Virginijus Vileiniškis

Laboratory of Nuclear Installation Safety (17)
Position:
Senior research associate
Room number:
251-AK
Phone number:
+37037401928

Publications

Scientific article

2018

Coindreau O., Jackel B., Rocchi F., Alcaro F., Angelova D., Bandini G., Barnak M., Behler M., Da Cruz D. F., Dagan R., Drai P., Ederli S., Herranz L.E., Hollands T., Horvath G., Kaliatka A. [LEI], Kljenak I., Kotsuba O., Lind T., Lopez C., Mancheva K., Matejovic P., Matkovič M., Steinbruck M., Stempniewicz M., Thomas R., Vileiniškis V. [LEI], Visser D.C., Vokač P., Vorobyov Y., Zhabin O.. Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool In: Annals of Nuclear Energy. Oxford, England: Elsevier, 2018, Vil. 120, p. 880-887. ISSN 0306-4549.

2016

Ušpuras E. [LEI], Rimkevičius S. [LEI], Urbonavičius E. [LEI], Kaliatka A. [LEI], Dundulis G. [LEI], Alzbutas R. [LEI], Stankūnas G. [LEI], Vaišnoras M. [LEI], Vileiniškis V. [LEI], Povilaitis M. [LEI], Kaliatka T. [LEI], Janulionis R. [LEI], Karalevičius R. [LEI], Voronov R. [LEI], Iešmantas T. [LEI], Kačegavičius T. [LEI]. Branduolių sintezės tyrimai Lietuvos energetikos institute In: Energetika. Vilnius: Lietuvos mokslų akademija, 2016, T. 62, Nr. 3, p. 102-123. ISSN 0235-7208.
Kaliatka T. [LEI], Kaliatka A. [LEI], Vileiniškis V. [LEI]. Application of Best Estimate Approach for Modelling of QUENCH-03 and QUENCH-06 Experiments In: Nuclear Engineering and Technology. Korėja: Elsevier, 2016, Vol. 48, p. 419-433. ISSN 1738-5733.

2014

Kaliatka T. [LEI], Kaliatka A. [LEI], Vileiniškis V. [LEI], Ušpuras E. [LEI]. Modelling of QUENCH-03 and QUENCH-06 experiments using RELAP/SCDAPSIM and ASTEC codes In: Science and Technology of Nuclear Installations. 2014, Volume 2014, p. 1-13. ISSN 1687-6075.

2013

Kaliatka A. [LEI], Ognerubov V., Vileiniškis V. [LEI], Ušpuras E. [LEI]. Analysis of the processes in spent fuel pools in case of loss of heat removal due to water leakage In: Science and technology of nuclear installations. 2013, Vol. 2013, p. 1-7. ISSN 1687-6075.

2010

Kaliatka A. [LEI], Ognerubov V., Vileiniškis V. [LEI]. Analysis of the processes in spent fuel pools of Ignalina NPP in case of loss of heat removal In: Nuclear engineering and design. Elsevier, 2010, Vol. 240, iss. 5, p. 1073-1082. ISSN 0029-5493.

Conference paper

2018

Kaliatka A. [LEI], Kaliatka T. [LEI], Vileiniškis V. [LEI], Ušpuras E. [LEI]. Best Estimate Approach for the Simulation of Reactor Core Overheating and Quenching Experiments In: Best Estimate Plus Uncertainty International Conference. Multi-Physics Multi-Scale Simulations with Uncertainty (BEPU 2018) May 13-18, 2018. Lucca, Italy: 2018, p. 1-12..

2015

Kaliatka A. [LEI], Vileiniškis V. [LEI], Ušpuras E. [LEI]. Analysis of heat removal accidents during the wet storage phase in Ignalina nuclear power plant In: The 26th international symposium on transport phenomena . Leoben, Austria: 2015, p. 1-8..
Šutas A., Vileiniškis V. [LEI]. Uncertainty analysis of severe accident in the spent fuel pool In: 12th Annual international conference of young scientists on energy issues (CYSENI 2015), Kaunas, Lithuania, May 27–28, 2015. Kaunas: Lietuvos energetikos institutas, 2015, p. 418-427. ISSN 1822-7554.

International projects

Horizon 2020

1
ELSMOR project logo

ELSMOR (towards European Lisencing of Small MOdular Reactors) aims to create methods and tools for the European stakeholders to assess and verify the safety of light water small modulMore

2
R2CA project logo

The Reduction of Radiological Consequences of design basis and extension Accidents (R2CA) is an EU H2020 project launched in September 2019. It will run for four years and is coordinaMore

3
MUSA project logo

The overall objective of the MUSA project is to assess the capability of SA codes when modelling reactor and SFP accident scenarios of GEN II, GEN III and GEN III+ reactor designs. ToMore

4
IVMR

The goal of the project is an analysis of the applicability and technical feasibility of the IVMR strategy to high power reactors, both for existing ones (e.g. VVER 1000 type 320 unitMore

Seventh Framework Programme (FP7)

1
NUGENIA+

The objective of the NUGENIA+ project is to support the NUGENIA Association in its role to coordinate and integrate European research on safety of the Gen II and III nuclear installatMore

2

Since 2013, LEI participated in the Consortium, managed by the Institut de Radioprotection et de Sûreté Nucléaire (IRSN), by implementing EU Seventh Framework Programme project AdvancMore

3

The Fukushima accidents highlighted that both the in-depth understanding of such sequences and the development or improvement of adequate severe accident management measures is essentMore

4

Today, about 80% of all energy produced comes from the fossil fuel (oil, carbon, and natural gas). European scientists are developing environmentally friendly, safe, and renewable eneMore

IAEA

1
IAEA logo

The Coordinated Research Project (CRP) aims to progress the understanding and modelling and simulation of major physical phenomena occurring in the strategy of In-Vessel Melt RetentioMore

2
IAEA logo

Description - Advanced understanding of the status and capabilities of multi-physics/multi-scale simulation tools in modeling propagation and consequences of severe accidents in advaMore