaitinis vertinimas , Energetika
- Assessment of different mechanisms of C-14 production in irradiated graphite of RBMK-1500 reactors , Kerntechnik — DOI: 10.3139/124.110083
2009
- Numerical modelling of neutron activation processes in reactor RBMK-1500 structural elements: 3. Modelling of neutron activation proceses in fuel chanels employing modeled Neutron fluxes,Reaktoriaus RBMK-1500 konstrukcinių elementų neutroninės aktyvacijos skaitinis vertinimas: 3. Kuro kanalų neutroninės aktyvacijos vertinimas naudojant sumodeliuotus neutronų srautus , Energetika
- Neutron activation in the metal structures of an RBMK-1500 reactor , Nuclear Technology — DOI: 10.13182/NT09-A9239
2008
- Numerical modelling of neutron activation processes in the reactor RBMK-1500 structural elements 2. Numerical modelling of neutron activation processes in shielding and support plates,Reaktoriaus RBMK-1500 konstrukciniu̧ elementu̧ neutroninės aktyvacijos skaitinis vertinimas 2. Atraminiu̧ ir apsauginiu̧ plieno plokščiu̧ neutroninės aktyvacijos skaitinis vertinimas , Energetika
- Temperature distribution assessment for spent nuclear fuel casks at the ignalina NPP storage facility,Ignalinos AE saugyklos panaudoto branduolinio kuro konteineriu̧ temperatūru̧ pasiskirstymo i̧vertinimas , Energetika
2006
- Storage of spent nuclear fuel and perspectives for IT disposal,Panaudoto branduolinio kuro saugojimas ir jo laidojimo perspektyvos , Energetika
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant , Kerntechnik — DOI: 10.3139/124.100297
2005
- Modelling of activation processes for GR-280 graphite at Ignalina NPP , Radiation Protection Dosimetry — DOI: 10.1093/rpd/nci118
- Modelling of the shielding capabilities of the existing solid radioactive waste storages at Ignalina NPP , Radiation Protection Dosimetry — DOI: 10.1093/rpd/nci212
2003
- Experience from safety assessment of the existing storage facility for solid radwaste at Ignalina NPP , Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM — DOI: 10.1115/ICEM2003-4650
- Černobylio AE branduolinio kuro izotopų charakteristikų kitimo modeliavimas ir palyginimas su avarijos metu išmestų elementų tyrimo rezultatais , Energetika / Power Engineering
- Evaluation of neutron activation processes in RBMK-1500 reactor graphite , Lithuanian Journal of Physics
2002
- Ignalinos AE eksploatuojamos trumpaamžių kietujų radioaktyviujų atliekų saugyklos radiacinių charakteristikų įvertinimas , Energetika / Power Engineering
2001
- Experimental determination of radiation safety of spent nuclear fuel dry storage casks CASTOR and CONSTOR , Lithuanian Journal of Physics
- Konteinerių CASTOR RBMK-1500 ir CONSTOR RBMK-1500 su panaudotu branduoliniu kuru kritiškumo įvertinimas , Energetika / Power Engineering
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
Horizon 2020
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
IAEA
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
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