Publications
https://orcid.org/0000-0002-6734-9966
Ernestas Narkunas
Darbovietės
2026
- Impact of Hyperparameters on Surrogate Model Performance: Calcite Dissolution Under Geological Disposal Conditions , Applied Sciences — DOI: 10.3390/app16094252
2025
- 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
2022
- Gamma Radiation Shielding Assessment Using Stochastic, Deterministic, and Experimental Methods for RBMK-1500 SNF Storage Cask , Nuclear Technology — DOI: 10.1080/00295450.2022.2092367
- 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
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
- 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
2019
- 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
- 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 inventory of 14C 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
- Updating of the public dose assessment approach for decommissioning related releases from the Ignalina NPP , Annals of Nuclear Energy — DOI: 10.1016/j.anucene.2016.02.028
- 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
- Numerical modelling of radionuclide inventory for RBMK irradiated nuclear fuel , Nuclear Engineering and Design — DOI: 10.1016/j.nucengdes.2014.06.014
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
- Neutron activation in the metal structures of an RBMK-1500 reactor , Nuclear Technology — DOI: 10.13182/NT09-A9239
- 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
2008
2005
- Modelling of activation processes for GR-280 graphite at Ignalina NPP , Radiation Protection Dosimetry — DOI: 10.1093/rpd/nci118
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
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
Seventh Framework Programme (FP7)
The CAST project (CArbon-14 Source Term) aims to develop understanding of the generation and release of 14C from radioactive waste materials under conditions relevant to waste packagiMore
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