Articles in Scholarly Journals [Incomplete List]

1. Deterministic Analysis of Natural Circulation Events at the Ignalina NPP
   Science and Technology of Nuclear Installations, vol. 2008, Article ID 672519, 9 pages, 2008
2. Thermalhydraulic Characteristics in Annular Pebble Beds with Axial and Radial Gas Flows
   Experimental Heat Transfer, vol. 20, no. 2, pp. 185–196, 2007
3. Relap5 Analysis of Processes in Reactor Cooling Circuit and Reactor Cavity in Case of Station Blackout in RBMK-1500
   Science and Technology of Nuclear Installations, vol. 2007, Article ID 52850, 9 pages, 2007
4. Benchmarking analysis of water hammer effects using RELAP5 code and development of RBMK-1500 reactor main circulation circuit model
   Annals of Nuclear Energy, vol. 34, no. 1-2, pp. 1–12, 2007
5. Safety analysis of beyond design basis accidents in RBMK-1500 reactors
   Annals of Nuclear Energy, vol. 34, no. 5, pp. 356–373, 2007
6. Evaluation of pipe whip impacts on neighboring piping and walls of the Ignalina Nuclear Power Plant
   Nuclear Engineering and Design, vol. 237, no. 8, pp. 848–857, 2007
7. Structural integrity analysis of an Ignalina nuclear power plant building subjected to an airplane crash
   Nuclear Engineering and Design, vol. 237, no. 14, pp. 1503–1512, 2007
8. Updating of risk-informed ISI programme for Ignalina RBMK-1500 nuclear power plant in Lithuania: Results and challenges
   Nuclear Engineering and Design, vol. 236, no. 24, pp. 2547–2555, 2006
9. Hazard distribution and risk assessment in the network systems
   Stochastic Environmental Research and Risk Assessment, vol. 21, no. 1, pp. 51–61, 2006
10. Development of accident management measures for RBMK-1500 in the case of loss of long-term core cooling
    Nuclear Engineering and Design, vol. 236, no. 1, pp. 47–56, 2006
11. Experimental Investigation of Heat Transfer and Flow Mixing in Pebble Beds
    Heat Transfer Engineering, vol. 27, no. 8, pp. 9–15, 2006
12. Validation of RELAP5-3D RBMK-1500 reactor model
    Nuclear Energy, vol. 43, no. 5, pp. 257–264, 2004
13. Estimation of the Gas Gap Between the Channels and the Graphite Masonry in an RBMK-1500 Reactor
    Atomic Energy, vol. 96, no. 4, pp. 241–245, 2004
14. Reliability of the Coolant Flow Rate Measuring System at the Ignalina Nuclear Power Plant
    Atomic Energy, vol. 96, no. 6, pp. 403–406, 2004
15. Validation of coupled neutronic/thermal-hydraulic code RELAP5-3D for RBMK-1500 reactor analysis application
    Annals of Nuclear Energy, vol. 31, no. 15, pp. 1667–1708, 2004
16. Modeling of void, fast power and graphite temperature reactivity coefficients measurements for the validation of RELAP5-3D RBMK-1500 reactor model
    Nuclear Engineering and Design, vol. 232, no. 1, pp. 29–45, 2004
17. Development of Ignalina NPP RBMK-1500 reactor RELAP5-3D model
    Nuclear Engineering and Design, vol. 220, no. 2, pp. 159–178, 2003
18. Prediction of fuel channel—graphite gas-gap behaviour in RBMK reactors
    Nuclear Engineering and Design, vol. 223, no. 2, pp. 117–132, 2003
19. RELAP5-3D code validation in the neutron-dynamic analysis of transient processes taking place in RBMK-1500 reactors
    Nuclear Engineering and Design, vol. 224, no. 3, pp. 293–300, 2003
20. State-of-the-art computer code RELAP5 validation with RBMK-related separate phenomena data
    Nuclear Engineering and Design, vol. 225, no. 1, pp. 65–81, 2003
21. Thermal-hydraulic analysis of accidents leading to local coolant flow decrease in the main circulation circuit of RBMK-1500
    Nuclear Engineering and Design, vol. 217, no. 1-2, pp. 91–101, 2002
22. Development and evaluation of additional shutdown system at the Ignalina NPP by employing RELAP5 code
    Nuclear Engineering and Design, vol. 217, no. 1-2, pp. 129–139, 2002
23. Ignalina NPP RBMK-1500 gas gap evaluation
    Nuclear Engineering and Design, vol. 203, no. 2-3, pp. 195–207, 2001
24. Analysis of potential waterhammer at the Ignalina NPP using thermal–hydraulic and structural analysis codes
    Nuclear Engineering and Design, vol. 203, no. 1, pp. 1–12, 2001
25. Benchmark analysis of main circulation pump trip events at the Ignalina NPP using RELAP5 code
    Nuclear Engineering and Design, vol. 202, no. 1, pp. 109–118, 2000
26. Structural response analysis of the confinement system of the Ignalina nuclear power plant
    Nuclear Engineering and Design, vol. 191, no. 1, pp. 75–81, 1999
27. Thermal–hydraulic evaluation of the RBMK-1500 accident confinement system using CONTAIN 11AF
    Nuclear Engineering and Design, vol. 191, no. 1, pp. 83–99, 1999
28. Turbulent momentum and heat transfer in channel gas flow at high heat loads: A review
    Experimental Thermal and Fluid Science, vol. 4, no. 4, pp. 375–388, 1991
29. Investigation of heat transfer Prandtl number dependence by ? and ? solutions
    International Journal of Heat and Fluid Flow, vol. 11, no. 1, pp. 23–29, 1990